NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION · 2020-01-07 · Erwin, TN 37650-9718 5. Docket...

NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION

MATERIALS LICENSEPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Codeof Federal Regulations, Chapter 1, Parts 30, 31, 32, 33, 34, 35, 36, 39, 40, and 70, and in reliance on statements and representationsheretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct,source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; todeliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This licenseshall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to'allapplicable rules, regulations, and orders of the Nuclear, Regulatory Commission now or hereafter in effect and to any conditions specifiedbelow.

Licensee

1. Nuclear Fuel Services, Inc. 3. License Number SNM-1 24, Amendment 78

2. 1205 Banner Hill Road 4. Expiration Data. July 31, 2009Erwin, TN 37650-9718 5. Docket No. 70-143

Reference No.

6. Byproduct Source, and/orSpecial Nuclear Materia[l

A. Uranium enriched up to100 w/% in the U235isotope which maycontain up to an averageof 10' grams plutoniumper gram of uranium,0.25 millicuries of fissionproducts per gram of uraniand 1.5 x 10-5 gramstransuranic materials(including plutonium),per gram of uranium,as contaminants.

B. Uranium enriched upto 100 w/% in the U233isotope

7. Chemrical and/or Physical 8. Maximum amount that Licensee'~rn j, May Po~ssess at Any One Time

I Under Th'is License

A As described in AAppendix B to-

KChapter 1 of the A

ýFlS license-.~application, excluding ~pyropho'ric fqrrnsA

B. 1 Any form, but only B. 1as residualcontamination fromprevious operations

B.2 Any form, as received B.2for analysis and/or forinput into developmentstudies

Enclosure 2

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2NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION

Lice-nse Number

7NM-124MATERIALS LICENSE Docket or Reference Number

SUPPLEMENTARY SHEET 70-1 43Amendment 78

C. Plutonium, 0. 1 As counting and C. 1calibration standards

0.2 As residual 0.2 As described in thecontamination and license application andholdup from an NFS report to theprevious operations. NRC transmitted by

letter dated January 21,1994 (NFS Document

~iNo. 28G94-001), and~NF Syeport datedOctob$pr 17, 1988 (NFSDocument No. 28G88-007)

0ý3 As.r~eceived for 0t31'analysis or for

-inpUt into d'eV61epment studies, anyform ~exceptLpyrophoric I

CA4 As waste resul ting CA.4ýfrom decontamination,and volume redu~ctio'nof equip~mentreceived'¾from other organhiza-tions, any form exceptpyrophoric

D. Transuranic Isotopes D. As waste resu~lting, D.from processingenriched uranium

E. Fission Products E. As waste resulting E.from processingenriched uranium

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U 3NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION

License NumberSNM-1 24

MATERIALS LICENSE Docket or Reference NumberSUPPLEMENTARY SHEET 70-143

Amendment 78

9. Authorized place of use: The licensee's existing facilities in Unicoi County, Tennessee, as described in'the referenced application.

10. This license shall b 'e deemed to contain two sections: Safety Conditions and Safeguards Conditions.These sections are part of the license, and the licensee is subject to compliance with all listedconditions in each section.

FOR THE NUIQLARcREGUVIAT6RYCMISO- -T Y OMISO

Date: ________ By-'Michael D. Tschiltz, Acting Deputy Director

:Fuel FacilityLiJbehsing DirectorateDivsion of Fuel Cycle, Safety

anhd.Safeguiards',Office of Nuclear Matenial Safety

:~:.and Safeguards

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- . 4NRC FORM 374A U.S. NUCLEAR REGULAT ORY COMMISSION

License NumberSNM-124


Amendment 78

.SAFETY CONDITIONS

S-1 For use in accordance with the statements, representations, and conditions in Chapters 1 through 8of the application submitted on the following dates, or as revised pursuant to 10 CFR 70.32or 70.72:

July 24, 1996, and supplements dated May 9 and November 14, 1997; March 13, March 25,June 23, July 23, August 7, August, 114,.August 28, September 4, September 11, September 15,September 25, September 28, Oqt6IbeK1,9, October ,21;, October 22, October 23, November 6,November 13, November 1,6,No6fember 20, Noveriber,24r December 18, and December 21, 1998;January 29, February 4,.February 10, February 16, FebruarV,24, April 20, April 23, May 21, July 30(NFS No. 21 G-99-005.8)j, July 30 (NFS No. 21 G-99-0093), AugUst-.. 3~, December 10, December 21,and December 29, 1999; January 25, March 31, July 6, August 18, Agust 23, September 1,November 3, December-5, Decemb er 8, December 14, December20 and December 27, 2000;January 11, January 12, March, 30, May 11, June 29, Octo~ber', an'ctober 25, 2001;February 21, February 28, M'6r'ch, 8;.March 12, April,3, April .4, August,23, September 13,October 18, Decembfer 17, and'Dece'ý.befýr 23 ýý2002; January 23, Febiruary 10, February 14,

February 27, Matdh 3, March" ad 0i''dh 13,'Ap'ril'14, April 16:6j'pril 22, July 31,September 26, andý October~ 27203 'JAuibia Ap'ril.,5,-September20,Nvme17December 3, 204(xetýcin1 . n relafin'b the review frequeVncy of operatingprocedures by the safety review corni~hittee), ~an b"ecemb6C316 ;'2004!f~ebruary 9, March 30,April 22 (MLO51 170273), Api~ril,2 (MLO-5I 2601 78)'April 29,- Ma'y 23, 'b1y 31, June 6, June 10,June 13, June 20, July 18, Sep5tember 13, Septemnber 29 , toiberZ2i7November 10, December 14,December 16 (ML05353031 I ), December 16 (MLO'601 105,19), anWd, Dcember 19, 2005; January 9,January 18, February ý20, March 10, March,24, May 2;. Ju~ne 16, QOdtober 18, November 8,December 1, and.Decem"ber 13, 2006; January 5, February 15 (except the change to Section 3.0 ofthe Physical protection Plan), April 13, May 23, and Auut, 23(artial approval, see ConditionSG-6.1), 2007.

