ACCELERATED DI UTION DEMONS

'Ew '

TION SYSTEM

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

R

D

A0500052805000529 D05000530

NOTES:STANDARDIZED PLANTStandardized plant.Standardized plant.

ACCESSION NBR:9106050299 DOC.DATE: 91/05/28 NOTARIZED: NO DOCKETFACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528

STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529-STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530

AUTH.NAME AUTHOR AFFILIATIONCONWAY,W.F. Arizona Public Service Co. (formerly Arizona Nuclear Power

RECIP.NAME RECIPIENT AFFILIATIONDocument Control Branch (Document Control Desk)

4

SUBJECT: Advises that util revising updated=FSAR to remove statementthat sampling & analysis of certain plant effluentsperformed isokinetically,per NUREG-0737,Item II.F.1.Marked-up applicable updated FSAR sections encl.

DISTRIBUTION CODE: A046D COPIES RECEIVED:LTR t ENCL / SIZE:TITLE: OR Submittal: TMI Action Plan Rgmt NUREG-0737 &WUREG-0660

RECIPIENTID CODE/NAME

PD5 LATRAMMELL,C

COPIESLTTR ENCL

1 02 2

RECIPIENTID CODE/NAME

PD5 PDTHOMPSON,M

COPIESLTTR ENCL

1 12 2

INTERNAL: ACRSNRR/DST 8E2OCQQFJ5E~I'EE

E 'R DEPY

EXTERNAL: NRC PDR

NOTES:

01

6 61 01 01 11 1

1 1

1 1

NRR/DREP/PEPB9DNUDOCS-ABSTRACTOGC/HDS1RES/DSIR/EIB

NSIC

1 11 11 01 " 1

1 1

R

D

NOTE TO ALL"RIDS" RECIPIENTS:

A

D\

D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 19

5

Arizona Public Service CompanyP,O. 8OX 53999 ~ PHOENIX, ARIZONA85072<999

WILLIAMF. CONWAYEXECUTIVEVICEPRESIDENT

NUCLEAR

161-03972-WFC/GAM

May 28, 1991

Docket Nos. STN 50-528/529/530

U. S. Nuclear Regulatory CommissionAttn: Document Control DeskMail Station Pl-37Washington, D. C. 20555

Dear Sirs:

Subj ect: Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3NUREG-0737, II.F.1, Sampling and Analysis of Plant EffluentsFile: 91-056-026

The purpose of this letter is to notify you that Arizona Public Service Company(APS) is revising the PVNGS Updated Final Safety Analysis Report (UFSAR) toremove the statement that the sampling and analysis of certain plant effluentsis performed isokinetically (as included in the UFSAR Section 18.II.F.1.2response to NUREG-0737 II.F.l, and UFSAR Sections 9A, 11.5, and 15A). A 10 CFR

50.59 evaluation has been performed, which concludes that this UFSAR change doesnot involve an unreviewed safety question. The fixed-flow sampling techniquesbeing utilized comply with the design principles of ANSI 13.1-1969, which isendorsed by NUREG-0737. The fixed flow techniques permit more accurateprediction of sample line loss values for both particulates and iodines, andcontribute to greater reliability of the radiation monitors. Copies of theannotated pages of the UFSAR are attached.

The letter issuing the NUREG-0737 requirements, dated October 31, 1980, requiredthat any relief from its criteria be requested in response to that letter.However, in the years since NUREG-0737 was issued, its criteria as committed toby APS have been incorporated into the PVNGS UFSAR and were reviewed and acceptedby the NRC in the initial licensing process. Because the NUREG-0737 criteriais now a part of the PVNGS UFSAR, changes to those criteria are considered byAPS to fall under the 10 CFR 50.59 regulation governing changes to the facilityas described in the safety analysis report. APS recognizes the importance ofthe NUREG-0737 requirements, from the regulatory perspective and for their impacton safe operations, and is providing this transmittal to the NRC to ensure promptnotification of the change. This change will also be submitted as part of theannual 10 CFR 50.59 report and the annual UFSAR update.

9106050299 910528, PDR ADOCK 05000528

' PDR

t

0 61-03972-MFC/GAMMay 28, 1991

Document Control DeskU. S. Nuclear Regulatory CommissionNUREG-0737Page Two

If you have any questions or require additional information, please contactMichael E. Powell at (602) 340-4981.

Sine rely,

WFC/GAM/gam

Attachment

cc: J. B. MartinD. H. CoeA. C. GehrA. H. Gutterman

l

PVNGS UPDATED FSAR

APPENDIX 9A

RESPONSE: Demineralized Water System: This system isnonradioactive and there is no radioactive input to thesystem. Refer to amended subsection 9.2.3.

Condensate Storage Facilities: This is a nonradioactivesystem. Refer to amended subsections 9.2.6 and 11.2.2.

