Turkey Point Leakage Limits

8/14/2019 Turkey Point Leakage Limits

1/5

44405Federal Register / Vol. 74, No. 166/ Friday, August 28, 2009/ Notices

NUCLEAR REGULATORYCOMMISSION

[NRC20090369; Docket Nos. 50250 and50251]

Florida Power & Light Company;Notice of Consideration of Issuance ofAmendment to Facility OperatingLicense, Proposed No SignificantHazards Consideration Determination,and Opportunity for a Hearing andOrder Imposing Procedures for Accessto Sensitive Unclassified Non-Safeguards Information (SUNSI) forContention Preparation

The U.S. Nuclear RegulatoryCommission (the Commission) isconsidering issuance of an amendmentto Facility Operating License Nos. DPR31 and DPR41, issued to Florida Power& Light Company (the licensee), foroperation of Turkey Point, Units 3 and4 located in Florida City, Florida.

The proposed amendment wouldrevise the TS 6.8.4.j, Steam Generator(SG) Surveillance Program and TS6.9.1.8, Steam Generator TubeInspection Report. The purpose of thesemodifications is to revise the scope ofthe inservice inspections required in thetubesheet regions of the Turkey PointUnits 3 and 4 SGs. The amendmentapplication dated July 23, 2009,contains sensitive unclassified non-safeguards information (SUNSI).

Before issuance of the proposedlicense amendment, the Commissionwill have made findings required by theAtomic Energy Act of 1954, as amended

(the Act), and the Commissionsregulations.

The Commission has made aproposed determination that theamendment request involves nosignificant hazards consideration. Underthe Commissions regulations in Title 10of the Code of Federal Regulations (10CFR), 50.92, this means that operationof the facility in accordance with theproposed amendment would not (1)involve a significant increase in theprobability or consequences of anaccident previously evaluated; or (2)create the possibility of a new or

different kind of accident from anyaccident previously evaluated; or (3)involve a significant reduction in amargin of safety. As required by 10 CFR50.91(a), the licensee has provided itsanalysis of the issue of no significanthazards consideration, which ispresented below:

1. The proposed changes do not involve asignificant increase in the probability orconsequences of an accident previouslyevaluated.

Of the applicable accidents previouslyevaluated, the limiting transients with

consideration to the proposed change to theSG tube inspection and repair criteria are theSG tube rupture (SGTR) event and the steamline break (SLB) postulated accident.

During the SGTR event, the requiredstructural integrity margins of the SG tubesand the tube-to-tubesheet joint over the H*distance will be maintained. Tube rupture intubes with cracks within the tubesheet isprecluded by the constraint provided by the

presence of the tubesheet and the tube-to-tubesheet joint. Tube burst cannot occurwithin the thickness of the tubesheet. Thetube-to-tubesheet joint constraint results fromthe hydraulic expansion process, thermalexpansion mismatch between the tube andtubesheet, and from the differential pressure

between the primary and secondary side, andtubesheet rotation. Based on this design, thestructural margins against burst, as discussedin Regulatory Guide (RG) 1.121, Bases forPlugging Degraded PWR Steam GeneratorTubes [Reference 7] and NEI [NuclearEnergy Institute] 9706, Steam GeneratorProgram Guidelines [Reference 3], aremaintained for both normal and postulatedaccident conditions. For the portion of the

tube outside of the tubesheet, the proposedchange also has no impact on the structuralor leakage integrity. Therefore, the proposedchange does not result in a significantincrease in the probability of the occurrenceof an SGTR accident.

At normal operating pressures, leakagefrom tube degradation below the proposedlimited inspection depth is limited by thetube-to-tubesheet crevice. Consequently,negligible normal operating leakage isexpected from degradation below theinspected depth within the tubesheet region.The consequences of an SGTR event are notaffected by the primary to secondary leakageflow during the event as primary tosecondary leakage flow through a postulated

tube that has been pulled out of thetubesheet, which would constitute a failureto meet H*, is considered to be equivalent toa tube rupture. Therefore, the proposedchange does not result in a significantincrease in the consequences of an SGTRevent. In addition, the selected H* valueenvelopes the depth within the tubesheetrequired to prevent a tube pullout.

The probability of a SLB is unaffected bythe potential failure of a SG tube as thefailure of a tube is not an initiator for a SLBevent.

