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MONTHYEARL-HU-08-005, Application for Order and Conforming License Amendments to Transfer Operating Authority Under Facility Operating Licenses2008-04-16016 April 2008 Application for Order and Conforming License Amendments to Transfer Operating Authority Under Facility Operating Licenses Project stage: Request L-HU-08-016, Corrected Operating License Pages Regarding Transfer of Operating Authority2008-08-0606 August 2008 Corrected Operating License Pages Regarding Transfer of Operating Authority Project stage: Request ML0822407612008-09-15015 September 2008 Order Approving Transfer of Licensed Operating Authority and Conforming Amendment Project stage: Other ML0825211822008-09-15015 September 2008 Order Approving Transfer of Operating Authority from NMC to NSPM Project stage: Other ML0822407502008-09-15015 September 2008 Safety Evaluation Associated with the Order and Conforming Amendments Authorizing Transfer of Operating Authority Project stage: Approval L-HU-08-021, ISFSI and Monticello, Confirmation of Transition Readiness as of September 22, 20082008-09-19019 September 2008 ISFSI and Monticello, Confirmation of Transition Readiness as of September 22, 2008 Project stage: Other ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) Project stage: Approval ML0826812912008-09-22022 September 2008 Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623) Project stage: Approval ML0826007722008-09-22022 September 2008 Operating Licenses Revised to Reflect Transfer of Operating Authority to NSPM Project stage: Other ML0825906762008-09-22022 September 2008 Letter to Transmit Conforming Amendments Number 188, 177, and 06 Re. License Transfer Project stage: Other ML0825906382008-09-22022 September 2008 Conforming Amendments to Facility Operating Licenses and Material License for the ISFSI to Reflect Transfer of Operating Authority to NSPM Project stage: Other ML0828105432008-10-17017 October 2008 Correction of Error in Amendment No. 6 of Material License SNM-2506 for the Independent Spent Fuel Storage Facility Regarding the Transfer of Operating Authority (Tac Nos. L24245, MD9622, and MD9623) Project stage: Other 2008-08-06
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Category:License-Dry Cask
MONTHYEARML24241A1702024-09-23023 September 2024 Enclosure 1 - Prairie Island Independent Spent Fuel Storage Installation Materials License No. Special Nuclear Material-2506 Amendment No. 13 ML24008A1302024-03-0505 March 2024 Enclosure 1 - Prairie Island ISFSI - Amendment 12 ML20237F3672020-10-29029 October 2020 Amendment No. 11 to Materials License No. SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation ML18057A2862018-03-0606 March 2018 Enclosure 1: Renewed Materials License (Amendment No. 10 to Renewed Materials License No. SNM-2506 for the Prairie Island Site Specific Independent Spent Fuel Storage Installation) ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0825906382008-09-22022 September 2008 Conforming Amendments to Facility Operating Licenses and Material License for the ISFSI to Reflect Transfer of Operating Authority to NSPM 2024-09-23
[Table view] Category:ISFSI
MONTHYEARML24241A1702024-09-23023 September 2024 Enclosure 1 - Prairie Island Independent Spent Fuel Storage Installation Materials License No. Special Nuclear Material-2506 Amendment No. 13 ML24008A1302024-03-0505 March 2024 Enclosure 1 - Prairie Island ISFSI - Amendment 12 ML20237F3672020-10-29029 October 2020 Amendment No. 11 to Materials License No. SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation ML18057A2862018-03-0606 March 2018 Enclosure 1: Renewed Materials License (Amendment No. 10 to Renewed Materials License No. SNM-2506 for the Prairie Island Site Specific Independent Spent Fuel Storage Installation) ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0825906382008-09-22022 September 2008 Conforming Amendments to Facility Operating Licenses and Material License for the ISFSI to Reflect Transfer of Operating Authority to NSPM 2024-09-23
[Table view] Category:(Amend) DKT 72
MONTHYEARML24241A1702024-09-23023 September 2024 Enclosure 1 - Prairie Island Independent Spent Fuel Storage Installation Materials License No. Special Nuclear Material-2506 Amendment No. 13 ML24008A1302024-03-0505 March 2024 Enclosure 1 - Prairie Island ISFSI - Amendment 12 ML20237F3672020-10-29029 October 2020 Amendment No. 11 to Materials License No. SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation ML18057A2862018-03-0606 March 2018 Enclosure 1: Renewed Materials License (Amendment No. 10 to Renewed Materials License No. SNM-2506 for the Prairie Island Site Specific Independent Spent Fuel Storage Installation) ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0825906382008-09-22022 September 2008 Conforming Amendments to Facility Operating Licenses and Material License for the ISFSI to Reflect Transfer of Operating Authority to NSPM 2024-09-23
[Table view] Category:Technical Specifications