UESTION 9A.37 (NRC Question 460.5) (9.3 and 11.5)

a) Provide continuous process monitoring capability for thespent fuel pool and refueling pool treatment systems.

b) Clarify whether discrete sample analyses provisions areavailable for 'both the high and low TDS holdup and monitortanks.

c) Describe the provisions for monitoring concentrate monitortank activities.

d) Describe the process sampling provisions for grab samplingiodine in fuel storage area vent system, radwaste areavent system, and the evaporator vent system (these arerequired by Standard Review Plan. Section 11.5, Rev. 2,"Process and Effluent Radiological Monitoring and SampleSystems," See Table lA).

RESPONSE:

a) Refer to amended paragraph 9.1.3.2.1.2.

b) Descrete sample capabilities are listed in table 9.3-3(sheet 10 of 12). Refer to amended paragraph

11.2.2.3.')

Sample capabilities are described in paragraph11.2.2.3, and listed in table 9.3-3 (sheet 10 of 12).

d) The fuel storage area currently is designed to be

grab sampled for iodine using a movable airbornemonitor (refer to table 11.5-1). Continuous iodinecollection using a charcoal cartridge will be pro-vided for the fuel building.

9A-21

PVNGS UPDATED FSARel 3>

APPENDIX 9A

The radwaste area and evaporator vent are designedto be grab sampled from the grab sample connectionon radiation monitor XJ-SQN-RU-14. Prior to release,the plant vent radiation monitors (XJ-SQN-RU-143 andXJ-SQN-RU-144) continuouslycollect an iodine sample using a charcoalcartridge. Additionally, areas in the radwastebuilding may be grab sampled for iodine using a

movable airborne monitor.

UESTION 9A.38 (NRC Question 460.6) (9.4 and 11.3)

Provide a table comparing the design features and radio-activity removal capability of each normal ventilation filtersystem to each position detailed in Regulatory Guide 1.140,Rev. 1 (October 1979), "Design. Testing and MaintenanceCriteria for Normal Ventilation Exhaust System Air Filtrationand Adsorption Units of Light-Water-Cooled Nuclear PowerPlants." For each item for which an exception is taken, theapplicability of the proposed exception should be justified.

RESPONSE: The response is provided in table 1.8-3.

UESTION 9A.39 (NRC Question 282.1) (9.1.2.3)

Provide fabrication details of the Boral tube inserts to be usedin the spent fuel storage pool. Provide details of the kind and

thickness of the cladding of the Boral. Explain how exposed

Boral matrix (Boron carbide) is protected from the borated poolwater. Describe corrosion protection of the Boral tube.

RESPONSE: The response is given in amended paragraph9.1.2.2.2.

9A-22

~ t

I.

tt

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICALMONITORING AND SAMPLING SYSTEMS

11.5.2.1.1.5.4 Automatic Contxols. Provides automatic controlof each channel by the associated field unit microcomputer.Automatic contxol includes the following, as applicable to theparticulaz channel type:

A. Automatic activation of the check source and monitor-ing for a proper response at regular intervalsspecified in the channel critical parameter file.

B. tomatic s ing of a 'culate nel mo 'ngpa er fi er at regul intez als speci ed n tcharm critical ameter file.

y'CsCi~

p,g. Automatic sample flo ~ontrol0

'11.5.2.1.1.5.5 Remote Manual Controls. Provides remotemanual control of each channel through operation of DCU

keyboard. The following xemote manual controls are accom-plished via eithex of the DCU keyboards:

A. Remote manual activation of the check souzce.

Remote manual staztup oz shutdown of detectors and/orsampling auxiliazy equipment for maintenance.

Remote manual acknowledgment of radiation level high,~

~ ~

~high-high, or high rate alaxms.

Changes to the file of critical parameters for each

channel. including addition or deletion of parametersand changes to pazametez values.

A key lock switch, which assures positive administrativecontrol over access to these remote manual contzols, is mounted

on each DCU keyboazd (control room and radiation protectionoffice).

11.5-30

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICAI.MONITORING AND SAMP(,ING STSTEMS

Table 11. 5-1CONTINUOUS PROCESS AND EFFLUENT

RADIATION MONITORING (Sheet 2 cf 11)

Raspier/Ncnf torlocation

(Instc Tag No())(pil Dug. Ref.)

I~i- r ~I(ES (cont)

Quantitypac Vnlt

Designated Locationror Rnvfcolvse)[)I Design 04ckgcoUAdQuail(Ication (AR/h Co-60) Sanplec Type

Deter(gf Actfvlt'f)Typ» Neasured

CalfhcatlonNoel!de

R4nge(scf/cn )-

Rxpected AtacnCcncentrat)ons Setpofy

(vcf/cn ) (vcf/cn )

ResponseTine ~ t Nin.Detect~~) ~Conc.

roue[ )Autonatic Ag)cns

Supply I nit lated

AUR1114cy Ste4n COAdensate Receiver Tank inlet(RTI) Ncnftor(XJ SQN RV 7)

Auxiliary Sullding Venti-lation Rxhaust ritterinlet (Ascf) Nonftoc(XJ SQN RV 5)(rlgUC~ 9.i ))

Auxiliary Suf tdfng ~rLevels (ASLL) VentilationRxh4U5t CRNlltoc(XJ-SQN RV 9)(rlguce 9.4-))

Auxlllacy Sull4lng upperLevel (ASUL) ventilationRsh4USt NOAltoC(XJ~-RV 10)(plSure 9.4-))

Auxlllacy Sldg.