The leak rate factor of 1.82 for TurkeyPoint Units 3 and 4, for a postulated SLB, has

been calculated as shown in Table 97 ofReference 2, Westinghouse Electric Company

WCAP17091P, H*: Alternative RepairCriteria for the tubesheet Expansion Regionin Steam Generators with HydraulicallyExpanded Tubes (Model 44F). Turkey PointUnits 3 and 4 will apply the factor of 1.82to the normal operating leakage associatedwith the tubesheet expansion region in thecondition monitoring (CM) and operationalassessment (OA). Through application of thelimited tubesheet inspection scope, theexisting operating leakage limit providesassurance that excessive leakage (i.e., greaterthan accident analysis assumptions) will notoccur. Multiplying the leak rate factor of 1.82

by the TS operational leak rate limit of 150

gpd (at room temperature) through any oneSG indicates that an assumed primary tosecondary accident induced leak rate of 273gpd or greater through any one SG is requiredto ensure that the limiting design basisaccident assumption is not exceeded. Thiscondition is satisfied by the current UFSAR[Updated Final Safety Analysis Report]assumed primary to secondary accidentinduced leak rate of 500 gpd (355 gpd

adjusted to room temperature) through anyone SG for SLB. Since the existing limits onoperational leakage continue to ensure thatthe SLB assumed accident induced leakagewill not be exceeded, the consequences of aSLB accident are not increased.

For the CM assessment, the component ofleakage from the prior cycle from below theH* distance will be multiplied by a factor of1.82 and added to the total leakage from anyother source and compared to the allowableaccident induced leak rate. For the OA, thedifference in the leakage between theallowable leakage and the calculated accidentinduced leakage from sources other than thetubesheet expansion region will be divided

by 1.82 and compared to the observed

operational leakage.The previously analyzed accidents are

initiated by the failure of plant structures,systems, or components. The proposedchange that alters the SG inspection andreporting criteria does not have a detrimentalimpact on the integrity of any plant structure,system, or component that initiates ananalyzed event. The proposed change willnot alter the operation of, or otherwiseincrease the failure probability of any plantequipment that initiates an analyzedaccident.

Based on the above, the proposed changedoes not involve a significant increase in theprobability or consequences of an accidentpreviously evaluated.

2. The proposed changes do not create thepossibility of a new or different kind ofaccident from any previously evaluated.

The proposed change that alters the SGinspection and reporting criteria does notintroduce any new equipment, create newfailure modes for existing equipment, orcreate any new limiting single failures. Plantoperation will not be altered, and all safetyfunctions will continue to perform aspreviously assumed in accident analyses.

Therefore, the proposed change does notcreate the possibility of a new or differentkind of accident from any previouslyevaluated.

3. The proposed changes do not involve asignificant reduction in the margin of safety.

The proposed change defines the safetysignificant portion of the tube that must beinspected and repaired. WCAP17091Pidentifies the specific inspection depth belowwhich any type of tube degradation is shownto have no impact on the performance criteriain NEI 9706 Rev. 2, Steam GeneratorProgram Guidelines [Reference 3] and TS6.8.4.j, Steam Generator (SG) Program.

The proposed change that alters the SGinspection and reporting criteria maintainsthe required structural margins of the SGtubes for both normal and accidentconditions. Nuclear Energy Institute 9706,Steam Generator Program Guidelines

VerDate Nov2008 21:38 Aug 27, 2009 Jkt 217001 PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 E:\FR\FM\28AUN1.SGM 28AUN1


2/5

44406 Federal Register / Vol. 74, No. 166/ Friday, August 28, 2009/ Notices

[Reference 3], and NRC Regulatory Guide(RG) 1.121, Bases for Plugging DegradedPWR Steam Generator Tubes [Reference 7],are used as the bases in the development ofthe limited tubesheet inspection depthmethodology for determining that SG tubeintegrity considerations are maintainedwithin acceptable limits. RG 1.121 describesa method acceptable to the NRC for meetingGeneral Design Criteria (GDC) 14, Reactor

Coolant Pressure Boundary, GDC 15,Reactor Coolant System Design, GDC 31,Fracture Prevention of Reactor CoolantPressure Boundary, and GDC 32,Inspection of Reactor Coolant PressureBoundary, by reducing the probability andconsequences of a SGTR. RG 1.121 concludesthat by determining the limiting safeconditions for tube wall degradation, theprobability and consequences of a SGTR arereduced. This RG uses safety factors on loadsfor tube burst that are consistent with therequirements of Section III of the AmericanSociety of Mechanical Engineers (ASME)Code.

