ML15209A512

Prairie Island Technical Specifications - Updating Instructions -Effective Date: 7/24/2015

ML15209A512
Person / Time
Site:	Prairie Island
Issue date:	07/17/2015
From:	Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
Download: ML15209A512 (17)

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TInK02PASSPORT DOCUMENTToFacilityAddressFromAddressCityCountryEmailContactDate/TimeTrans No.Total Items:NRC DOC CONTROL DESK COPY #383PI DepartmentONE WHITE FLINT NORTH11555 ROCKVILLE PIKEROCKVILLE, MD 20852-2738C-DOC CNTRL-PI Attention:1717 WAKONADE DR EASTTRANSMITTALPage:HllHlllll Ulllll I I tNllllllllWELCHUNITED STATESState: MN Postal Code: 5508907/17/2015 10:16 Transmittal Group Id:000283843 Title:000020000031107Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy # Media Cpys0001 PI LIC BASE ISFSI BASES ISSUED 010 383 HC 010002 PI LIC TECH ISFSI TECH SPECS ISSUED 009 383 HC 01If a document was not received or is no longer required check the response below and return to sender.Documents noted above not received (identify those not received).I no longer require distribution of these documents (identify those no longer required).Date: Signature:

PRAIRIE ISLANDTechnical SpecificationsUPDATING INSTRUCTIONSEffective Date: 7/24/2015PINGP tj ISFSIREMOVE INSERTPage Revision Doc Type Page RevisionAmendment/All (6 pgs) 8 License All (6 pgs) 9pagesRecord ofRoR-1 5/14/14 Revisions RoR-1 7/24/2015A, B 6/25/14 Currentpage list A, B 7/24/2015BasesB RoR-l 8/27/13 Record of B RoR-I 7/24/2015RevisionsBasesA 8/27/13 Current A 7/24/2015PagesREMOVE INSERTPage Revision Sect/Chap Page Revision3.1.2-2 7 3.1.2 3.1.2-2 9n/a 3.1.2-3 9B 3.1.2-.4 8 3.1.2 3.1.2-4 10B-3.1.2-5 7 3.1.2 3.1.2-5 10 NORTHERN STATES POWER COMPANY, A MINNESOTA CORPORATION (NSPM)DOCKET NO. 72-10PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATIONAMENDMENT TO MATERIALS LICENSE NO. SNM-2506Amendment No. 9License No. SNM-2506The Nuclear Regulatory Commission (the Commission) has found that:A. The amendment application dated May 23, 2014, as supplemented by the letteron November 19, 2014, complies with the standards and requirements of theAtomic Energy Act of 1954, as amended (the Act), and the Commission'sregulations set forth in 10 CFR Chapter I;B. The Prairie Island Independent Spent Fuel Storage Installation will continue tooperate in conformity with the application, as amended, the provisions of the Act,and the rules and regulations of the Commission;C. There is reasonable assurance that (i) the activities authorized by thisamendment can be conducted without endangering public health and safety, and(ii) such activities will be conducted in compliance with the Commission'sregulations;D. The issuance of this amendment will not be inimical to the common defense andsecurity or to public health and safety; andE. The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2. Accordingly, the license is amended by the enclosed changes to Materials License No.SNM-2506, indicated by margin notations.

3. This license amendment is effective as of the date of its issuance.FOR THE U.S. NUCLEAR REGULATORY COMMISSION/RA/Michele Sampson, ChiefSpent Fuel Licensing BranchDivision of Spent Fuel ManagementOffice of Nuclear Material Safetyand Safeguards

Enclosure:

Amended LicenseDate of Issuance: April 10, 2015 NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION(10-2000)10 CFR 72 PAGE 1 OF 4 PAGESLICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL ANDHIGH-LEVEL RADIOACTIVE WASTEPursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title10, Code of Federal Regulations, Chapter 1, Part 72, and in reliance on statements and representations heretofore made by thelicensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel andother radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and atthe place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with theregulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of theAtomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear RegulatoryCommission now or hereafter in effect and to any conditions specified herein.LicenseeNorthern States Power Company, a 3. License No. SNM-2506Minnesota corporation (NSPM) 1jeiedment No 92. 414 Nicollet Mall .Minneapolis, Minnesota, 55401-19274. Expiration Date October 31, 20135. Docket or 72-10<'Reference No.6. Byproduct, Source, and/&,. .7. -Chemical or Physical Form .,8 Maximum Amount That LicenseeSpecial Nuclear Material X May P6ssess at Any One Time-' Under.This License* Spent fuel assemblie's fromPrairie Island Nuclear-StationUnits I and 2 reactors, usingnatural water for cooling andenriched not greater than. 3.85(TN-40) and not greater.4han5.00 (TN-40HT) percent 9U235,and associated radioactive<materials related to receipt,.storage and transfer of the fuel.assembliesB. Irradiated fuel assembly insertsfrom the Prairie Island NuclearStation Units 1 and 2 reactors.An insert may be a burnablepoison rod assembly (BPRA) ora thimble plug device (TPD).A. As U2 .cladwith zirconium.or zirconiurn alloys~. ;4iB SS5 304 str.ucture, lnconel718 spring, and .boratedpyrex glass.A.715.29 TeU of spent fuelassermibliesB. One BPRA or TPD per spent fuelassembly.Northern States Power Company was incorporated in Minnesota as a wholly owned subsidiary of XcelEnergy Inc., effective August 18, 2000. This license, as amended, was amended to reflect the.Commission's consent per 10 CFR Part 72, Section 72.50, to the license transfer approved by orderdated May 12, 2000.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGES(10.2000)2 License No. SNM-2506 Amendment No. 9LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEARFUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10SUPPLEMENTARY SHEET9. Authorized Use: For use in accordance with the conditions in this license and the TechnicalSpecifications contained in Appendix A. The basis for this license was submitted in the Safety Analysisdated August 31, 1990, and supplements dated October 29, 1990; April 2, June 5, October 9 and 31,November 15, December 11, 20, and 23, 1991; January 17, February 6, 10, and 12, March 2 and 5,April 3, 22, and 23, July 10, August 12, 13, and 14, 1992; October 2, 1995; August 31, October 29, andNovember 24, 1999; and February 2, March 14, October 16, 2000; and February 12, 2001; March 28,June 26, and August 29, 2008; June 26, and September 28, 2009; January 18, May 4, July 27, 2010;and July 17, December 5, 2013, and May 23, 2014 and as further supplemented and amended inaccordance with 10 CFR 72.70 and 10 CFR 72.48.The material identified in 6 and 7 above is authorized for receipt, possession, storage, and transfer.10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored atthe Prairie Island ISFSI located on the Prare Nuclear.Generatg Plant site in Goodhue County,Minnesota.11. This site is described in Chabppter2 of the Technical Specifications anh&-Safety Analysis Report (TS/SAR)for the Prairie Island ISFSJ..12. The Technical Specjfications contained in Appendix A attached hereto are iicprporated into the license.NSPM shall operate the installation in accordance with the Technical Specifications in Appendix A.NSPM shall fullyimplement and maintain in effect all provisions, of the ISFSl-bphysical security, guardtraining and qualification, and safeguairds plans previously approved by the Commissionand all amendments made authorityof 10,FR 72.56, 72.44(e), and 72.186. The plans,which contain saf~guards informatioi undei-0 73 .21, are entitild: "Prairie IslandNuclear Generating Plant Independent Spent Fue StorageInTstallation Security Plan,"Revision 0, submitted by letter-datedMarc 10... , 1.992-;',ie Island Nuclearid-'nerating PlantIndependent Spent Fuel Storage Installation Security Force Trainingiand Quaiifihcation Plan," Revision 0,submitted by letter dated Marchtjl0, 1992; and "Praiie Island Niclear Generating Plant IndependentSpent Fuel Storage Installation.Safeguards ContirgecynyPlan,"Revision 0.,su'bmitted by letter datedMarch 10, 1992.14. The Technical Specificatioijs1for Environmental Protdction contained iinppendix A attached hereto areincorporated into the license')". .Specifications required pursuant to 10,CFR.72.44(d), limits on the release of radioactivematerials for compliance with limits of 10 CFR Par20 and "as low as is reasonably achievableobjective" for effluents are not applicable. Spent fuel storage cask external surface contamination withinthe limits of Technical Specification 3.2.1 ensures that the offsite dose will be inconsequential. Inaddition, there are no normal or off-normal releases or effluents expected from the double-sealedstorage casks of the ISFSI.Specifications required pursuant to 10 CFR 72.44(d)(1), for operating procedures, for control ofeffluents, and for the maintenance and use of equipment in radioactive waste treatment systems, tomeet the requirements of 10 CFR 72.104 are not applicable. There are, by the design of the sealedstorage casks at the ISFSI, no effluent releases. Also, cask loading and unloading operations andBwaste treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of itsoperating licenses.