Auxiliary sldg.

AU$1114Cy Sidg ~

1uxlllary 014).

2.5

0.5

2.5

2,5

T4nk Recite./Ligule

Off Line/

rlxed rapecP@cticul ~ t~rlltec

Off Line/

rlxe4 charcoalor Sliverxeol itscartridge

Off-Line/Cas

Cff-Line/Cas

CCO$ 5

ccoss 9

volatileI 1st

Cross ft

cross 0

Cs 1)7

Cs-l)7

Sa I))(I)

xr-55(k)

xr-SS(k)

Io-6-Io-I

Sxlo-ll 5510-6

lo-11-10-6

10-6-io I

IO-S-IO-I

6 x lo loI l)l

9R 106Xe I))

25106Cs ll)

) x IO-10Cs-I))

I x logI I)I

1.0 x lo 5Xe-I))

2 R 10 6Xe-I))

I Nin.

I Naut

0 Neucs

I Ntn.

I Nin.

Instr. (u) 1lacn and divert4UR 5tn condeAsate to Ilguldcadv4$ te Systeo.

IAstc ~ (n) Al~ cn UAIy,

Alarn cnly.

IAstc ~ (n) A14fn INlly

Instr. (~ ) Alacn only.

vases ces Decay Tank(Ucot) Nsnl tor(XJ SQN RV 12)(rigor~ Il.l 2)

Sull4ing Vent (SV)NonltocsTSC IJ SQN RV l)1Ror )J SQH RV l)5

I(Ccaamto ~ llvnl is)

Radvaste 0ld9,

Technical Suppor tCenter (~)Reecgency Cpec4tlcNls racll lty(sor)

50 In line/cas

Off-Line/

rixed operp4ctfcu14t ~rllterOff line/ 7/SC1

cross 0

cross 0

Volatll~I 1)I

xr SS

Cs l)7

~ -I))())

10 )-1042

lo-9-Io-4

lo-9-lo-4

IND/I x 10 IXr-SS

(o)

1.2 x 10 6

Cs I)7

2. ~ 5 10 7

I 1)I

I Nin.

IS Nln.

15 Nin.

Inst c Al~ rn and Inltl-~ t ~ close ofthe U4$ ta 94$discharge valves

ln5tc (~ ) 114cn UAly

A14cn OAly.xe ccoal

oc SliverXeol itsCartridge

cff-Line/Cas Cross 9 XC-55(k) lo 6-io-I 7.2 x 10 )Xe-I))

I Nin. Alaco only.

0

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICA(

MONITORING AND SAMPLING SYSTEMS

Table 11.5-1CONTINUOUS PROCESS AND EFFLUENT

RADIATION MONITORING (Sheet 3 of 11)