For the Blended Low-Enriched Uranium (BLEU) PeatinFacility (BPF) and Oxide ConversionBuilding (OCB) and Effluent Processing Building (EPB): May 24, August 16, October 11,October 16, November 8, and December 3, 2002; March 8, April 4, June 20, September 3,September 5, October 23 (Attachment 1), October 31, November 5, December 5, andDecember 10, 2003, February 6, February 11, February 25, March 12, March 15, March 16,March 17, March 18, March 19, April 30, and May 21, 2004; April 13, and May 24, 2006.

S-2 Deleted by Amendment 59, dated January 2005.

S-3 Deleted by Amendment 5, dated May 2000.

S-4 Deleted by Amendment 59, dated January 2005.

S-5 5-5 Deleted by Amendment 59, dated January 2005.


"Licese NumberSNM-124

MATERIALS LICENSE Docket or Reference NumberSUPPLEMENTARY SHEET 70-1 43

Amendment 78

S-6 Deleted by Amendment 2, dated February 2000.

S-7 Deleted by Amendment 2, dated February 2000.

S-8 NFS shall conduct quarterly NOS audits of selected plant activities involving SNM such that SNMprocessing or storage areas are audited biennially. The purpose of the audits is to determine that:(a) site operations are conducted in compliance with license conditions, operating procedures, andposted limits, (b) administrative controls and, postings are consistent with NCSE, (c) equipment andoperations comply with NCSE, and (d) corrective aýctions. relative to findings of NCS inspections areadequate.

S-9 Subcritical parameter values based on experiments, unless they are from. the ANSI/ANS series 8standards, shall be not-]ess than that corre~ponding to k~ff of 0.98 ..or, alternatively, the factors inSection 4.2.3.1 of the~ license, application may be applied for uranidfm-water systems.

S-10 Nowtsadn ~t~escriiof setting failure limitsinSection 4.2.3.2 of the application, whendetermining sub riticality based ncmp cdeaktions the fafilure limit shall be no greaterthan the value codrresponding' 'to:kff =.95 for systems containing uranium enriched in 23 U above20%, keff = 95 for systems above 1i0% but be616w 2bo~icmn thtIenthghymdrtdkeff = .97 for systems above-10% b~ut below, 20% 'enrichi mentthat: are highly moderated, and keff=.97 for systems co ,ntaining u.ra~niuirh enriched in 236U" less than, 10%. As one acceptable method,the margin may be ,based,:ný,y alidation a'ga~in~st applicabl~e be'nchmark experiments using a one-sided 95% toleranice' limit ata 9 ,5% confidence levI l'ess.a ; 'dditional 0.015 Akeff.- The keff valuesof .95 and .97 above are ex~adt limiit valuesad pdo dnlot-itriply that compliance need only be shownto 2 significant figures. .Compliand6 with them shball 511ik~ for purdly--calculational inaccuracies, suchas Monte Carlo varianc~e~by meeting the limitkWith a margin in~jthidconservative direction of at leasttwo standard dleviations." Xf rounding shall be in the conse'vati've direction.

S-11 Notwithstanding Section 4.2.4.7of V h plctoj~o ýiai in which it is credible, and notunlikely, that critical masses or concentrations may accumulate in a solution confined to a favorablegeometry or poisoned vessel, and then be released to vessels of unfavorable geometry, transfershall be controlled by one of the following three general provisions for double contingency:

(1) multiple engineered hardware controls capable of preventing unsafe transfer; or

(2) at least one engineered hardware control capable of preventing unsafe transfer plus adetermination of safe conditions and actuation of transfer by an individual; or

(3) a design requiring independent actions by two individuals before transfer is possible, eachaction supported by independent measurements of material to be transferred, and adetermination of safe conditions. In this case , physical impediments should be included inthe system design which will prohibit either individual from performing both of the actionsintended to be performed independently.


Licese NumberNM-124


Amendment 78

S-i12

S-13

S-14

S-15

S-16

S-17

S-18

S-19

S-20

S-21

S-22

Prior to August 15, 1999, NES will implement fire protection procedures to minimize the threat offire, explosions, or related perils to process control and safety systems which could lead to anunacceptable release of hazardous material related to SNM or radiation that would threatenWorkers, the public health and safety, or the environment, as committed to in Section 6.2 of thelicense application.

Deleted by Amendment No. 4, March 2000.

Theresistance rating.

will be protected by barriers with an equivalent two hour fire

Active and administrative controls for flammable liquids and gasses must be operable in the firearea where flammable~liquids and gases are present during KAS IT processing.

Prior to August 15, 1999, -.,TProcess fire walls will b iipgraded to-meet FHA recommendations,as described in NFS Document- No. -,21 G-98-0198, NFS -Rsponse to equest for Additional FireSafety Information for the KASTProc~ess, datýddýDe'cerMbdri8, 1998.

Prior to December 31, 1999, NES shall protect KAST procdss areas and special nuclear materialvaults from lightning by installing a lightning pro~tection,$ystem, in accordance with the standard"Lightning Protection Code;",NFPA 780.

Prior to August 1 5, 1999, fix~ed co 'mbustible gas~detectors in the shall becapable of alarm irfg locally and ~at a constantly?'Manned location.

Prior to December 312,14999 NFS will upgra~de. 61) proces's area sp rinkler systems to alarm at aconstantly manned location ý

Deleted by Amendment 24, April 2001.

Deleted by Amendment No. 64, dated August 2005.

NES shall perform the following steps as detailed in the NFS Bulk Chemical TankAnalysis (NESDocument 21 G-99-0207).

A. By July 31, 2001, for 9NFS shall:

1. Perform a 100 percent visual internal tank inspection.

2. Provide details of internal nozzle penetrations and welds, add these details todrawing, then recalculate estimated service life.

3. Conduct liquid penetrant examinations of floor-to-shell welds.


Licese NumberSM-1 24

MATERIALS LICENSE Docket or Reference Number.SUPPLEMENTARY SHEET 70-143

Amendment 78

4. Perform a magnetic flux leakage inspection of 100 percent of the tank bottom todetect underside corrosion and pitting.