For axially oriented cracking locatedwithin the tubesheet, tube burst is precluded

due to the presence of the tubesheet. Forcircumferentially oriented cracking,Westinghouse WCAP17091P defines alength of degradation-free expanded tubingthat provides the necessary resistance to tubepullout due to the pressure induced forces,with applicable safety factors applied.Application of the limited hot and cold legtubesheet inspection criteria will precludeunacceptable primary to secondary leakageduring all plant conditions. The SLB leak ratefactor for Turkey Point Units 3 and 4 is 1.82(Table 97 in WCAP17091P). Multiplyingthis factor by the room temperature TSoperational leak rate limit of 150 gpd throughany one SG indicates that an assumedprimary to secondary accident induced leak

rate of 273 gpd or greater through any one SGis required to ensure that the limiting designbasis accident assumption is not exceeded (atroom temperature). This condition issatisfied by the current UFSAR assumedprimary to secondary accident induced leakrate of 500 gpd (355 gpd adjusted to roomtemperature) through any one SG for SLB.

Therefore, the proposed change does notinvolve a significant reduction in any marginof safety.

The NRC staff has reviewed thelicensees analysis and, based on thisreview, it appears that the threestandards of 10 CFR 50.92(c) aresatisfied. Therefore, the NRC staff

proposes to determine that theamendment request involves nosignificant hazards consideration.

The Commission is seeking publiccomments on this proposeddetermination. Any comments receivedwithin 30 days after the date ofpublication of this notice will beconsidered in making any finaldetermination.

Normally, the Commission will notissue the amendment until theexpiration of 60 days after the date ofpublication of this notice. The

Commission may issue the licenseamendment before expiration of the 60-day period provided that its finaldetermination is that the amendmentinvolves no significant hazardsconsideration. In addition, theCommission may issue the amendmentprior to the expiration of the 30-daycomment period should circumstances

change during the 30-day commentperiod such that failure to act in atimely way would result, for example,in derating or shutdown of the facility.Should the Commission take actionprior to the expiration of either thecomment period or the notice period, itwill publish in the Federal Register anotice of issuance. Should theCommission make a final No SignificantHazards Consideration Determination,any hearing will take place afterissuance. The Commission expects thatthe need to take this action will occurvery infrequently.

Written comments may be submittedby mail to the Chief, Rulemaking,Directives and Editing Branch (RDB),TWB05B01M, Division ofAdministrative Services, Office ofAdministration, U.S. Nuclear RegulatoryCommission, Washington, DC 205550001, and should cite the publicationdate and page number of this FederalRegister notice. Written comments mayalso be faxed to the RDB at 3014923446. Documents may be examined,and/or copied for a fee, at the NRCsPublic Document Room (PDR), locatedat One White Flint North, Public FileArea O1 F21, 11555 Rockville Pike (first

floor), Rockville, Maryland.Within 60 days after the date of

publication of this notice, any person(s)whose interest may be affected by thisaction may file a request for a hearingand a petition to intervene with respectto issuance of the amendment to thesubject facility operating license.Requests for a hearing and a petition forleave to intervene shall be filed inaccordance with the CommissionsRules of Practice for DomesticLicensing Proceedings in 10 CFR Part2. Interested person(s) should consult acurrent copy of 10 CFR 2.309, which is

available at the Commissions PDR,located at One White Flint North, PublicFile Area O1F21, 11555 Rockville Pike(first floor), Rockville, Maryland.Publicly available records will beaccessible from the AgencywideDocuments Access and ManagementSystems (ADAMS) Public ElectronicReading Room on the Internet at theNRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If arequest for a hearing or petition forleave to intervene is filed by the abovedate, the Commission or a presiding

officer designated by the Commission orby the Chief Administrative Judge of theAtomic Safety and Licensing BoardPanel, will rule on the request and/orpetition; and the Secretary or the ChiefAdministrative Judge of the AtomicSafety and Licensing Board will issue anotice of a hearing or an appropriateorder.