saap I4 r/Ncnl torLocation

(Instr. 249 No())(PLI DV9, Ref )

~~~IIO42 (cont)

Qwnt ltyPef Qnlt

Des(9hated LocationPor Rnvlrcnaeg~ IQwll(Ication

Des)9h Sac'k9round(aa/h Co do) 5aapler Type

Detcc[g~Typt

1ctlvltfc) Cal )orat tonH445ucc4 Nut)144

44ll943(vcl/ca )

RxpectcdContent rat )ohs

(acl/ca )

114thSct pot p(vcl/ca )

Response1st at Nln.Detect/) ~ Pout[ )Conc. Supply

Autwatlc Ag3onsIn It I4 Ie4

Radvaste Sulldtns Vent 1

let(on Rxhauat filterInlet (RSPI) Nonltor(XJ SQN RQ I~ )(PISure 9.4-5)

V4SCe Cas Af44 Ccah)hedvent llatlon Sxhaust(vcvs) Nonltor(XJ SQN RQ 1$ )(Plsure 9.4-$ )

Outside (4/V Sids,Roo()

Radvastt olds.

) ~ 0

2.5

o(C-L

plxtd Papefp@ctlculat ~

filter0((-Ltne/Ccs

Cross O

Cross O

Cs l)3

Xr 45(k)

5xlo II Sxlo d

lo-4-lo-I

2.4 x 10-1Cs-l)1

2 x lo 4Xe-I))

I Hour

I Nln.

Instr..(a)

Illxtf (~ )

llara only.

114fa onl'I

Operettas Level 1ct4(CLA) Non(tot(XJ-SQCC-RQ-Id)

Incor ~ Ihstclacnt 1cea(111) Hca)tor(XJ SQN-RQ.I))

Contalraent

conte)chant

N/A

NIA

N/A 0-N

0-N O-T

IO '-IOce <h

-I ~ aah

9 aalh

9 aa/h

IS aa/h

15 aR/h

)0 Scc.

30 Sec.

Instr.

Instr.

Alaca only.

Altea only

control aooa Area (caA)Heal tot(XJ SQN RQ 14l

Control S)49. NIA N/1 0-N4 ~ aa

10 -10h

0 S aa/h 30 ScC Instr A14Ca eel Iy.

Neu Put) Atca (NPA)Honltor(XJ SQV-RQ 19)

so)Id vesta Proccsslns5t4tloh Ace4 (SPA)Nohltof(XJ-SQN RQ 20)

Pwl Sids.

Radwste olds.

N/A

NIA N/A ow

10 10h

lo '-Iota SEh 1.5 aa/h

2.S aR/h 30 5cc

2.5 aa/h )0 Sec.

Instr.

Instr

Alaca only

A14ca only

solid vesta stoca94 Ates(ssA) Non( tor(XJ~ Rtl 21)

Loadlns Say Acta (LSA)Honltoc'XJ

SQN-RQ 22)

Radvast ~ Sld9.

Radv4ste Sld9

N/A

N/1

NIA

N/1

0-H

0 N

10 lo

Io 10 1.5 aR/h

IOO aa/h )0 scc. Ins~r.

2.5 aa/h 30 SeC. Inxtr.

Alara only.

114th call'I

Radlochealcal LaboratoryArea (RL1) Non)toe(XJ SQN-RQ 2))

1uxll!4Cy S)49 N/A N/A 0-N O.T IO '-IOce ~h 0.5 aR/h 15 aR/h 30 Scc. Instr. AI4ca ohl'y.

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICAL

MONITORING AND SAMPLING STSTEMS

Table 11.5-1CONTINUOUS PROCESS AND EFFLUENT

RADIATION MONITORING (Sheet 7 ot 11)

Raspier/non(torloc4t lcn

(Instr. Tag No(l)(PSI Dvg. Ret.)

((sant 1tyPer Unit

Designated Loc4ticnPof Snvtcolwcgtt Design 94ckgcound(tua I (f)cat ion (sslb Co 40) Raspier Type

DeteclgfType

ACtlvltNtasuccd

ClllbcatlcnNuclide

Rangt(vc(lcn )

Rrpcctcdconccntratlons

(vcl/cn )

blamSet pe(y

(set/cn )

ResponseTIM ~ I Nln.Detcctie povcl )

Auteur to A@lansCeno. Supply Initiated

Nein Stean Line Rttlu«nt(NSIA. NSLR) MonitorsXI SQN Rtl l)9XI-SQN RO Ito

Nein Stean SupportStructure

Norse 1

c0.$AccidentIOt

II/A Icn Cross 'I Cs l)I IOO - 105 ealh 10 sr/b 30 sec Instr. (~ ) blam only.

condenser vacuue pcaapleland Seal RshaustNeo(tore (cvtR)

tc Range X)-SCN-RO-1st

TwblM Null ding Ott-Line/oat cross lt Xt I)) IO4 to lO) 9 x lo 4XR L))

(o) I Nln. Instr. (~ ) Alacn Atterprop4f overlap ~

shl(ts to highrange on increas-ing ra4lct ionlevel.

lo

(CVNR)Nigh Range XJ SON RO 143

Plant vent Nonttors

(PVLR)teat Range X)~SO lt)

Turbine Sulldlng

Turbine Ru lid lng

Ott-Line/

Pactlcul ~ 'I~

OCt LtnedtgntCCnaf

coal or SilverXcolitsCactrldge

OCC-Line/Oas

OCC Line/

~ te

oct-Lined)cccbg?RXglchar

coal or silverXeol1teCartridge

OtC Llnelcas

Ott I.inc/CISRDXXKE~

Ppac Icul~ te

No Detector

No Detector

0 N

0-N

0 N

Cross 0

Cross 9

X@ 1)3

Xe-l)3

Cs l)I

3zlo) to10$

IO')

IO')

lodto3

IO-0 to

IO-'o)

(p)

(p)

(o)

(p)

1 Nin.

1 Nln.

I Nin.

1 Itin.

15 Itin.

instr.(»

Instr.(n)

NIA

N/A

blam - Atterpeeper overlapshitts to Iovrange on decreas-ing radiac ionlevel.

shltts to another444pl ~ cartridge ~

Shitts to 4nothtf44eple c4f tci414 ~

blam - Atterproper overlap.shttts to highrange on increas-ing fad tat tenlevel.

NIA

lo

lo

lo

lo

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICALMONITORING AND SAMPLING SYSTEMS

Table 11.5-1CONTINUOUS PROCESS AND EFFLUENT

RADIATION MONITORING (Sheet 8 of 11)

'- saspf sr/cccnf tortoes cion

(Instr. Tag No(l)(PSI Dug 1st ~ )

<tuancf tyPer Unit

Deslgn4ted lnc4tlonPor Envfromeglf Design Sackgrcxnd<)us 1 it lest ion (ss/h Co-60) Saspler Type

De teel g lf

TypeActfvftg Calibration

N44$ore4 Nuclide14nge

(vcl/cs )

SespcnseExpecte4 stars Cise at clin.

concentrations setpof~t Detect/le(eel/cn ) (eel/cs ) Canc.

Auc$$atfc A@lensInitiated