Ui NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 4 PAGES I(10-2000) License No. SNM-2506 Amendment No. 9LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEARFUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10SUPPLEMENTARY SHEET15. No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperationallicense conditions are satisfied:A A training exercise (Dry Run) of all spent fuel storage cask loading and handling activities shallbe held, which shall include, but not be limited to, those listed, and which need not be performedin the order listed:a. Moving cask in and out of spent fuel pool areab. Loading fuel assembly (using dummy assembly)c. Cask drying, sealing, and cover gas backfilling operationsd. Moving cask to, and, on, the storage pade. Returning the cask-io the auxiliary buildingf. Unloadingft4ii caskg. Decontarmiihating the caskh. All dry-run activities shall be done usihgwritten procedures ';i. The activities listed abov&~hall be' performed or modified and performed to show that eachactivitan be before acatual, fuel loading .: "B The Prairie Island NLuclear Generating Plant Emergency Plan shall be,.reviewed and modified, asrequired, tq.Jinclude theISFSI.C A training module shall be developed for the Prairie Island Nuclear 9enerating Plant TrainingProgram, establishing an ISFSI Traihing cand 0ertification Program thalt will include the following:a. Cask Designi(overview)b. ISFSI Facility DesignrI(0verview)c. ISFSI Safety Analysis (overview)d. Fuel loading and cask handling procedures and off-normal procedurese. ISFSI License (overview).D The Prairie Island Nuclear Generating Plant Radiation Protection Procedures shall be reviewedand modified, as required, to include the ISFSI.E The Prairie Island Nuclear Generating Plant Administrative Procedures shall be reviewed andmodified, as required, to include the ISFSI.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES(10-2000)1:0 CFR 72 License No. SNM-2506 Amendment No. 9LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR DoktrRerncN.721SUPPLEMENTARY SHEETF A procedure shall be developed and implemented for the documentation of the characterizationsperformed to select spent fuel to be stored in the casks. Such procedure shall includeindependent verification of fuel assembly selection by an individual other than the originalindividual making the selection.G A procedure shall be developed and implemented for two independent determinations (twosamples analyzed by different individuals) of the boron concentration in the water used to fill thecask cavity for fuel loading and unloading activities.H Written procedures shall be implemented to describe actions to be taken during operation, off-normal, and emergency conditions.16. The design, construction, and operation of the ISFSI shall be accomplished in accordance with the U.S.Nuclear Regulatory Commission Regulation's specifiedc inTitle. 10 of the U.S. Code of FederalRegulations. All commitments to the applicable NRC regulator) guides and to engineering andconstruction codes shall be .carried out. 717. Fuel and cask movemeritand handling activities that are to be perform6e"'in the Prairie Island NuclearGenerating Plant Auxiiary Building will be governed by the requiremen ofthe Prairie Island NuclearGenerating Plant Facility Operating Licenses (DRP-42 and -60) and associated TechnicalSpecifications. *The TN-40HT confinement boundary baIse material:.and associp wsated welds shall be helium leak tested atthe fabricator in acc6rdance with AN.N 14.5 to citeria. The TN-4O0bpnfinement boundarybase material and,*ssociated welds shall be helium leak tested at the fabricator in accordance withANSI N14.5 to "leaktight" criteria, if fabriatcatetdeafedateAte,.6 Amendment No: 7 approval.This license is