ML15209A509

Technical Specifications - Updating Instructions

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

11PCX02 PASSPORT DOCUMENT To NMSS PROJECT MGR COPY #846 Facility PI Department TRANSMITTAL (1111 Address 2 WHITE FLINT NORTH 11545 ROCKVILLE PIKE From Address ROCKVILLE, MD 20852-2738 C-DOC CNTRL-PI 1717 WAKONADE DR EAST Attention:

Page:

inl l [i nuf~ll~lll[llll il City WELCH State: MN Postal Code: 55089 Country UNITED STATES Email Contact Date/Time 07/17/2015 10:16 Transmittal Group Id: 0000031107 Trans No. 000283853

Title:

Total Items: 00002 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy # Media Cpys 0001 PI LIC BASE ISFSI BASES ISSUED 010 846 HC 01 0002 PI LIC TECH ISFSI TECH SPECS ISSUED 009 846 HC 01 If 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 ISLAND Technical Specifications UPDATING INSTRUCTIONS Effective Date: 7/24/2015 PINGP

• ISFSI REMOVE INSERT Page Revision Doc Type Page Revision Amendment/

All (6 pgs) 8 License All (6 pgs) 9 pages RoR-l 5/14/14 Record of RoR-l 7/24/2015 5/14/14Revisions A, B 6/25/14 Current page list A, B 7/24/2015 Bases B RoR-l 8/27/13 Record of B RoR-l 7/24/2015 Revisions Bases A 8/27/13 Current A 7/24/2015 Pages REMOVE INSERT Page Revision Sect/Chap Page Revision 3.1.2-2 7 3.1.2 3.1.2-2 9 n/a 3.1.2-3 9 B 3.1.2-.4 8 3.1.2 3.1.2-4 10 B 3.1.2-5 7 3.1.2 3.1.2-5 10

NORTHERN STATES POWER COMPANY, A MINNESOTA CORPORATION (NSPM)

DOCKET NO. 72-10 PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATION AMENDMENT TO MATERIALS LICENSE NO. SNM-2506 Amendment No. 9 License No. SNM-2506 The Nuclear Regulatory Commission (the Commission) has found that:

A. The amendment application dated May 23, 2014, as supplemented by the letter on November 19, 2014, complies with the standards and requirements of the Atomic 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 to operate 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 this amendment 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 and security or to public health and safety; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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

/RAI Michele Sampson, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards

Enclosure:

Amended License Date of Issuance: April 10, 2015

NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION 10 CFR 72 PAGE 1 OF 4 PAGES LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of FederalRegulations,Chapter 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic 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.

Licensee Northern States Power Company, a 3. License No. SNM-2506 Minnesota corporation (NSPM) 1 oncl'erf No.* 9

2. 414 Nicollet Mall " .. .. 9 Minneapolis, Minnesota, 55401-1927 4. Expiration Date October 31, 2013

5. Docket or 72 "10 Reference No. 72-1

6. Byproduct, Source, and/Qr 7. Chemical or Physical Form ...... 8. Maximum Amount That Licensee Special Nuclear Material May:Possess at Any One Time "UnderthisLicense Spent fuel assemblies from A. As U0 2 clad with zirconium. A. 715.29 TeU of spent fuel Prairie Island Nuclear Station '

• al.oys.

Jzirconiu ,, assemblies Units 1 and 2 reactors, using natural water for cooling and enriched 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 inserts B 8S'304,structure,l lcbnel B. One BPRA or TPD per spent fuel from the Prairie Island Nuclear 718 spring, and borated assembly.

Station Units 1 and 2 reactors. pyrex glass.

An insert may be a burnable poison rod assembly (BPRA) or a thimble plug device (TPD).