(cont)

(PVCO)Nfgh Sange X3-SyC-SO 144

tuel su(14lng Vent ll~cion Exhaust Ncnltord

(PSLS) Lcu SensexJ EQS su 14$

(psf(S) R(gh Santax) $00 su 146

Turhfne Sulldlng

tuel Sullding

~uel guild lng

O.s

O.S

ott-t ne/~coal or SilverXeolltecarcrtdge

Ott-Line/Cas

Ott Line/

p4rciclllaCC

Ott-Line/r

coal or SliverXeol it ~c4rcri4ge

Ott Line/Oas

Ott Line/

particulate

Ott-Line/Cs(DCha r

coal or SliverEcol fcaC4rtc14ge

Ott-Ltne/Cas

I/scA

No Detectoc

No Detector

0 N

valet lie1-131

Cross (C

Sa 133<))

Xe 133

Xe-133

Xa 133

1O-10 Co 1O-3

10 I to 10$ 3

1043

1043

10 6 to 10 1

10 I to 10S

lp)

(o)

(p)

<p)

<o)

to)

13 nin.

1 Nfn.

1 Nin.

1 Nin.

1 Nin.

I nin.

Instr. <s)

vital 0 <h)

vital 0 <h)

114rs Atterproper overlap.shitta tO flearange cn decreas-ing radiatfcnlevel.

Shirts to anothersasple cartridge.

Shifts to anothersaaple cartridge.

Alars InitiatePuef Su tidingEssential ventffatten (PSCVAS)- A(car properoverlap. shitCsto high rangeon increasingradiation level.

N/1

N/A

slats Atterproper overlap.shltts to lourange on decreas-ing radiationlevel

1O

lo

lo

lo

lo

PVNGS UPDATED FSAR

PROCESS AND EFFlUENT RADIOLOGICALMONITORING AND SAMPLING SYSTEMS

Table 11.5-1CONTINUOUS PROCESS AND EFFLUENT

RADIATION MONITORING (Sheet 9 Df 11)

Saspfet/Hcnf CnrLocation

(IASCc ~ Tos No())(PSI DUS. Re(.)

QuantityPer Vnlt

Deslln4te4 Loc4C lospoc Rnvfrccaogfl DOOISA 54ckSrocsldQuail(ication (stlh Co-{{0) 5aspler Type

Dotoc)gf lcCfvftk) C411br4tlonH44$Ute4 Nuclide

ROASOJ(vcl/cs )

ResponseRrpecto4 liars Tlse at Hln

ccncentrat)ons setpofI)t Detect/) ~(vcl/cs ) (sci/cs ) Conc. Supply

Autcutfc Ag)cnsInltfaccd

(cent)

In Concalnunt AcesHcnftort(HCIA) XJ~ RV lct(HCAS) XJ SQS RV li')

Prlsary Coolant Hcnl tora(PCHA) XJ S{}A RV ISO(P{2{s) xJ 5QS Rv 1SI

~ocsonul IARICvesa AIafffary 70'evel(VlTO) XJ~RS ISIA

Personnel IARH54$ C AUxlllac'f TO'evel(SAID) XJ SQN Rl 1S25

Pecsonne1 IARHSouth Stafruoy

40'evel

Auxl fiery(SSCA) XJ-SQH RS 132C

PorsoAnol IARHNorth Stafrvaf 51'4Level Auxiliary SldS.(NSSI) XJ SQN RS IS2D

Personnel IARICV4$ C AU11llory SldS,100'evel(Vale) XJ SQH RS ISIA

Personnel IAtH54$ C AU1lllocy 4145100'evel(SAID) XJ 5QH tt 1530

Cont 4 Imon C

(Post LOCA)

Contefcwent(Post LOCA)

Auxiliary 0145.

aalllacy 0145.

AIafllacy 5145.

Auxiliary SldS,

luxlllacy sldS.

luxlllacy RldS.

SO Rlhr5aana

30 R/hrAOUCrcAO

N/A

N/A

N/A

N/A

Th c 4 ~ '4 pe r4 t ~Of( Line/

act cui ~ to/IodlnelC4cct1414$

N/l

H/A

N/A

N/A

NIA

Nll

H/A

N/A

Iccl Ch4obec I photons Co (4

lon Chasber I photons co-(4

Ion Chuber

Ion Chasber

Icn Chaaber

lon Chasber

Ion Chuber

Ion chanber

1043 st/hr

I RlhrCoID+I Rlhr

I R/hrtoIOIS Rlhr

0.1 RlhrCoIOC Rlhr

0.1 RlhrtoIOC Rlhr

O.l R/hrto104 Rlhr

0 ~ I R/hrto10$ 1/hr

0.1 R/htCo104 R/hr

O.l R/hrtolct R/hr

(4 Rlhr

~0 R/hr

2 1/hr

2 Rlhr

2 R/hr

2 t/hr

2 R/hr

2 R/hr

I Nin.

30 Sec.

30 Sec,

30 5ec.

30 Scc.

30 Sec.

30 Sec.

30 Sec.

30 Sec.

Vital l~AAVital 5(HCAS)

Vlt~ I A

Vital 0(Pcrs)

Instr. (s)

Inscr. (s)

Instr. (s)

Instr. (~ )

Instr, (s)

Instr, (s)

Shi(ts to anotherseeps caccrldie.

liars cnly.

Alars only.

liars only.

liars only.

liars cAlf.

liars only.

Alors OAlf.

A14fs cnl f.

11 ~ 5-18

C

r ~ „~ ~ «l s., ~ ~ .=4' w

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICAL//,S.Z ~ I./ 7 2 ~ ~P~<~@«e~~g MONITORING AND SAMPLING SYSTEMS

containing components is performed in accordance withANSI B31.1. For ESF monitors, welding of pressure-containingcomponents is performed in accordance with AWS Dl. -1972 (with1973 revisions). Welding of other equipment is performed inaccordance with industry standards.

For liquid and process channels, the sampler is a lead-shieldedsteel chamber. For particulate and iodine channels, thesampler is a lead-shielded filter assembly. Four ~ shieldingis furnished for all process and effluent detectors.Airborne particulate and iodine monitors and samplers,(XJ-SQN-RU-08, -RU-14, -RU-141, -RU-142. -RU-143, -RU-144, andXJ-SQB-RU-145 and -RU-146) sample in accordancewith the principles and methods of ANSI N13.1-1969, Guide toSampling Airborne Radioactive Materials in Nuclear Facilities.

Far v)o~mgt ..~,~,;g,.-@he particulate and iodine sample flow is maintained constant

over the normal expected range of filter paper and/or charcoalcartridge differential pressure by an automatic control system.