As required by 10 CFR 2.309, apetition for leave to intervene shall setforth with particularity the interest ofthe petitioner in the proceeding, andhow that interest may be affected by theresults of the proceeding. The petitionshould specifically explain the reasonswhy intervention should be permittedwith particular reference to thefollowing general requirements: (1) Thename, address and telephone number ofthe requestor or petitioner; (2) thenature of the requestors/petitionersright under the Act to be made a partyto the proceeding; (3) the nature and

extent of the requestors/petitionersproperty, financial, or other interest inthe proceeding; and (4) the possibleeffect of any decision or order whichmay be entered in the proceeding on therequestors/petitioners interest. Thepetition must also identify the specificcontentions which the petitioner/requestor seeks to have litigated at theproceeding.

Each contention must consist of aspecific statement of the issue of law orfact to be raised or controverted. Inaddition, the petitioner/requestor shallprovide a brief explanation of the basesfor the contention and a concise

statement of the alleged facts or expertopinion which support the contentionand on which the petitioner intends torely in proving the contention at thehearing. The petitioner/requestor mustalso provide references to those specificsources and documents of which thepetitioner is aware and on which thepetitioner intends to rely to establishthose facts or expert opinion. Thepetition must include sufficientinformation to show that a genuinedispute exists with the applicant on amaterial issue of law or fact.Contentions shall be limited to matters

within the scope of the amendmentunder consideration. The contentionmust be one which, if proven, wouldentitle the petitioner to relief. Apetitioner/requestor who fails to satisfythese requirements with respect to atleast one contention will not bepermitted to participate as a party.

Those permitted to intervene becomeparties to the proceeding, subject to anylimitations in the order granting leave tointervene, and have the opportunity toparticipate fully in the conduct of thehearing.



3/5


If a hearing is requested, theCommission will make a finaldetermination on the issue of nosignificant hazards consideration. Thefinal determination will serve to decidewhen the hearing is held. If the finaldetermination is that the amendmentrequest involves no significant hazardsconsideration, the Commission may

issue the amendment and make itimmediately effective, notwithstandingthe request for a hearing. Any hearingheld would take place after issuance ofthe amendment. If the finaldetermination is that the amendmentrequest involves a significant hazardsconsideration, any hearing held wouldtake place before the issuance of anyamendment.

All documents filed in NRCadjudicatory proceedings, including arequest for hearing, a petition for leaveto intervene, any motion or otherdocument filed in the proceeding prior

to the submission of a request forhearing or petition to intervene, anddocuments filed by interestedgovernmental entities participatingunder 10 CFR 2.315(c), must be filed inaccordance with the NRC E-Filing rule,which the NRC promulgated on August28, 2007 (72 FR 49139). The E-Filingprocess requires participants to submitand serve all adjudicatory documentsover the internet, or in some cases tomail copies on electronic storage media.Participants may not submit papercopies of their filings unless they seeka waiver in accordance with theprocedures described below.

To comply with the proceduralrequirements of E-Filing, at least ten(10) days prior to the filing deadline, thepetitioner/requestor must contact theOffice of the Secretary by e-mail [email protected], or by calling(301) 4151677, to request (1) a digitalID certificate, which allows theparticipant (or its counsel orrepresentative) to digitally signdocuments and access the ESubmittalserver for any proceeding in which it isparticipating; and/or (2) creation of anelectronic docket for the proceeding(even in instances in which the

petitioner/requestor (or its counsel orrepresentative) already holds an NRC-issued digital ID certificate). Eachpetitioner/requestor will need todownload the Workplace FormsViewerTM to access the ElectronicInformation Exchange (EIE), acomponent of the E-Filing system. TheWorkplace Forms ViewerTM is free andis available at http://www.nrc.gov/sitehelp/esubmittals/installviewer.html.Information about applying for a digitalID certificate is available on NRCspublic Web site at http://www.nrc.gov/

sitehelp/esubmittals/apply-certificates.html.