Northern States Power Company was incorporated in Minnesota as a wholly owned subsidiary of Xcel

. Energy 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 order dated May 12, 2000.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGES (102000) License No. SNM-2506 Amendment No.99I LI CENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET

9. 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 Analysis dated 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, and November 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 in accordance 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 at the 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, guard training and q . nlicoriingency plans previously approved, by the Commission and all amendmeis made pursuant*o*othe authority--of 1&CFR*72.56, 72.44(e), and 72.186. The plans, which contain safeguards information, protected brider 10 FR,73.21, are entitied: "Prairie Island Nuclear Generating. Plant IndependenSp,*n*F** e Stoag Ienstallation Physic"LSecurity Plan,"

Revision 0, submitted by letter*dated March 10, 1992-; "Pairie Island Nuclear. G,enerating Plant Independent SpentIndependent,'

Fuel Storage....

Spent ..........SecurityIF~orce Training': and ng Installation QualificationPlantPlan,","d pRevision nd n 0, submitted by letter,,-,,ted March, 10.0 1992-; andi"Prdai]rieIslad NuclearGeneihg Plant Independent

• Spent Fuel Storage. nIstallation Safeguards qCnti'gendcyPlan,', Revision 0,, ubmitted by letter dated March 10, 1992.

14. The Technical Specifications,?for Environmental-Protection contained n-ppendix A attached hereto are incorporated into the license. .-

Specifications required pursuant to 1 0i*CFR.72.,44'(d),,sfatin*"'imits 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 within the limits of Technical Specification 3.2.1 ensures that the offsite dose will be inconsequential. In addition, 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 of effluents, and for the maintenance and use of equipment in radioactive waste treatment systems, to meet the requirements of 10 CFR 72.104 are not applicable. There are, by the design of the sealed Swaste storage casks at the ISFSI, no effluent releases. Also, cask loading and unloading operations and treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of its operating licenses.

10 CFR 72 License No. SNM-2506 Amendment No. 9 OF SPENT NUCLEAR LICENSE FOR INDEPENDENT STORAGE FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 IL SUPPLEMENTARY SHEET

15. 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 shall be 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 area

b. 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 building

f. Unloading tlhi_ cask

g. 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 each activity can be successfullyexcu. bibefore actual fuel loading.

B The Praire Island Nuclear Generating Plant Ebmergency Planshall bereviewed and modified, as required, to include the ISFSI .

C A training module shall be develoiped forthe Prairie Island Nuclear Generating Plant Training Program, 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 reviewed and modified, as required, to include the ISFSI.

E The Prairie Island Nuclear Generating Plant Administrative Procedures shall be reviewed and modified, as required, to include the ISFSI.

U NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES 10CFR72 License No. SNM-2506 Amendment No. 9 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR ,__

FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET F 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 include independent verification of fuel assembly selection by an individual other than the original individual making the selection.

G A procedure shall be developed and implemented for two independent determinations (two samples analyzed by different individuals) of the boron concentration in the water used to fill the cask 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 Federal Regulations. All commitments to the aIp"icable NRC regulatory guides and to engineering and construction codes shall be carried out.

17. Fuel and cask movemerit-and handling activities that are to be performerd in the Prairie Island Nuclear Generating Plant Auxiliary Building will be governed by the requirements"ofthe Prairie Island Nuclear Generating Plant Facilit Operating Licenses (DRP-42 and -60) and associ ated Technical Specifications.

8. The TN-40HT confinement boundary base materialand associated welds sh al -e helium leak tested at the fabricator in accordance with ANJ Ni 4.5 o "leaktight",citeria. The TN-40-pnfinement boundary base material and associated weids'h*hall be helium leak tested at the fabricator inaccordance with ANSI 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 iRAI.