ow indication and high- and low-sample flow alarmsignals are provided. These signals actuatethe channel failure alarm. Sampling assembly fittings areprovided which allow grab sampling of the monitored

fo

0Cl

O

cft~OJ

'8<~ .

airstreams. The automatic control system maintains isokinetf based on a comparison of sample 'flow to HVAC duct w.The HVAC du ow input is performed manually fo -SQN-RU-08and -RU-14 and automat for XJ-SQN-RU- through -RU-144,and XJ-SQB-RU-145 and -RU-146.

A flow-integzating ela sample volume indicator 'ovideddownstzea ach particulate and/or iodine channel. It h

cal digital readout and is resettable to zero.

Refer to subsection 18.II.F.1.2 for TMI-related informationpertaining to the particulate collection and iodine adsorptionefficiency.

11.5-33

PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICAL

MONITORING AND SAMPLING SYSTEMS

11.5.2.1.3.4 Auxiliar Steam Condensate Receiver Tank RTIXJ-S N-RU-07 Monitor. Auxiliary steam condensate retuzning

fzom the boric acid concentzator and LRS evaporator is moni-tored before it leaves the receiver tank. A high activityalarm indicates radioactive leakage into the tubes of anevaporatoz during blowdown of the shell side, or due toimproper operation. Upon a high-high alarm, the RTI monitor.automatically diverts the condensate to the liquid zadwastesystem. This monitor draws and returns a sample from thesampled tank. A pumping system, to generate the requizedsample driving head, and a sample cooler, to cool the sampleto less than 120F, are provided. The sample cooler is cooledby nuclear cooling water.

11.5.2.1.3.5 Auxiliar Buildin Ventilation Exhaust FilterABFI Inlet XJ-S N-RU-08 Monitor. The auxiliary building

ventilation exhaust is continuously moni-tored for airborne radioactive particulates and iodines.

Available monitor sensitivity, zeduced by the applicable ven-tilation dilution factor for each compartment, allows thebuilding exhaust pazticulate and I-131 channels to detectmaximum permissible concentrations allowed by 10CFR20 for anycompartment in the auxiliazy building within 1 hour for Cs-137

and within 8 hours for I-131. The significant noble gas souzces

in the auxiliary building are monitored as listed in paragraphs11.5.2.1.3.6 and 11.5.2.1.3.7. The exhaust fzom these areas ismonitored directly befoze dilution in the building ventilationsystem; therefore, a gaseous monitor is not provided in thebuilding exhaust. A gas monitor is, however, provided in the

'lantvent.

11.5.2.1.3.6 . Auxiliar Buildin Lower Levels VentilationABLL Exhaust XJ-S N-RU-09 Monitor. The combined ventila-

tion exhaust from the train A penetration room and the rooms

housing the letdown heat exchanger, the associated valve

11.5-42

0PVNGS UPDATED FSAR

PROCESS AND EFFLUENT RADIOLOGICALMONITORING AND SAMPLING SYSTEMS

noble gases. Samples are preconditioned as necessary to assureaccuzate results without damaging the sample assemblies. Eachmonitor is controlled by a remote microprocessor. Thismicroprocessor is linked by a "daisy chain" to a minicomputerwhich provides multiple informational displays on request bythe operator. A dedicated alarm status line is maintained onthe CRT display. This status line does not move with each

r.change of CRT displays. Thus, alarms are provided regazdlessof the status of the displays in the Health Physics Office andmain control zoom. Monitors aze provided with an openstructural construction that provides for easy maintenance andgood heat dissipation. Backup battery power is provided toassure continued microprocessor memory during a loss ofexternal power sources. Multiple detectors aze used to achievethe dynamic range required. Hard copy zeadouts are availablefrom dedicated printers in the Health Physics Office and thecontrol room for selected data and alazms.

Refer to subsection 18. II.F.1.1 for TMI-related informationpertaining to noble gas effluent monitors.

11.5.2.1.4.1 Condenser Vacuum Pum /Gland Seal Exhaust CVSE