effective as_.f the date of issuance shown below.19.2' 2.4.9, 9,9,SFOR THE U.S. NUCLEAR REGULATORY COMMISSION.S i * 'IR-A!Michele Sampson, :iefSpent Fuel Licensing 'BranchDivis;ionE.bfSp0ent Fuel ManagementOffice of Nuclear Material Safetyand SafeguardsWashington, DC 20555Date of Issuance: October 19, 1993As amended byAmendment No. 9 dated April 10, 2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATIONRECORD OF REVISIONSTECHNCIAL SPECIFICATION CHANGES AND LICENSE AMENDMENTSNSP Revision(REV) No.Date ofIssueLicenseAmendment No.RemarksORIGINAL123455*10/19/933/17/942/1/968/7/008/18/002/12/015/1/089/22/088/20/103/10/14License Issued12345Correction toAmendment 5Correction to Page 1 of LicenseChange to p. 6-1Change to p. 6-1License reissue onlyChange to Sec. 3/4Correction to page 1 of License, perNRC letter dated February 7, 2008Transfer of operating authorityReformatted and Inclusion ofTN-40HTdesignRevised absorber and aluminum plateminimum allowed thermalconductanceRevise surveillance requirements inTS 3.1.26786.7897/24/20159RoR-17/24/2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATIONTECHNCIAL SPECIFICATION CURRENT PAGE LISTLICENSE SNM-2506PAGE AMENDMENTNRC Findings & 9issuance (1st page)NRC Findings &issuance (2n page)1 92 93 94 9Appendix A -Record of Revisionr PAGE DateRoR-1 7/24/2015Page ListPAGE DateA 7/24/2015B 7/24/2015Appendix A -Table of Contents[ i 8/20/10Appendix A -Technical SpecificationsPAGE REVISION No.1.1-1 71.1-2 71.1-3 71.2-1 71.2-2 71.2-3 71.3-1 7.1.3-2 71.3-3 71.3-4 71.3-5 71.4-1 7Appendix A -Technical SpecificationsPAGE REVISION No.1.4-2 71.4-3 71.4-4 71.4-5 71.4-6 72.0-1 72.0-2 72.0-3 73.0-1 73.0-2 73.0-3 73.0-4 73.0-5 73.1.1-1 73.1.1-2 73.1.2-1 73.1.2-2 93.1.2-3 93.1.3-1 73.1-3-2 73.1'4-1 73.1.4-2 73.1.5-1 73.1.5-2 73.1.6-1 73.1.6-2 73.2.1-1 73.2.1-2 73.2.2-1 73.2.2-2 73.3.1-1 73.3.1-2 73.4.1-1 73.4.1-2 74.0-1 7A7/24/2015 TECHNCLAL SPECIFICATION CURRENT PAGE LIST (CONTINUED)PAGE REVISION No.4.0-2 74.0-3 74.0-4 74.0-5 8*4.0-6 74.0-7 74.0-8 74.0-9 74.0-10 74.0-11 74.0-12 74.0-13 84.0-14 74.0-15 74.0-16 74.0-17 75:0-1 75.0-2 7*Re-issued 6/3/14 to add sidebarsB7/24/2015 Cask Helium Backfill Pressure3.1.2ACTIONS (continued)CONDITION REQUIRED ACTION COMPLETIONTIMEB. Required Action A. 1 and B. 1 Return cask to pool and 7 daysassociated Completion reflood.Time not met.SURVEILLANCE REQUIREMENTSSURVEILLANCE FREQUENCYSR 3.1.2.1 -----------------NOTE ----------------Not required to be met prior to the specifiedFrequency.Verify that a helium environment has been Once within 34established in the cask cavity, hours aftercommencing caskdrainingSR 3.1.2.2 -----------------NOTE ----------------Not required to be met prior to the specifiedFrequency.Verify that the cask cavity pressure is < 14 mbar Once prior toabsolute. pressurization(SR 3.1.2.3)Prairie Island ISFSITechnical SpecificationsAmendment 93.1.2-2 Cask Helium Backfill Pressure3.1.2SURVEILLANCE REQUIREMENTS (continued)SURVEILLANCE FREQUENCYSR 3.1.2.3 -----------------NOTE ----------------Not required to be met prior to the specifiedFrequency.Verify that the cask cavity helium pressure is Once prior leak> 1345 mbar absolute and < 1445 mbar absolute, testing(SR 3.1.3.1)Prairie Island ISFSITechnical SpecificationsAmendment 9 13.1.2-3 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATIONRECORD OF REVISION BASES CHANGES AND LICENSE AMENDMENTSNSPM Date of LicenseRevision Issue Amendment No. Remarks(REV) No.1 t"hrnrh" 1 iriainal Car iTnVn nRvt AqfTp('hn1(rt:,788/20/201012/12/20127SpecificationsInitial Issue of revised format andInclusion of TN-40HT design.Clarify "helium environment"requirement in ISFSI SR 3.1.2.1.Revise B 3.1.5 paraphrase ofregulatory requirements.Revise SR for B 3.1.2.9108/27/137/24/20159Prairie IslandISFSIB RoR- I7/24/2015