B. By September 1, 2001, NFS shall provide a written plan that details the continuedinspection and testing of bulk chemical storage tanks that will provide a documentedsafety basis for bulk storage tanks.

C. Prior to December 31,.,201i,. NFS shall conduct a second set of ultrasonic thickness tests

)These readingsý will provide data' thiat`Will allo w the corros~ion' r Iate .and tankwall thickness to be determined. The ,shall also havean internal inspection and a liquid penetrant examinatidn of, the floor-to-shell welds.

D. As req uiredby code,,each tank shall have'a pemnn nameplateatchdseiyn

tank op 6rating conditions" The American SoldietV..'f Mechanical Engineers, "Boiler andPress u'hVessel Cod~e', SectiontyW, 'ýlý'Markingt1rlsts necestary' information fornamepl~Tfes. ~

S-23 NFS shall inform the, NRC within 30 days of receipt of a vio~tion, notice fr~Ii the State of TennesseeDivision of Air Polluti6' A or Wafer Pollution Control,~ or~ recep qfmdfe euirements of the state-issued National Pollutant Discharge Eliminafio Syseip (NDS.ofrmnoifi r

S-24 The licensee shall maintain and execute the response measures in the Emergency Plan, Revision 10,transmitted by letter dated May 22, 2006, or as further revised by the licensee consistent with 10 CFR70.32(i).

S-25 NFS may make changes (modifications, additions, or remrovals) to the site, structures, processes,systems, equipment, components, computer prbgra~ms, an6`6 activities of personnel without licenseamendment, provided that the proposed change does-not involve:

(1) the creation of new types of accident sequences that, unless mitigated or prevented, wouldexceed the performance requirements of 10 CFR 70.61 and have not previously beendescribed in the ISA summary;

(2) the usage of new processes, technologies, or controls for which NFS has no priorexperience;

(3) the removal, without at least an equivalent replacement of the safety function, of an itemrelied on for safety that is listed in the ISA summary;

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION



Amendment 78

(4) the alteration of any item relied on for safety, listed in the ISA summary, that is the sole itempreventing or mitigating an accident sequence that exceeds the performance requirementsof 10 CFR 70.61; and

(5) a change to the conditions of this license or Part I of the license application.

Proposed changes not meeting all of the above, criteria shall be deemed to require NRC approval byamendment. As part of the application for a'mendfment, NFS shall perform an ISA for the change andsubmit either an ISA summary,,or applIcable, changes to4a "p'rk` existing ISA summary. NFS shall alsoprovide any necessary revisions toi its environmental report.

Proposed changes requiring revision of applicable safety or environme~ntal bases, but not requiring anamendment to the license in accordance with the above criteria, shall'Wb~reviewed and approved by theNFS safety review comfmittee.' The, internally authorized change*documentation shallyprdvide the basis for determining tha~tli&'cridange wi!ll _e consistent with thecriteria (1) through (5)-above.

For any internally authorized change implement'e~d by .NF'S ýwivthout NRC approval pursuant to thislicense condition, NFS shall submit annually to the NRC bkalchangegs t h ISAsmayoaprior existing ISA. lnmaddition, NFS will submit annually a, brief ,surnraryo9f-all internally authorizedchanges not requiringýp~rior NRC approval. NFS wil~l submit by.'January 30,,,, of each calendar year therevisions to the ISA Summary and the sum ma ryof all linternally authorized changes not requiring NRCapproval.

S-26 Prior to engaging in the decommissioning acti~vities Specified, in Section 1.6.6 of the license applicationdated November 16,1998, NFS must determine the status of th.',procedures and activities plannedwith respect to 10 CFR 70.38(g)(1).-.If required, NFS must submit a decommissioning plan to the NRCfor review and approval prior to initiatiing such actioflsý

S-27 By January 30 of each cale ndar year, the licensee shall update the safety demonstration sections ofthe license application to reflect the licensee's current operations and evaluations. The updates shall,as a min~imum, include information for the health and safety section of the application as required by 10CFR 70.22(a) through 70.22(f) and 70.22(i) and operational data on environmental releases asrequired by 70.21.

S-28 Deleted by Amendment 31, October 2001.





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NRC FORM 374A U.S. NUCLEAR REGU7LATORY COMMISSION9

Licese NumberNM-1 24


Amendment 78,

S-33 Deleted, by Amendment 31, October 2001.






S-39 For individual fire areas in the ,NFS shallcomplete a nuclear criticality safe Ity analysi's demionstrating that-a cri Itic'ality a cciden~t resulting from acredible fire, analyzed in the Fire Hazards Analysis, or from the6 consequenices of fire-suppressionactivities, is highly unlikely. This may be done by:- (i) demo nstrating that a criticality resulting from anaccident sequence initiated by a major fire would be highly unlikely, or (ii) dýemonstrating that a majorfire is highly unlikely. NFS shall also review all NCSAs potentially affected'b the installation ofautomatic fire suppression systems and assoc ,iated facil,1.ity modifications to 'determine their effect onthe safety basis. For the analyses specified by this safety condition,, a majo r fire is defined as onewhich would affect, two or more process Areas in

S-40 By December 31, 1999, for KAST process structures and equipment, NES shall classify all items reliedon for nuclear criticality safety as either safety-r~elated or configuration-controlled equipment. Safety-related equipment (SRE) is defined as-active or passive e~ngineered-controls that are relied on toprevent nuclear criticality in accordance with the double contingency principle, and whose operationcan change with time such th'at the equipment might not perform its function. Config uration-control ledequipment (OCE) is defined as's structures, systems, or components for which either:

(i) some characteristic is relied on for double 'contingency, which~characteristicý will not changewith time as a result of accidents identified in the ISA, or

(ii) the control is supplemented by one or more controls as one leg of the double contingencyprinciple.

For SRE items, maintenance, calibration, testing, and/or inspection shall be performed in accordancewith written, approved procedures to assure continued reliability and functional performance. SRE thathas undergone maintenance will be functionally tested, c alibrated, or inspected (as applicable) prior torestart.

CCE will be functionally tested, maintained, calibrated, and/o r inspected periodically in accordance withwritten, approved procedures, with thefollowing exceptions:

CE that has no credible mechanism to fail beyond the conditions assumed in the bounding normal casedoes not require functional testing, calibration, or preventive maintenance.

