ML15209A509
| ML15209A509 | |
| 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: ML15209A509 (17) | |
Text
11PCX02PASSPORT DOCUMENTToFacilityAddressFromAddressCityCountryEmailContactDate/Time Trans No.Total Items:NMSS PROJECT MGR COPY #846PI Department 2 WHITE FLINT NORTH11545 ROCKVILLE PIKEROCKVILLE, MD 20852-2738 C-DOC CNTRL-PI Attention:
1717 WAKONADE DR EASTTRANSMITTAL Page:(11111 nuf~ll~lll[llllo inllll[i ilWELCHUNITED STATESState: MN Postal Code: 5508907/17/2015 10:16 Transmittal Group Id:000283853 Title:000020000031107 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy # Media Cpys0001 PI LIC BASE ISFSI BASES ISSUED 010 846 HC 010002 PI LIC TECH ISFSI TECH SPECS ISSUED 009 846 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 Specifications UPDATING INSTRUCTIONS Effective Date: 7/24/2015 PINGP ISFSIREMOVE INSERTPage Revision Doc Type Page RevisionAmendment/
All (6 pgs) 8 License All (6 pgs) 9pagesRoR-l 5/14/14 Record of RoR-l 7/24/2015 5/14/14Revisions A, B 6/25/14 Currentpage list A, B 7/24/2015 BasesB RoR-l 8/27/13 Record of B RoR-l 7/24/2015 Revisions BasesA 8/27/13 Current A 7/24/2015 PagesREMOVE 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 INSTALLATION AMENDMENT 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's regulations 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's regulations; 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
/RAIMichele Sampson, ChiefSpent Fuel Licensing BranchDivision of Spent Fuel Management Office of Nuclear Material Safetyand Safeguards
Enclosure:
Amended LicenseDate of Issuance:
April 10, 2015 NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION 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 Regulatory Commission now or hereafter in effect and to any conditions specified herein.LicenseeNorthern States Power Company, a 3. License No. SNM-2506Minnesota corporation (NSPM) 1oncl'erf 92. 414 Nicollet Mall .." .. 9Minneapolis, Minnesota, 55401-1927
- 4. Expiration Date October 31, 20135. Docket or 72 "10Reference No .72-16. Byproduct, Source, and/Qr 7. Chemical or Physical Form ......8. Maximum Amount That LicenseeSpecial Nuclear Material May:Possess at Any One Time"Underthis LicenseSpent fuel assemblies fromPrairie Island Nuclear StationUnits 1 and 2 reactors, usingnatural water for cooling andenriched not greater than. 3.85(TN-40) and not greate&4than 5.00 (TN-40HT) percentU`-235, and associated radioactives materials related to receipt;
,storage and transfer of the fuel.assemblies B. 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 U02 clad with zirconium.
' Jzirconiu al.oys. ,,B 8S'304,structure,l lcbnel718 spring, and boratedpyrex glass.A.715.29 TeU of spent fuelassemblies B. 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(102000)
License No. SNM-2506 Amendment No.9 9ILI CENSE 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 Technical Specifications 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 Prajide Island -Nuclear Generating Plant site in Goodhue County,Minnesota.".
- 11. This site is described in Chapter 2 of the Technical Specifications andSafety Analysis Report (TS/SAR)for the Prairie Island ISFSl,12. The Technical Specifications contained in Appendix A attached hereto are incorporated into the license.NSPM shall operateAlte installation in accordance with the Technical Specifications in Appendix A.NSPM shall fully. ,imnplement and m.aintain in effect all provisions of the ISFSl~phyisical
- security, guardtraining and q .nlicoriingency plans previously
- approved, by the Commission and all amendmeis made authority--of 72.44(e),
and 72.186. The plans,which contain safeguards information, protected brider 10 FR,73.21, are entitied:
"Prairie IslandNuclear Generating.
Plant e Stoag Ienstallation Physic"LSecurity Plan,"Revision 0, submitted by March 10, 1992-; "Pairie Island Nuclear.
G, enerating PlantIndependent Spent Fuel Storage Installation Security IF~orce Training':
and Qualification Plan," Revision 0,Independent,'
Spent ..... ng .... .. ........
Plant ,"d p nd nsubmitted by letter,,-,,ted March, 10.0 1992-; andi"Prdai]rie Islad NuclearGeneihg Plant Independent
- Spent Fuel Storage.
nIstallation Safeguards qCnti'gendcyPlan,',
Revision 0,, ubmitted by letter datedMarch 10, 1992.14. The Technical Specifications,?for Environmental-Protection contained n-ppendix A attached hereto areincorporated into the license.
.-Specifications required pursuant to 1 on the release of radioactive materials for compliance with limits of 10 CFR PRart20 'and "as low as is reasonably achievable objective" 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-sealed storage 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 andSwaste treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of itsoperating licenses.