IR/

Michele Sampson, Chief Spent Fuel Licensing Branch Divisionp.bf.Sbent Fuel Management Office of'Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: October 19, 1993 As amended by Amendment No. 9 dated April 10, 2015

PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISIONS TECIINCIAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision Date of License (REV) No. Issue Amendment No. Remarks ORIGINAL 10/19/93 License Issued 1 3/17/94 1 Correction to Page 1 of License 2 2/1/96 2 Change to p. 6-1 3 8/7/00 3 Change to p. 6-1 4 8/18/00 4 License reissue only 5 2/12/01 5 Change to Sec. 3/4 5* 5/1/08 Correction to Correction to page 1 of License, per Amendment 5 NRC letter dated February 7, 2008 6 9/22/08 6 Transfer of operating authority 7 8/20/10 7 Reformatted and Inclusion of TN-40HTdesign 8 3/10/14 8 Revised absorber and aluminum plate minimum allowed thermal conductance 9 7/24/2015 9 *Revise.surveillance requirements in TS 3.1.2 RoR-1 7/24/2015

PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION TECHNCIAL SPECIFICATION CURRENT PAGE LIST LICENSE SNM-2506 Appendix A - Technical Specifications PAGE AMENDMENT PAGE REVISION No.

NRC Findings & 1.4-2 7 issuance ( 1st page) 1.4-3 7 NRC Findings & 1.4-4 7 issuance (2n page) 9 1.4-5 7 1 9 1.4-6 7 2 9 2.0-1 7 3 9 2.0-2 7 4 9 2.0-3 7 3.0-1 7 Appendix A - Record of Revision 3.0-2 7

[ PAGE Date 3.0-3 7 RoR- 1 7/24/2015 3.0-4 7 3.0-5 7 Page List 3.1.1-1 7 PAGE Date 3.1.1-2 7 A 7/24/2015 3.1.2-1 7 B 7/24/2015 3.1.2-2 9 3.1.2-3 9 Appendix A - Table of Contents 3.1.3-1 7 Si T- 8/20/10 3.1.3-2 7 3.114-1 7 Appendix A - Technical Specifications 3.1.4-2 7 PAGE REVISION No. 3.1.5-1 7 1.1-1 7 3.1.5-2 7 1.1-2 7 3.1.6-1 7 1.1-3 7 3.1.6-2 7 1.2-1 7 3.2.1-1 7 1.2-2 7 3.2.1-2 7 1.2-3 7 3.2.2-1 7 1.3-1 7. 3.2.2-2 7 1.3-2 7 3.3.1-1 7 1.3-3 7 3.3.1-2 7 1.3-4 7 3.4.1-1 7 1.3-5 7 3.4.1-2 7 1.4-1 7 4.0-1 7 A 7/24/2015

TECHNCIAL SPECIFICATION CURRENT PAGE LIST (CONTINUED)

PAGE REVISION No.

4.0-2 7 4.0-3 7 4.0-4 7 4.0-5 8*

4.0-6 7 4.0-7 7 4.0-8 7 4.0-9 7 4.0-10 7 4.0-11 7 4.0-12 7 4.0-13 8 4.0-14 7 4.0-15 7 4.0-16 7 4.0-17 7 5,0-1 7 5.0-2 7

• Re-issued 6/3/14 to add sidebars B 7/24/2015

Cask Helium Backfill Pressure 3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action A. 1 and B.1 Return cask to pool and 7 days associated 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 34 established in the cask cavity, hours after commencing cask draining SR 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 to absolute. pressurization (SR 3.1.2.3)

Prairie Island ISFSI Amendment 9 Technical Specifications 3.1.2-2 I

Cask Helium Backfill Pressure 3.1.2 SURVEILLANCE 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 ISFSI Amendment 9 Technical Specifications 3.1.2-3

PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISION BASES CHANGES AND LICENSE AMENDMENTS NSPM Date of License Revision Issue Amendment No. Remarks (REV) No.

1 fkrcmalh A (r; rncal "a*c-a rxr r*," ci Ttxrr1,t *l Specifications 7 8/20/2010 7 Initial Issue of revised format and Inclusion of TN-40HT design.

8 12/12/2012 Clarify "helium environment" requirement in ISFSI SR 3.1.2.1.