.BASES CURRENT PAGESPAGE DATEB RoR-1 7/24/2015A 7/24/2015i 8/20/10PAGE REVISION No.B 2.0-1 7B 2.0-2 7B 3.0-1 7B 3.0-2 7B 3.0-3 7B 3.0-4 7B 3.0-5 7B 3.0-6 7B 3.0-7 7B 3.0-8 7B 3.0-9 7B 3.0-10 7B 3.0-11 7B 3.1.1-1 7B 3.1.1-2 7B 3.1.1-3 7B 3.1.2-1 7B 3.1.2-2 7B 3.1.2-3 7B 3.1.2-4 10B 3.1.2-5 10PAGE REVISION No.B 3.1.3-1 7B 3.1.3-2 7B 3.1.3-3 7B 3.1.3-4 7B 3.1.4-1 7B 3.1.4-2 7B 3.1.4-3 7B 3.1.5-1 9B 3.1.5-2 7B 3.1.5-3 7B 3.1.5-4 7B 3.1.5-5 7B 3.1.6-1 7B 3.1.6-2 7B 3.1.6-3 7B 3.2.1-1 7B 3.2.1-2 7B 3.2.1-3 7B 3.2.2-1 7B.3.2.2-2 7B 3.2.2-3 7B 3.3.1-1 7B 3.3.1-2 7B 3.3.1-3 7B 3.3.1-4 7B 3.4.1-1 7B 3.4.1-2 7B 3.4.1-3 7Prairie IslandISFSIA7/24/2015 Cask Helium Backfill PressureB 3.1.2BASESACTIONS B.1(continued)If a helium cask environment cannot be achieved and maintained,fuel clad temperatures may increase beyond the analyzed condition.Therefore, the cask will be required to be placed back into the spentfuel pool within 7 days and re-flooded. This time is sufficient timeto return the cask to the spent fuel pool and re-flood the cask cavity.Once placed in the spent fuel pool, the fuel is provided adequatedecay heat removal to maintain the loaded fuel within limits.SURVEILLANCE SR 3.1.2.1REQUIREMENTSThis Surveillance is modified by a Note. The Note clarifies thatmeeting the Surveillance is not required, and thus there is not afailure to meet the LCO per SR 3.0.1 and SR 3.0.4 does not apply,prior to the specified Frequency.While, the effective thermal conductivity of the cavity gas is notdependant upon pressure, it is dependant upon the make-up of thegases within the cask cavity. Thermal analyses have shown thatmaximum fuel cladding temperature limit of 752°F is not exceededduring LOADING OPERATIONS provided a 75% heliumenvironment (based on partial pressure) is established within thecask. Thus, design basis heat removal requirements will be satisfiedprovided an environment of at least 75% helium has beenestablished, and maintained in the cask cavity within the 34 hourvacuum drying time frame (Reference 3).SR 3.1.2.2This Surveillance is modified by a Note. The Note clarifies thatmeeting the Surveillance is not required, and thus there is not afailure to meet the LCO per SR 3.0.1, and SR 3.0.4 does not applyprior to the specified Frequency.Evacuating the cask cavity to the specified vacuum prior topressurization (see SR 3.1.2.3) will ensure that the amount ofoxidizing gases remaining in the cavity will be no greater thanPrairie IslandISFSI B 3.1.2-4 Revision 10I Cask Helium Backfill PressureB 3.1.2SURVEILLANCEREQUIREMENTM(continued)0.25% (volume). Below this concentration, degradation ofstored cladding and fuel materials is not expected.SR 3.1.2.3This Surveillance is modified by a Note. The Note clarifies thatmeeting the Surveillance is not required, and thus there is not afailure to meet the LCO per SR 3.0.1 and SR 3.0.4 does not apply,prior to the specified Frequency.The long-term integrity of the stored fuel is dependent on storage ina dry, inert environment and maintenance of adequate heat transfermechanisms. Filling the cask cavity with helium at the initialpressure, following the evacuation in SR 3.1.2.2, will ensure that theamount of oxidizing gases remaining in the cavity will be no greaterthan 0.25% (volume). At this concentration, degradation of storedcladding and fuel materials is not expected. Also, maintainingpressure below the upper limiting value will ensure that cask cavityinternal pressure will remain within limits for the life of the cask.Backfilling with helium at a specified pressure must be performedsuccessfully on each cask prior to performance of leak testingactivities and TRANSPORT and STORAGE OPERATIONS.REFERENCES 1. SAR Section 8.2.2. SAR Section A8.2.3. SAR Section A3.3.Prairie IslandISFSIB 3.1.2-5Revision 10