II


7Licese NumberSM-1 24


Amendment 78

CCE that is tested by every use and that is used with sufficient frequency to ensure adequate reliabilitydoes not require functional testing or preventive maintenance, unless it contains parts that degradeover time.

OCE items will be inspected after initial installation, replacement, and by periodic NOS audits.

S-41 Deleted by Amendment 32, February 2002.

S-42 Deleted by Amendment 5, dated April 200.

S-43Delted y Aendmnt 2, dted-Marh 20 1

S-44 Deleted by Amendment 22, dated March 2001.

S-45 Deleted by Amendment f32, February. 2002.

S-46 By August 1, 2000, NFS shall submrit a Criticality" Safety Up gra~de Program (CSUP) Plan to NRC forreview and approval. This CSUP shall address ,tlhe foll'owing elements, at a minimum:

1. All Nuclear Criticality Safety Analyses (NOSAs) performed or revised after May 1, 2000, shall beupgraded as follows:

(a) the criticality safety basis shall be conso'lidated'in a single integrated and self-consistentdocument;

(b) all engineered structdres, systems, 'add! ?mone nts' and ol~erbtor actions relied on to meet thedouble contingency otinciple shall be clearly identified fo a6ch accident sequence leading tocriticality;

c) the basis for double contingency shall b~e-clearly documented, including technicaldocumentation of the independence and unlikelihood of control failure;

d) normal and credible abnormal operating conditions shall be clearly identified; and

(e) all assumptions credited for criticality safety shall be supported by documentation consisting ofa technical demonstration of the adequacy of the assumptions rather than reliance onengineering judgement or historical practices.

2. By August 1, 2001, management procedures defining the criticality safety program shall beupgraded to the following standards:




Amendment 78

(a) the NOSAs consist of self-contained safety basis documents, sufficiently detailed to permitindependent reconstruction of results by a knowledgeable criticality safety specialist withoutreliance on additional site-specific or historical knowledge;

(b) the standard technical practices used in designing calculational models are specified insufficient detail. to ensure that the resulting NCSAs are uniform with respect to modelingreflection, determining the optimal range.,of moderation, treating interactions, accountingfor dimensional tolerance~sý ~," a banybbund-in approximations in models;

'(c) evaluation of accident sequences take. potential interaction between fire and chemical safetyand criticality safety into account;

(d) the scope, conduct, and documentation of independent reviews of NCSAs are specified;

(e) the applicability of code~validation(s) to the specific cases being ,modeled is evaluated,includinga adetermination. of the ad ,equ b-a cy ofthsbriclmain

(f) engineered as oppose'd _16ad'mrrinistrativ~ 6controls 'are used as i:'iý preferred method ofensuring, criticalitj -fetý;wnereve-r practicable."',,'' i

(g) the basis for using,ýdrinistratie instead of -engineered, control§2 is documented as part ofthe NCSA; a~nd ' .

(h) a problem reporting and corrective action program is establisihed to ensure theeffectiveness of the criticality safety program and critical it' 'controls, and to ensure thateffective corrective actions and lessons learned areflo~wed down into appropriateimplementing documhents. This program shall ýinclude the re-evaluation of the unlikelihoodof control failure, as parttof the double contingency safety basis, as control failure data isgenerated.

S-47 By July 31, 2001, NFS shall submit to NRC for approval the following information related to the North.Site Decommissioning Plan:

a) area factors for volumetrically-contamninated soils and the technical basis for those areafactors,

(b) actual Minimum Detectable Concentrations (MDCs) for the Nal detector and the technicalbasis for those MDCs,

c) appropriate investigation levels (ILs) for static and scan survey measurements that will beperformed in impacted areas.

1 U 12NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION

"Licnse NumberNM-124


Amendment 78

S-48 Notwithstanding the Derived Air Concentration (DAC) and Annual Limit on Intake (ALl) listed inAppendix B to 10 CFR Part 20, the licensee may use adjusted DAC values and adjusted ALl valuesspecified in International Commission on Radiation Protection (ICRP), Publication 68 (Annalls of theICRP Volume 24, No.4).

S-49 NFS shall utilize, for setpoint determinations, conservative engineering analyses which account forsafety limits, instrument and system accuracies, response times, instrument drift, manufacturer's dataand operating experience. The analysis for each safety setpoint shall be a formal calculation and shallbe documented for each IROFS interlock and alarm.

S-50 By February 13, 2004, NFIS shall submit a revised BPF Integrated Safety Analysis Summary thatincorporates changes res~ulIting from NRC review questions documented in NFS letters datedSeptember 3, September 5, October 31, November 5, November 7, December 5,. and December 10,2003.

S-51 The licensee shall submit a revised OCB/EPBý Integrated Safety Analysis Summary that incorporatesall changes to date, at least fifteen (15) days prior to the NRC's Operational Readiness Review.

S-52 For the approval of procedures,, the licensee shall ensure that conc'u ,rrence' with the Safety andSafeguards Review Council (SSRC) Chair's selection of the minimu'm designated SSRC reviewers isobtained from the entire SSRC and documented before procedures are approved. Documentationmay be in the form of-si~gnature sheets, emails, memos ~or other means acceptable to the SSRC, andmay include concurrence in advance..by individual SSRC members for individual procedures or classesof procedures.

SAFEGUARDS CONDITIONS~

Section-i .0- ABRUPT LOSS DETECTIONe (For SSNM.,Only):

SG-1. 1 Notwithstanding the req uirement of 10 CFR 74.53(b)(1) to have a process detection capability foreach unit process, the process units listed in Section 1.1.5.2 of the Plan identified in Condition SG-5.1 shall be exempt from such detection capability, and the licensee's process monitoring systemshall be comprised of the control units described in Section 1.3 (and all sub-sections therein) of theabove mentioned Plan.