Once a petitioner/requestor hasobtained a digital ID certificate, had adocket created, and downloaded the EIEviewer, it can then submit a request forhearing or petition for leave tointervene. Submissions should be inPortable Document Format (PDF) in

accordance with NRC guidanceavailable on the NRC public Web site athttp://www.nrc.gov/site-help/e-submittals.html. A filing is consideredcomplete at the time the filer submits itsdocuments through EIE. To be timely,an electronic filing must be submitted tothe EIE system no later than 11:59 p.m.Eastern Time on the due date. Uponreceipt of a transmission, the E-Filingsystem time-stamps the document andsends the submitter an e-mail noticeconfirming receipt of the document. TheEIE system also distributes an e-mailnotice that provides access to the

document to the NRC Office of theGeneral Counsel and any others whohave advised the Office of the Secretarythat they wish to participate in theproceeding, so that the filer need notserve the documents on thoseparticipants separately. Therefore,applicants and other participants (ortheir counsel or representative) mustapply for and receive a digital IDcertificate before a hearing request/petition to intervene is filed so that theycan obtain access to the document viathe E-Filing system.

A person filing electronically usingthe agencys adjudicatory e-filing system

may seek assistance through theContact Us link located on the NRCWeb site at http://www.nrc.gov/site-help/e-submittals.htmlor by calling theNRC Meta-System Help Desk, which isavailable between 8 a.m. and 8 p.m.,Eastern Time, Monday through Friday,excluding government holidays. TheMeta-System Help Desk can becontacted by telephone at 18666727640 or by e-mail [email protected].

Participants who believe that theyhave a good cause for not submittingdocuments electronically must file a

motion, in accordance with 10 CFR2.302(g), with their initial paper filingrequesting authorization to continue tosubmit documents in paper format.Such filings must be submitted by: (1)First class mail addressed to the Officeof the Secretary of the Commission, U.S.Nuclear Regulatory Commission,Washington, DC 205550001, Attention:Rulemaking and Adjudications Staff; or(2) courier, express mail, or expediteddelivery service to the Office of theSecretary, Sixteenth Floor, One WhiteFlint North, 11555 Rockville, Pike,

Rockville, Maryland, 20852, Attention:Rulemaking and Adjudications Staff.Participants filing a document in thismanner are responsible for serving thedocument on all other participants.Filing is considered complete by first-class mail as of the time of deposit inthe mail, or by courier, express mail, orexpedited delivery service upondepositing the document with theprovider of the service.

Non-timely requests and/or petitionsand contentions will not be entertainedabsent a determination by theCommission or the presiding officer ofthe Atomic Safety and Licensing Boardthat the petition and/or request should

be granted and/or the contentionsshould be admitted, based on a

balancing of the factors specified in 10CFR 2.309(c)(1)(i)(viii).

Documents submitted in adjudicatoryproceedings will appear in NRCselectronic hearing docket which isavailable to the public at http://ehd.nrc.gov/ehd_proceeding/home.asp,unless excluded pursuant to an order ofthe Commission, an Atomic Safety andLicensing Board, or a Presiding Officer.Participants are requested not to includepersonal privacy information, such associal security numbers, homeaddresses, or home phone numbers intheir filings, unless an NRC regulationor other law requires submission of suchinformation. With respect tocopyrighted works, except for limited

excerpts that serve the purpose of theadjudicatory filings and wouldconstitute a Fair Use application,participants are requested not to includecopyrighted materials in theirsubmissions.

For further details with respect to thislicense amendment application, see theapplication for amendment dated July23, 2009, which is available for publicinspection at the Commissions PDR,located at One White Flint North, FilePublic Area O1 F21, 11555 RockvillePike (first floor), Rockville, Maryland.Publicly available records will be

accessible electronically from theAgencywide Documents Access andManagement Systems (ADAMS) PublicElectronic Reading Room on the Internetat the NRC Web site, http://www.nrc.gov/readingrm/adams.html.Persons who do not have access toADAMS or who encounter problems inaccessing the documents located inADAMS, should contact the NRC PDRReference staff by telephone at 18003974209, 3014154737, or by [email protected].



4/5


5/5


Attachment 1General TargetSchedule for Processing and ResolvingRequests for Access to SensitiveUnclassified Non-SafeguardsInformation (SUNSI) in ThisProceeding

Day Event

0 .......................................... Publication of [Federal Register notice/other notice of proposed action and opportunity for hearing], includingorder with instructions for access requests.10 ........................................ Deadline for submitting requests for access to SUNSI with information: Supporting the standing of a potential party

identified by name and address; and describing the need for the information in order for the potential party toparticipate meaningfully in an adjudicatory proceeding.