CVHR XJ-S N-RU-141 and XJ-S N-RU-142 Monitor. The vacuumpumps and gland seal condenser remove gases from the secondarysystem. The exhaust is continuously monitored for gaseousactivity resulting fzom primary-to-secondary system leakage.The exhaust is continuously sampled forairborne radioactive particulates and iodines. Since theexhaust is piped to its own separate exhaust from the building,no other airborne monitors aze provided for the turbinebuilding. The monitor/sampler provides automatic initiation offiltration of condenser vacuum pump/gland seal exhaust wheneverthe monitor channel is in a high-high alazm condition.

Sampled aiz is pulled from the condenser vacuum pump/glandsteam exhaust piping at conditions of 125F and 1000 relative

11.5-46

PVNGS UPDATED FSAR

zl 'lkgo/

PROCESS AND EFFLUENT RADIOLOGICAL

MONITORING AND SAMPLING SYSTEMS

humidity. Heat tracing is provided to the sampler piping inorder to prevent degradation of particulate and I-131 samplerfilters due to excessive moisture. The downstream gas channeldetector is designed to withstand these sample conditions incontinuous service.

A low and high range monitor is used to cover a range ofeleven decades with one decade of overlap. Particulate/iodinecartridge samples exist in the low and high range monitor andaze removed for analysis. High range cartridge samplers areshielded.

11.5.2.1.4.2 Plant Vent XJ-S N-RU-143 and XJ-S N-RU-144PVLR PVHR Monitor. The plant vent exhaust is continuously

monitored for particulate, I-131, and

gaseous activity.A low and high range monitor is used to cover a range of elevendecades with one decade of overlap. Shielded particulate andiodine samples exist in the high monitor and are ed for

Oil l&v$analysis. The low range iodine and particulate sam~ have a

five decade detection range.

11.5.2.1.4.3 Fuel Buildin Ventilation Exhaust MonitorFBLR FBHR Channel B XJ-S B-RU-145 and XJ-S B-RU-146

l building exhaust is contin ousl~~ pl Wl1 Cc i c.'~

gaseous channel also monitors the fuel building ventilationexhaust for re ase of activity due to a fuel handlingaccident. -The-f xhaus4 —i-s—corHinuous-ly—and-

pheon~ — - . ad—I~-> The monitorperforms the safety function of isolating the normalventilation system and activating the essential ventilationsystem (initiates a FBEVAS signal) on a high-high activityalarm. Redundancy and diversity are provided by the fuel poolarea monitor (XJ-SQA-RU-31) that also actuates the essential

11.5-47

I~

PVNGS UPDATED FSARl</

PROCESS AND EFFLUENT RADIOLOGICAL'ay

\(iq e~rpmenfo,~g 4po~u.v~s MONITORING AND SAMPLING SYSTEMS

the loss of radioactive material by deposition on the walls ofthe sample containex or volatilization.Effluent ventilation ducts and stacks are sampled continuously

in accordance with ANSI N13.1-1969 forradioactive gases, particulates, and iodines. The containmentatmosphere is sampled continuously for radioactive gases,particulates, and iodines by the containment building atmo-sphere radiation monitor. The sample is drawn from a pointbetween the containment normal air-conditioning unit suctions.A containment atmosphere gas sample is collected for analysisprior to the initiation of a containment purge batch xelease.This sample is analyzed for txitium and the principal gamma

emitters in accordance with Technical SpecificationTable 4.11-2. Containment purge batch release contribution tothe plant release will be incorporated into the continuoussample collected at the plant vent release point. Particulate.iodine, and noble gas.samples will be collected four times permonth fox all continuous effluent airborne radiation monitorsand samplers. Where composite samples are used, they arecollected in proportion to the volume of each batch of effluentxeleases or in proportion to the rate of flow of the effluentstream. Prior to analysis, the composite is thoroughly mixed

so that the sample is repxesentative of the average ef fluentrelease.

11.5.2.2;2 Analytical Procedures

Samples of proces's and effluent gases and liquids are analyzedin the laboratory by the following techniques as appropriate:

Gross beta counting

Gross alpha counting

Gamma spectrometry

Liquid scintillation counting

Radio-chemical separations

Maxch 1990 11.5-55 Revision 2

1

PVNGS UPDATED FSAR

+msgr~~ I S 8 ~ <o APPENDIX 15A

include radiation monitors to sense the occurrence of anaccident and initiate protective action.

1) The PAPA area radiation monitors isolate thecontainment refueling purge upon high radiation.They are located just outside the containmentbetween the refueling purge exhaust ducting andthe power access purge ducting as shown onfigure 12.3-4. Air flow transit time is lessthan 1/4 second.