Section-2.0 -- ITEM MONITORING (For SSNM Only):

SG-2.11 Notwithstanding the requirement, of 10 CFR 74.55(b) for item monitoring tests for all item categoriesexcept those identified by 10 CFR 74.55(c), and notwithstanding statement '#8 of ,Section 2.3.3 Of thePlan identified in Condition SG-5.1. the licensee is exemo~t from

icn stanaaras are noi, nowever, exer


Lice nse NumberSNM-1 24


Amendment 78

Section-3.0 -- ALARM RESOLUTION

SG-3.1 The licensee is authorized to continue material processing operations in Control Units 1, 3, 4, 5,and 15 under process monitoring alarm conditions. During the continuation of processingoperations, the measures contained in Section 3.1.1 of the Plan identified in Condition SG-5.1 shallbe implemented.

Section-4.0 -- QUALITY ASSURANCE (SSNM & LEU):

SG-4.1 Notwithstanding the requiremen ,ts o1f 10 CFR 74.31(, c)(2) fo r LEU and 10 CFR 74.59(d)(1) forSSNM to maintain a system,,of measurements to substantiate both the element and fissile isotopecontent of all SNM received, inventoried, shipped or discarded, SNMV measured by the licensee forU-233, U-235, orPu-?349`by non-destructive assay techniques need not be measured for totalelement if the calculated ,element content is based on the'measure'd isotope content which, in turn,is traceable to an ibtopic arbundance measurement at the -area of gederation.

rglSG-4.2 Notwithstandingthle requirement of 10 CFR 74ýi,59(,e)(8),!tbo-stablish a~nd5 maintain control limits at

the 0.05 and 0.001 levels of significance for all HEU, rdib measurenidts, the licensee may useone and two scal~divisions as beind"ýequivalentt~oth~eýý6 05 and 0.001. control levels, respectively,for mass measu~rements. ~

SG-4.3, Notwithstanding Section 4.5.1 of the Plan identifie in Condition SG-5. 1, which states that aphysical inventory of SSNM is conducted at an' interval of at least eve6ry six calendar months with nomore than 185 da's e,;lapsing between 'any two co~nsecutive inventories, the licensee is granted anextension of time from April 3, 2000, to June 2,. 2000, for conducting its SSNMV physical inventory.This condition automatically expires on June, 5,, 2000.

SG-4.4 Notwithstanding the requirement. of 10 CFR 74.59(f)(2)(viii) to remeasure, at the time of physicalinventory, any in-process SSNM for which ~the validity 'fi a prior measurement has not beenassured by tamper-safing, the licensee may book for HEU physical inventory purposes:

(1) process holdup quantities determined by NDAmeasurements performed prior to the start of an inventory, in accordance with the controlsdescribed in Sections 4.5.2.3.1 and 4.5.2.3.2 of the Plan identified in Condition SG-5.1;

(2) pre-listed feed material to the process that is introduced into process prior tothe start of an inventory, in accordance with the controls described in Section 4.5.2.3.2 of the.Plan identified in Condition SG-5.1; and

(3) holdup quantities determined by the most recent NDA measurements, inaccordanc-e with the controls described in Section 4.5.2.3.1 of the Plan identified inCondition SG-5.1.


License Number,SNM-1 24


Amendment 78

SG-4.5 Notwithstanding the requirements of 10 CFR 74.59(f)(1) and 74.59(f)(2)(viii) to measure andinventory all SSNM, the licensee may determine process exhaust ventilation system inventoryquantities in accordance with Section 4.5.3.5 of the Plan identified in Condition SG-5.1.

SG-4.6 Deleted by Amendment 65, dated November 16, 2005..

SG-4.7 Deleted by Amendment 65, dated November 16, 2005.

SG-4.8 The SNMV content of liquid waste di'scarded from,.c'ollection tanks shall be analyzed andrecorded at measured val'ues. The measuremeri tm hodls must have a greater sensitivity thanthe concentration of th,6 ,sample aliquot analyzed, except when the quantity discarded does notexceed 50 grams LJ-235 per month from Plant I (HEU) and "does not exceed 10 grams U-235per month from MBA-4 (LEU) through those discard batches where the sample aliquotconcentration is, les`s4tha.n the sensitivity of the method.

S0-4.9 Notwithstandifng the statementt'in Section 5.9, ofth W&P6 ,n identified in Condition S0-5.2,pertaining to-bias corrections tob inventory differenc6ID) values, the licensee shall comply withSection 4,.3.11.bf11 such Plan with respect to determining, any bias corrections to IDS.

SG-4. 10 Notwithstanding the requirements of 10 CFR 74.59(e)(8) relative to actions to be taken whenreplicate measurement data exceed a 0.001 control limit, the' licensee shall comply withSection 4.4.1.7.3.4 of the Plan identified in Condition SG-5A.1

SG-4.11 Notwithstanding~ the requirement of, 10 CF~R-74.59(e)(4) that allows the pooling of, data whichhas been showrh6t be not signiflcaintlyýdiff&reht orvthe basis of appropriate statistical tests, thelicensee may pool data from equivaleritsbdals without testing>41

S0-4.12 Notwithstanding the requirement of 10 CIFR 74.59(e)(5) to evaluate all program datai toestablish random error variances, limits for systerfiatic error, etc., the licensee may randomlyselect a partial quantity of bulk measure ment orog ram data, as described in Section 4.4.4(3) ofthe Plan identified in Condition 50-5.1, provided the partial data set is not statistically differentfrom the total data population whenever the impact on SEID is greater than 1.0 percent.

50-4.13 Not withstanding the requirement of 10 CFR 74.59(f)(1 )(i) to calculate the SEID associated witheach HEU inventory difference (ID) value, the licensee need not determine such SEID forMBA-7 whenever its ID is less than 300 grams U-235.

SG-4.14 Notwithstanding the requirement o f 10 CFR 74.31 (c)(3) and of 74.59(e)(3)(i) to measure controlstandards for all measurement systems for the purpose of determining bias, andnotwithstanding the requirement of .10 CFR 74.31(c)(4) and of 74.59(e)(8) to maintain astatistical control system to monitor such control standard measurements, the licensee need notmeasure nor monitor such control standards for point calibrated, bias-free, systems. To be

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Lice nse Number

"7NM-1 24MATERIALS LICENSE Docket or Reference Number

SUPPLEMENTARY SHEET 70-143

Amendment 78

regarded as bias-free, a measurement system must be calibrated by one or moremeasurements of a representative standard(s) each time process unknowns are measured,and the measurement value assigned to a given unknown is based on the associatedcalibration.