[20, 30 or 60] ...................... Deadline for submitting petition for intervention containing: (i) Demonstration of standing; (ii) all contentions whoseformulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestorreply).

20 ........................................ NRC staff informs the requester of the staffs determination whether the request for access provides a reasonablebasis to believe standing can be established and shows need for SUNSI. NRC staff also informs any party tothe proceeding whose interest independent of the proceeding would be harmed by the release of the informa-tion. If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins documentprocessing (preparation of redactions or review of redacted documents).

25 ........................................ If NRC staff finds no need for SUNSI or likelihood of standing, the deadline for petitioner/requester to file a mo-tion seeking a ruling to reverse the NRC staffs denial of access; NRC staff files copy of access determinationwith the presiding officer (or Chief Administrative Judge or other designated officer, as appropriate). If NRC stafffinds need for SUNSI, the deadline for any party to the proceeding whose interest independent of the pro-

ceeding would be harmed by the release of the information to file a motion seeking a ruling to reverse the NRCstaffs grant of access.30 ........................................ Deadline for NRC staff reply to motions to reverse NRC staff determination(s).40 ........................................ (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information

processing and file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/li-censee to file Non-Disclosure Agreement for SUNSI.

A ......................................... If access granted: Issuance of presiding officer or other designated officer decision on motion for protective orderfor access to sensitive information (including schedule for providing access and submission of contentions) ordecision reversing a final adverse determination by the NRC staff.

A+3 ..................................... Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuingthe protective order.

A+28 ................................... Deadline for submission of contentions whose development depends upon access to SUNSI. However, if morethan 25 days remain between the petitioners receipt of (or access to) the information and the deadline for filingall other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file itsSUNSI contentions by that later deadline.

A+53 (Contention receipt+25).

Answers to contentions whose development depends upon access to SUNSI.

A+60 (Answer receipt +7) .. Petitioner/Intervenor reply to answers.B ......................................... Decision on contention admission.

[FR Doc. E920808 Filed 82709; 8:45 am]

BILLING CODE 759001P

SMALL BUSINESS ADMINISTRATION

[Disaster Declaration #11849 and #11850]

Tennessee Disaster #TN00031

AGENCY: U.S. Small BusinessAdministration.

ACTION: Notice.

SUMMARY: This is a Notice of thePresidential declaration of a majordisaster for Public Assistance Only forthe State of Tennessee (FEMA1856DR), dated 08/21/2009.

Incident: Severe Storms and Flooding.Incident Period: 07/15/2009 through

07/17/2009.

DATES: Effective Date: 08/21/2009.Physical Loan Application Deadline

Date: 10/20/2009.

Economic Injury (EIDL) LoanApplication Deadline Date: 05/21/2010.

ADDRESSES: Submit completed loanapplications to: U.S. Small BusinessAdministration, Processing andDisbursement Center, 14925 KingsportRoad, Fort Worth, TX 76155.

FOR FURTHER INFORMATION CONTACT: A.Escobar, Office of Disaster Assistance,U.S. Small Business Administration,409 3rd Street, SW., Suite 6050,

Washington, DC 20416.SUPPLEMENTARY INFORMATION: Notice ishereby given that as a result of thePresidents major disaster declaration on08/21/2009, Private Non-Profitorganizations that provide essentialservices of governmental nature may filedisaster loan applications at the addresslisted above or other locally announcedlocations.

The following areas have beendetermined to be adversely affected bythe disaster:

Primary Counties: Chester, Clay,Decatur, Jackson, Overton, Wayne.

The Interest Rates are:

Percent

Other (Including Non-Profit Orga-nizations) with Credit AvailableElsewhere ................................. 4.500

Businesses and Non-Profit Orga-nizations without Credit Avail-

able Elsewhere .... ... .. ... .. ... .. ... .. . 4.000

The number assigned to this disasterfor physical damage is 11849B and foreconomic injury is 11850B.

(Catalog of Federal Domestic AssistanceNumbers 59002 and 59008)

James E. Rivera,

Acting Associate Administrator for DisasterAssistance.

[FR Doc. E920772 Filed 82709; 8:45 am]

BILLING CODE 802501P


Turkey Point Leakage Limits

Documents

Transcript of Turkey Point Leakage Limits