9 8/27/13 Revise B 3.1.5 paraphrase of regulatory requirements.

10 7/24/2015 9 Revise SR for B 3.1.2.

Prairie Island ISFSI B RoR- I 7/24/2015

BASES CURRENT PAGES PAGE DATE PAGE REVISION No.

B RoR-1 7/24/2015 B 3.1.3-1 7 A 7/24/2015 B 3.1.3-2 7 i 8/20/10 B 3.1.3-3 7 B 3.1.3-4 7 B 3.1.4-1 7 B 3.1.4-2 7 B 3.1.4-3 7 B 3.1.5-1 9 PAGE REVISION No.

B 3.1.5-2 7 B 2.0-1 7 B 3.1.5-3 7 B 2.0-2 7 B 3.1.5-4 7 B 3.0-1 7 B 3.1.5-5 7 B 3.0-2 7 B 3.1.6-1 7 B 3.0-3 7 B 3.1.6-2 7 B 3.0-4 7 B 3.1.6-3 7 B 3.0-5 7 B 3.2.1-1 7 B 3.0-6 7 B 3.2.1-2 7 B 3.0-7 7 B 3.2.1-3 7 B 3.0-8 7 B 3.2.2-1 7 B 3.0-9 7 B.3.2.2-2 7 B 3.0-10 7 B 3.2.2 7 B 3.0-11 7 B 3.3.1-1 7 B 3.1.1-1 7 B 3.3.1-2 7 B 3.1.1-2 7 B 3.3.1-3 7 B 3.1.1-3 7 B 3.3.1-4 7 B 3.1.2-1 7 B 3.4.1-1 7 B 3.1.2-2 7 B 3.4.1-2 7 B 3.1.2-3 7 B 3.4.1-3 7 B 3.1.2-4 10 B 3.1.2-5 10 Prairie Island ISFSI A 7/24/2015

Cask Helium Backfill Pressure B 3.1.2 BASES ACTIONS 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 spent fuel pool within 7 days and re-flooded. This time is sufficient time to 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 adequate decay heat removal to maintain the loaded fuel within limits.

SURVEILLANCE SR 3.1.2.1 REQLUREMENS This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure 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 not dependant upon pressure, it is dependant upon the make-up of the gases within the cask cavity. Thermal analyses have shown that maximum fuel cladding temperature limit of 752°F is not exceeded during LOADING OPERATIONS provided a 75% helium environment (based on partial pressure) is established within the cask. Thus, design basis heat removal requirements will be satisfied provided an environment of at least 75% helium has been established, and maintained in the cask cavity within the 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> vacuum drying time frame (Reference 3).

SR 3.1.2.2 This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure to meet the LCO per SR 3.0.1, and SR 3.0.4 does not apply prior to the specified Frequency.

Evacuating the cask cavity to the specified vacuum prior to pressurization (see SR 3.1.2.3) will ensure that the amount of oxidizing gases remaining in the cavity will be no greater than Prairie Island ISFSI B 3.1.2-4 Revision 10

Cask Helium Backfill Pressure B 3.1.2 SURVEILLANCE 0.25% (volume). Below this concentration, degradation of REQUIREMENTS stored cladding and fuel materials is not expected.

(continued)

SR 3.1.2.3 This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure 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 in a dry, inert environment and maintenance of adequate heat transfer mechanisms. Filling the cask cavity with helium at the initial pressure, following the evacuation in SR 3.1.2.2, will ensure that the amount of oxidizing gases remaining in the cavity will be no greater than 0.25% (volume). At this concentration, degradation of stored cladding and fuel materials is not expected. Also, maintaining pressure below the upper limiting value will ensure that cask cavity internal 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 testing activities and TRANSPORT and STORAGE OPERATIONS.

REFERENCES 1. SAR Section 8.2.

2. SAR. Section A8.2.

3. SAR Section A3.3.

Prairie Island ISFSI B 3.1.2-5 Revision 10