SG-4.15 All SNMV not in transit shall be physically located within an MBA or ICA, except as specified inCondition SG-4. 15.1.

SG-4.15.1 The requirement of Condition, SG-4.15 shall not apply to HEUI or LEU contained in, orprecipitated from, measured, liquid or gaseous waste discards.

.SG-4.16 Solutions generated fibm the use of sinks, eye washers, safety showers, drinking fountains,etc., located within HEU MAAS shall be collected and measured prior to discarding.

SG-4.17 All HEU-bearin'- tiquid effluents that are routed to the.,Wbiste Water. Treatment Facility (WWTF)shall be measured for tofel'LI'ranium in the tWF~rofjcommingling with LEU. Each WWTFHEU input baitch measurem~ent, shall serve as an o~er 'heck to theicorresponding summation ofaccountabilitý'-Values, If f'or'aYnýateniaI -balan'ep ,reiod, the WWT, total cumulative HEU over-check value.an investigation shall *~cohd~Icted and documente'd;as to the caufse and corrective actiontaken, and the appropriate NRC safeguards' licenising authority shall be notified within 30 daysafter the start of,,the associated physical invenit~ory. The WWTF input overcheck measurementsystem shall be ýSubjectltbl all appropriate~requiriements of the Measurement Control Program asspecified in S6ctin 4.4 bf -the<-Plan ideritifiiid, iriCondition SG-5. 1.

SG-4.18 'Notwithstanding thW requirement of 110 CFR,"74.15 t6 include lim-it of error data on DOE/NRCForm-741 for all SNM' shipments, the licensee is exemp~tfrbnii including such data on 741Forms associated with Waste burial, shipments. .

SG-4.19 Whenever a SNM Material Superintendent or designated SNM Custodian is summoned to anMAA exit point to assist in resolving whether an item or container -should be allowed to exit tothe protected Area, in accordance with the currently approved "Physical Safeguards Plan," theSuperintendent or Custodian, shall document the basis for any decision allowing the item orcontainer to leave the area.

SG-4.20 The licensee is exempted from calculating the. standard error of inventory difference (SEID) and,measurement system biases associated with LEU physical inventories provided that thecalculated inventory difference does not exceed 1,000 grams U-235.

SG-4.21 Notwithstanding Section 7.1 of the Plan identified in Condition SG-5.2, which states that"confirmatory measurements of scrap receipts are performed after the scrap is dissolved," theterm "scrap receipts" shall not apply to receipt materials whose SNM content can be determinedon the as-received-material by weighing, sampling and analyses with a measurementuncertainty (at the 95% C.L.) of less than 2.00 percent (based on a single sample).

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Amendment 78

SG-4.22 Notwithstanding the-heading "Typical MC&A Procedures" for Table 3.5 of the Plan identified inCondition SG-5.2, all procedures listed in Table 3.5 shall be officially designated as "CriticalMC&A Procedures", and any revisions to these procedures shall be subject to the same reviewand approval requirements (as specified in Section 3.5 of the Plan) that applied to the originalprocedures.

SG-4.23 Notwithstanding statements contained in Section 4.2.4 of the Plan identified in ConditionSG-5.2, if the normal minimum number of ,control standard measurements per week, day, orshift of system use (depending dn,,type of ,measu Irement system) does not generate at least 25control standard measurem ents for a given lLEIJ mea~suremn system during any inventoryperiod in which the active- inventory is greater than 9,000 grams U-235, the licensee shallnevertheless generate; at least 16 control standard measurem~ents for each key measurementsystem utilized durling the inventory period.

SG-4.24 Deleted by Amendment 3, March 2000. This Conditioný expired May 15, 1999.

SG-4.25 Deleted by Amendment 16, January 2001.~ This Condition expired .July 8, 2000.

SG-4.26 Deleted by Amrendment 21, March 200.1..Ti Tis-Condition expired February 11, 2001.

SG-4.27 Deleted by Am~endment 28, June,2001, ~Tli§s Condition expired April 14, 2001.

SG-4.28~~~~~~~~~ NowtsadnIcnriitet~fS'jin': of the ýFundartiental Nuclear Material Control(FNMC) Plan id~rtfe 0-~o~d~ §" _5`1t ubi copeted Strategic Special NuclearMaterial Physicdl. Inyventory Summary Repo .rt on NRC Form 327,Nnot later than 45 days from thestart of the physical iniventory, the lice 6s"61 is- exempted fromlAhe above stated requirementsand shall have 21 addýitinal days to comiplete the May 2002 physical inventory report. Thiscondition automatically expires on July 23, 2002.

SG-4.29 Notwithstanding the commitments in Section, 4.7 of the Fundamental Nuclear Material Control(FNMC) Plan identified in Condition SG-5.11 to perform receipt verification measurements within30 days, the licensee shall have until August 31, 2003, to fulfill the above stated commitmentr elative to the shipment of highly-enriched uranium material identified in the July 23, 2003,request letter.

SG-4.30 Deleted by Amendment 48, February 2004. This condition expired October 2003.

SG-4.31 Deleted by -Amendment 48, February 2004. This condition expired November 2003.

SG-4.32 Notwithstanding the commitments in Section 4.7.2.1 of the Fundamental Nuclear MaterialControl Plan identified in Condition SG-5.1. to perform material receipt measurements fromeach material lot, the licensee may use the original receipt values with a limited confirmatorymeasurement relative to the received material identified in the October 1, 2004, request letter.This condition shall automatically expire on completion of the final shipment of the subject oxidematerial.

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Amendment 78

SG-4.33 Notwithstanding the commitments in Section 4.5.3.7 of the Fundamental Nuclear Material ControlPlan identified in Condition SG-5.1 to perform material measurements for physical inventories,the licensee may use a material inventory measurement modification with regard to a quantity ofpartially processed scrap material identified in the October 20, 2004, request letter. Thiscondition shall automatically expire on completion of the final processing of the subject scrapmaterial.