2) There are two redundant, ESF-grade monitors,13-J-SQA-RU-37 and 13-J-SQB-RU-38. Refer tosection 11.5.

3) Area radiation monitor 13-J-SQA-RU-31 is locatedon the east wall of the fuel building adjacentto the spent fuel pool. The detector will registerthe evolution of airborne radioactivity from thepool within 1/4 second.

4) 13-J-SQA-RU-31 is ESF grade. The redundant ESF

monitor has two channels, low range and highrange (13-J-SQB-RU-145 and 13-J-SQB-RU-146). Itis located just below the roof level and samplesthe exhaust downstream of the dampers.

The sample transit time is .less than10 seconds between duct and monitor.

UESTION 15A.11 (NRC Question 440.32) (15.0)

Expand Cable 15.0-6, the list of single failure considered intransient and accident analyses, to include the following:1. One primary safety valve stuck closed

2. One secondary safety valve fail to open or fail to close

3. Loss of offsite power

15A-7

SITING AND DESIGN

calibration, and technique is provided in table 11.5-1 andparagraphs 11.5.2.1.6.2 and 11.5.2.1.6, respectively. Theinstrumentation is described in detail in table 11.5-1.

Sampling of effluents meets the criteria of ANSI N13.1-1969 asdiscussed in paragraphs 11.5.2.1.1.7.2 and 11.5.2.2.1.Paragraph 11.5.2.1.1.7.2 also describes the sampling assembly.

A description of effluent radiation monitoring is presented inparagraph 11.5.2.1.4. Included in this section are discussionsof monitors located on the plant vent, main condenser/glandseal exhaust, and fuel building vent. The main steam linemonitors are area monitors required for post-accidentmonitoring and are discussed in paragraph 11.5.2.1.5.These monitors operate in conjuction with other monitors, asdescribed in section 11.5. and fulfillthe requirements asoutlined in NUREG-0737 and Regulatory Guide 1.97, .Revision 2.

18. II.F. 1.2 SAMPLING AND ANALYSIS OF PI ANT EFFLUENTS

NRC Position

Because iodine gaseous effluent monitors for the accidentcondition .are not considered to be practical at this time,capability for effluent monitoring of radioiodines for theaccident condition shall be provided with sampling conductedby adsorption on charcoal or other media, followed by onsitelaboratory analysis.

PVNGS Evaluation

The effluent samplin sembly is discussed i ragraph .~nc )HP cr $11.5.2.1.1.7.2. Fo articulate and iodine the- =:.

sampler is a lead- hielded filter assembly., -Fear~~ s a

L ~

18.II.F-2

PVNGS UPDATED FSAR

SITING AND DESIGN

'zbozne pazticulate and iodine monitors and samplers(XJ QN-RU-08, -RU-14, -RU-141, -RU-142, -RU-143, -RU-144, andXJ-SQB U-145 and -RU-146) sample isokinetically in acc dancewith the inciples and methods of ANSI N13.1-1969, ide toSampling Air me Radioactive Materials in NucleaFacilities. Th particulate and iodine sample ow ismaintained constan over the nozmal expected ange of filterpaper and/or charcoal artridge different' pressure by anautomatic control system. Local flow i dication and high- and

I

low-sample flow alarm signal are pr ided. These signalsactuate local alarms and the ch 1 failure alarm. Two

particulate monitozs (XJ-SQN-RU 08 nd -RU-14) are movingpaper filter type and incorp ate mic ocomputer-controlledstep advance, and feed fa uze channel ilure alarm.Sampling assembly fitti gs are provided wh h allow grabsampling of the moni red airstreams. ..The au omatic control -,

1 ~

'ystemmaintains i okinetic flow based'n a 'corn rison ofsample flow to AC duct flow. The HVAC duct flo input isperformed ma ally for XJ-SQN-RU-08 and -RU-14 andautomatica y for XJ-SQN-RU-141 through -RU-144, and

XJ-SQB- -145 and -RU-146.

A fl integrating elapsed sample volume indicator is provi ed

do stream of each particulate and/or iodine channel. It has

local digital readout and can be reset to zero.

Monitors are designed to meet a 90% efficiency level fozparticulates and 90% efficiency for iodine as required. byNUREG-0737, Table II.F.1-2. They are also designed to conformwith design basis shielding envelopes for sampling media, as

discussed in paragraph 12.1.2.4. Monitors are designed toallow personnel to remove, zeplace, and transport samplingmedia without exceeding the criteria of General Design

I

Criterion 19 of 5 zem whole-body and 75 rem to the extremities.

18.II.F-3

l~ ~

hP