10 CFR 72 License No. SNM-2506 Amendment No. 9LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEARFUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10IL SUPPLEMENTARY SHEET15. No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperational license 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 performed in 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 operations
- d. Moving cask to, and placing it on, the storagepad
- e. Returning the cask to the auxiliary buildingf. Unloading tlhi_ caskg. Decontaminating the cask.h. All dry-run activities shall be done using written procedures
- i. The activities listed above shall be perfored or modified and performed to show that eachactivity can be successfullyexcu.
bibefore actual fuel loading.B The Praire Island Nuclear Generating Plant Ebmergency Planshall bereviewed and modified, asrequired, to include the ISFSI .C A training module shall be develoiped forthe Prairie Island Nuclear Generating Plant TrainingProgram, establishing an ISFSI'Training and Certification Program that will include the following:
- a. Cask Designr(overview)
-:b. ISFSI Facility Design (Jverview)
- c. ISFSI Safety Analysis (overview)
- d. Fuel loading and cask handling procedures and off-normal procedures
- e. 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.
UNRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES10CFR72 License No. SNM-2506 Amendment No. 9LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR ,__FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10SUPPLEMENTARY SHEETF A procedure shall be developed and implemented for the documentation of the characterizations performed 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 Regulations specifiediniTitie 10 of the U.S. Code of FederalRegulations.
All commitments to the aIp"icable NRC regulatory guides and to engineering andconstruction codes shall be carried out.17. Fuel and cask movemerit-and handling activities that are to be performerd in the Prairie Island NuclearGenerating Plant Auxiliary Building will be governed by the requirements"ofthe Prairie Island NuclearGenerating Plant Facilit Operating Licenses (DRP-42 and -60) and associ ated Technical Specifications.
- 8. The TN-40HT confinement boundary ba se materialand associated welds sh al -e helium leak tested atthe fabricator in accordance with ANJ Ni 4.5 o "leaktight",citeria.
The TN-40-pnfinement boundarybase material and associated be helium leak tested at the fabricator in accordance withANSI N14.5 to "leaktight"
- criteria, iffabricated after the date of Amendment No. ".approval.
- 19. This license is effective as of the date of isuance shown below.FOR THE U.S. NUCLEAR REGULATORY COMMISSION IR/ iRAI.Michele Sampson, ChiefSpent Fuel Licensing BranchDivisionp.bf.Sbent Fuel Management Office of'Nuclear Material Safetyand Safeguards Washington, DC 20555Date of Issuance:
October 19, 1993As amended byAmendment No. 9 dated April 10, 2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISIONS TECIINCIAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision(REV) No.ORIGINAL123455*6789Date ofIssue10/19/933/17/942/1/968/7/008/18/002/12/015/1/089/22/088/20/103/10/147/24/2015 LicenseAmendment No.Remarks12345Correction toAmendment 56789License IssuedCorrection 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 authority Reformatted and Inclusion ofTN-40HTdesign Revised absorber and aluminum plateminimum allowed thermalconductance
- Revise.
surveillance requirements inTS 3.1.2RoR-17/24/2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATION TECHNCIAL SPECIFICATION CURRENT PAGE LISTLICENSE SNM-2506PAGE AMENDMENT NRC Findings
&issuance (1st page)NRC Findings
&issuance (2n page) 91 92 93 94 9Appendix A -Record of Revision[ PAGE DateRoR- 1 7/24/2015 Page ListPAGE DateA 7/24/2015 B 7/24/2015 Appendix A -Table of ContentsSi T- 8/20/10Appendix A -Technical Specifications PAGE 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 Specifications PAGE 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 73.114-1 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 TECHNCIAL 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 COMPLETION TIMEB. Required Action A. 1 and B.1 Return cask to pool and 7 daysassociated Completion reflood.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 -----------------
NOTE ----------------
Not required to be met prior to the specified Frequency.
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 specified Frequency.
Verify that the cask cavity pressure is < 14 mbar Once prior toabsolute.
pressurization (SR 3.1.2.3)Prairie Island ISFSITechnical Specifications Amendment 93.1.2-2I Cask Helium Backfill Pressure3.1.2SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.2.3 -----------------
NOTE ----------------
Not required to be met prior to the specified Frequency.
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 Specifications Amendment 93.1.2-3 PRAIRIE ISLAND NUCLEAR GENERATING PLANTINDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISION BASES CHANGES AND LICENSE AMENDMENTS NSPM Date of LicenseRevision Issue Amendment No. Remarks(REV) No.1 fkrcmalh A (r; rncal rxr ci Ttxrr1,t 788/20/2010 12/12/2012 7Specifications Initial 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 3.1.2.9108/27/137/24/2015 9Prairie IslandISFSIB RoR- I7/24/2015 BASES CURRENT PAGESPAGE DATEB RoR-1 7/24/2015 A 7/24/2015 i 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 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 3.1.2.1REQLUREMENS This 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 satisfied provided 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 10 Cask Helium Backfill PressureB 3.1.2SURVEILLANCE REQUIREMENTS (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, maintaining pressure 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 performed successfully on each cask prior to performance of leak testingactivities and TRANSPORT and STORAGE OPERATIONS.
REFERENCES