SG-4.34 Notwithstanding the commitment in Section .4.7.1 of the Fundamental Nuclear Material Control(FNMC) Plan, identified in Conditidn SG-5,T1't&.'p6rform certain receipt verification measurementsof strategic special nucleariaeal the licensee&~hiillhoave five (5) additional days to fulfill theabove stated commitmen relative to the shipment of high-Ibnriched uranium identified in theJanuary 5, 2007, reqube:.t letter. This condition automatically-lexpires on April 30, 2008.

SG-4.35 Notwithstanding the requirements of 10 CFR 74.59(f)(1) and Section 4.5.1 of the facility'sFundamentalr`_' NceaMaejlControl Plan, NFS may repo rt the results of the May 12, 2006,

inventory for (Blended Low -Ethrched.Uraniulm Preparation Facility)within 45 days ofihe date of__ th!etter in'fo'rminig NFS t~hat NRC has Ino objection to restartingoperations add?- sed in Confi rmatory Action Letter No. b2-06-003 dated March 18, 2006.

SG-4.36' Notwithstanding the requirements of Section 7.4.2. ,o'f the fadility's FNMC Plan, NFS mayuse the shipper's iquantities to reov'h hiprrcie d'iffe'rences and for material accountingpurposes for batches FZF-,KAS-096 ,Z-ASO7 and JXI-KAS-001 for the BlendedLow-Enriched Uranium Prbrtin ac~iý

Section-5.0 --- FNMC PLANS ANDb SPECIAL IJSSUES IN PLAN APP~tNDICES:

SG-5.1 In order to achieve the performance objectives of 10 CFR 74.51 (a) and maintain the systemcapabilities identified in 1IOCFR_ 74.51 (b), the licensee. shall follow its "Fundamental NuclearMaterial Control Plan" (Plan) withk-respec~t~t all~ activities involving strategic special nuclearmaterial, except as noted in License Condlition 9G-6.5. The Plan, as currently revised andýapproved, consists of:

General Discussion-------------------- Rev. 8 (dated April 2005)Sec. 1 - Process Monitoring----------- Rev. 19 (dated January 2006)Sec. 2 -- Item Monitoring--------------- Rev. 7 (dated July 2005)Sec. 3 -- Alarm Resolution------------- Rev. 6 (dated October 2004)Sec. .4 QA & Accounting ------------- Rev. 15 (dated April 2005)Annex A----------------------------- -- Rev. 5 (dated March 2003)Annex B ------------- ----------------- Rev. 1 (dated August 1998)Annex C ------------------------------ w- Rev. 1 (dated August 1998)Annex D ------------------------------- Rev. 2 (dated October 2000).

Revisions to. this Plan shall be made only in accordance with, and pursuant to, either10 CFR 70.32.(c) or 70.34.

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Amendment 78

SG-5.2 In order to achieve the performance objectives of 10 CFR 74.31 (a) and maintain the systemcapabilities identified in 10 CFR 74.31 (c), the licensee shall follow its "Fundamental NuclearMaterial Control Plan (Plan) for SNM of Low Enriched Uranium" with respect to all activitiesinvolving SNM of low strategic significance.' The Plan, as currently revised and approved,consists of:

Section 1--------------------------- Rev. 5 (dated October 2003)Section 2 -------------------------- Rev. 4 (dated August 2004)Section 3--------------------------- Rev. 6. (.,dated January 200.5)Section 4 --------------------------- mRev. -5 (MdatdJanuary 2005)_Section 5 --------------------------- Rev. 4 (dated January 2005)Section 6 --------------- I------------- Rev. 4 (dated AugýUsf.2004)Section 7----- ------------- Rev..2 (dated January 2002)Section 8 ------ ----------------- Rev. 3 (dated January'20.05)Section 9----------------- Rev. 1 (dated FiebrGiiiry 46~3)Annex-------- - -- --------- Rev. 5 (dat ,ed J1au r 2005

Revisions to this Pl an shall be mad esonly iniaccordance with, and purs'uant to, either10 CFR 70.32(6)-or 70.34.

SG-5.3 Notwithstanding the reqUirement of 10 CEFR 74 59,5(f)(1)'(1) to~es~timate th6 standard error associatedwith SSNM inventory diffebrence values, a~nd ribtwithstanding ithe requirfements of10 CFR 74.59(e)(3), thro'ugh (e)(8), the lice~nsee may, in lie of sadqcurmns olwApniG of the Plan identified in SO-Condition' 5. 1 with respebt~tb plutonitim 'Measurements andmeasurement control associated with the plutonium decommissiqning project.

SG-5.3.1 With regard to the plutonium decommis Isioning project (described in Appendix G of the Planidentified in Condition SG-5.1), the licensee shall comply with the following:

(a) For plutonium accountability measur meft, ts"he maximum measurement uncertainty (at the95% confidence level) of measurement values equal to or greater than 100 grams Pu shallnot exceed plus or minus 10.0%. For measurement values less than 100 grams Pu, butequal to or greater than 25 grams Pu, the maximum measurement uncertainty shall notexceed plus or minus 20.0% (at the 95% C.L.).

(b) For net weight measurements utilized for establishing "nanocuries Pu per gram waste"values (which in turn are used for establishing the category of waste),' the maximummeasurement uncertainty (at the 95% C.L.) shall not exceed plus or minus 2.00%.

(c) Sufficient control measurements shall be generated and documented so as to demonstratecompliance with 5.3.1 (a) and (b) above.

(d) For each inventory period during which plutonium decommissioning activities areconducted, the measurement uncertainty associated with the total quantity of plutonium initem form generated and measured during the period shall be derived from all relevantmeasurement control data generated during that inventory period.




Amendment 78

SG-5.3.2

SG-5.4

SG-5.5

(e) For each inventory period during which plutonium decommissioning activities areconducted, plutonium "additions to" and "removals from material in process" (ATP and RFP)shall be calculated. Any measured Pu quantity, in item form, which is generated fromexisting residual holdup shall be regarded as an ATP at the time of its generation. Anymeasured Pu quantity, in item form, which is tamper-safe sealed and which will not undergoany additional processing (such as washing, compaction, etc.) prior to shipment off siteshall be regarded as an REP upon obtaining such status. The limit for total plutoniummeasurement uncertainty for each irnvnor peiod shall be the larger of (1) 250 gramsplutonium or (2) 10.0Q, percent of the larger o0f AP~ir RFP.

(f) The licensee sh~all investigate any non-zero inventory diffe'rence, since a non-zeroID will be(for this operation r) indicative of an item(s) discrepancy.

Storage of pluttpnium items generated during plutonium'•J~e~omrnissionin g activities shall be inaccordance 'ihthe commitments contained in th~!ib6n9ee's Plan dentified in ConditionSG-6. 1. 1

Operations ivlngspecial nuclearrn maeil, which atre 4not described in the appropriate Planidentified by.eit~her Condition SG-5.1,or SQ-5.2,shallriot be initiatequntil an appropriatesafeguards plah (describing all new an/rmdfe eurf..n MC&A measures to beimplemented) has been approved by the appropriate NRC safegpapds licensing authority.

Notwithstanding the requirements of 10CFM 74.51f(b),and (d),",74.53, and 74.59(d)(3), duringperiods of curtailed SSNM activities limited to (1).use of less,th an five (5.000) formula kilogramsof SSNM contained in encapsulated or tamper-sa~fdsealed :sta'ndards; (2) use of less than five(5.000) formula kilograms of SSNM contained in mate rial at ýssoci ated with R&D activities and/orlaboratory services; (3) Výault storage of HEU oxides~in iterm form except for samples utilized forindependent receipt measurement; (4) storage ;of~l ,oW level waste materials destined for offsitedisposal; and (5) decontamination and decommissioning operations involving residu ,al holdupand site remediation; the licensee is exempt from the above mentioned regulations and shall, inlieu of these regulations, follow sections 1.0 through 4.0 of its "Fundamental Nuclear MaterialControl Plan Applicable for Periods of Limited HEU Processing Activities." This Plan, ascurrently revised and approved, consists of:

General Discussion ---- Revision 1 (dated October 1994)Section 1-------------- Revision 1 (dated October 1994)Section 2-------------- Revision 1 (dated October 1994)Section 3-------------- Revision 1 (dated October 1994)Section 4-------------- Revision 0 (dated February 1994)

During such periods of limited HEU processing, the licensee need not follow the Plan identifiedin Condition SG-5. 1. Whenever the possession and use limitations defined above in this .condition are not applicable, the Plan identified herein shall be regarded as null and void, andthe SG-5.1 Plan shall be in full force.

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ýýýM 20NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION



Amendment 78

Section-6.Q -- PHYSICAL PROTECTION REQUIREMENTS FOR STRATEGIC SPECIAL NUCLEARMATERIAL

SG-6.l1 The licensee shall follow the physical protection plan entitled "NFS Physical Protection Plan forProtection Of Category 1 High Enriched-Uranium (Strategic Special Nuclear Material),Revision 6," except for the fourth and sixth changes as they are listed in the Record of Revision,and as the plan may be further revised in accordance with the provisions of 10 CFR 70.32(e).

SG-6.2 The licensee shall follow the safegua~rdst conitingenicy plan titled "NFS Safeguards ContingencyResponse Plan, Revision 1,daedMrh31, 2006; andvais may be further revised in accordancewith the provisions of 100QFR'70.32(g).

SG-6.3 The licensee shall follow the guard training and qualification pldan itled "NFS Site Security TrainingPlan, Revision 1," datedMar 'ch 31, 2006; and as may be further revised in accordance with theprovisions of 10 CFR 70.32(e).

SG-6.4 Notwithstanding the above Sbfeguards L~ic-enh'se6 Cdndition~s (SG-6.1fS G-6.2, SG-6.3), uponpossession of less than Cat~6ijtý I 11vels/df spýecia'l n Ule1ar material,Ch'e licensee shall follow themeasures described in the ~physi a potecti6n plan~s 4title"'Physical S~e~urity Plan for theProtection of Special Nucle'ar MaieriaIfp Modrate-Stireitegic Significafi1ce," Revision 5, dated June

23,~~~~~~~~ 19(lte teJu 2 99, R sf6dat~d ,'february 6, 1996; and in the"Physical Securitly Plan for, Special Nuclear Material of Ldw,-Strategic' 'ignificance," Revision 2,

datd My 6, .004 an a~thy aybe'frthr' revised i In 8 -ccordahce with the provisions of 10CFR 70.32(e).

TRANSPORTATION CONDITIONS

Section-i .0- TRANSPORTATION SECURITY MEASURES:

TR-1.1 The licensee shall follow the measures described in the physical security plan titled "PhysicalSecurity Plan for the Protection of Special Nuclear Material of Moderate Strategic Significance,Revision 4," dated October 1991 (letter dated December 20, 1991), and as it may be furtherrevised in accordance with the provisions of 10 CFR 70.32 (e).

TR71 .2 Notwithstanding the requirements of 10 CFR 73.24(b), 73.25, 73.26, 73.27, 73.67(e), and 73.72,the licensee may ship SNMV up to and exceeding a formula quantity using physical protectionmeasures for SNM of Low Strategic Significance under 10 CFR 73.67(g) when the followingconditions are satisfied. This condition is limited to material in transit. Fixed site securityrequirements remain unchanged.

(a) The Shipment contains SNM only as a contaminant in low-level waste.(b) The maximum mass of SNMV per container is ý ý U-235 for every

of contiguous non-fissile material.



Amendment 78

(c) The maximum mass of SNM per conveyance is of U-235, providedall other requirements of 10 CER Part 71 are met.

(d) SNM is essentially uniformly distributed throughout the wa-ste package.(e) The maximum concentration of SNM in the waste, based upon a container

average, is of U-235 per kilogram of waste.(f) The material form is such that recovery of SNM from the waste is estimated to

be less than using very aggressive processing techniques.

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NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION · 2020-01-07 · Erwin, TN 37650-9718 5. Docket...

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Transcript of NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION · 2020-01-07 · Erwin, TN 37650-9718 5. Docket...