MONTHYEARML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24008A1292024-03-0505 March 2024 Enclosure 2 - PI ISFSI Amendment 12 Section 4.0 Design Features Technical Specifications ML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 ML20346A0202021-03-15015 March 2021 Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20356A0022021-02-0505 February 2021 Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1 ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency ML19045A4802019-04-16016 April 2019 Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19029A0942019-01-29029 January 2019 Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances) ML17362A2022018-03-0505 March 2018 Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175) ML16133A4062016-06-16016 June 2016 Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450) ML15264A2092015-11-30030 November 2015 Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License ML15229A1762015-08-26026 August 2015 Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML15209A5092015-07-17017 July 2015 Technical Specifications - Updating Instructions L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15086A0462015-05-21021 May 2015 Issuance of Amendment Nos. 214 and 202 Regarding Revisions to Technical Specification 3.8.1, AC Sources - Operating ML15062A0132015-05-20020 May 2015 Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation2014-12-11011 December 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation ML14058A2072014-02-19019 February 2014 Technical Specifications (3801 TS Markup) ML13214A0292013-08-0202 August 2013 Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2) ML13113A4002013-07-0202 July 2013 License Amendments TSTF-510 L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).2013-05-23023 May 2013 License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr). ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits2012-05-15015 May 2012 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology ML1129011152011-12-0101 December 2011 Issuance of Amendments Revision of Technical Specifications 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications. L-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011 License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil ML11172A0222011-06-27027 June 2011 Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant ML11172A0202011-06-27027 June 2011 Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant L-PI-11-016, License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-02-0303 February 2011 License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating. L-PI-10-104, Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-20020 October 2010 Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 ML1025715492010-09-16016 September 2010 Correction to Amendment Nos. 195 and 184 Regarding Technical Specification Changes to Control Room Habitability Requirements ML0925703672009-09-15015 September 2009 Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) L-PI-08-080, License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.92008-11-0404 November 2008 License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9 ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0826812912008-09-22022 September 2008 Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623) ML0820504452008-07-18018 July 2008 Tech Spec Pages for Amendments 186 & 176 Adopting Provisions of Regulatory Guide (Rg) 1.52 Revision 3 ML0818402342008-06-27027 June 2008 Prairie, Units 1 and 2, Tech Spec Pages for Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497 ML0812705062008-05-0101 May 2008 Submittal of Entire Re-Issue of ISFSI Technical Specifications ML0801404252008-01-28028 January 2008 Issuance of Amendments (TAC Nos. MD4209 & MD4210) - Tech Specs ML0735204002007-12-14014 December 2007 Technical Specifications in Support of Containment Sump Resolution L-PI-07-086, License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)2007-11-19019 November 2007 License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR) 2024-05-01
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NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 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 Federal Regulations, Chapter 1, Part 72, and, in reliance on statements and representationsheretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fueland 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
- 1. Northern States Power Company, a 3. License No. SNM-2506 Minnesota corporation (NSPM) 1 Amendment No. 6
- 2. 414 Nicollet Maill Q Minneapolis, Minnesota, 55401-1927,",*ý .6 .
- 4. :Expiration Date 4"'Otober 31,2013
,.-,. 5. N Docket or -No.
.~Reference 72"-10 721"
- 6. Byproduct, Source, and/or'20 7".'.-emical or Physical Ma.xlm1um Amount That M8.
Special Nuclear Material-j'f "GA -Licensee May-. ssess at Any One
~ Und~ffhs License A. Spent fuel:assemblies from 2.U a it 'Ap115.294-bU of spent fuel Prairie Island Nuclear Station"* "-lreo. u .z assemnlies Units 1 and 2 reactors, using.
natural water for cooling and ,
enriched not greater than 3.85V percent U-235, and associated radioactive materials related to receipt, storage and transfer of the fuel assemblies.
B. Irradiated fuel assembly inserts B SS 304 structure, Inconel B. One BPRA or TPD per'spent fuel from the Prairie Island Nuclear 718 spring, and borated -assembly.
Station Units 1 and 2 reactor. 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 -ýOF .4 PAGES (10-2000) License No. SNM-2506 Amendment No. 6 10 CFR 72 LICENSE 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 statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report 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, 1 991; 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 and October 16, 2000; February 12, 2001; April 16 and August 8, 2008.
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 Prairie Island Nuclear Generating Plant site in .Goodhue County, Minnesota.
- 11. This site is described in Chapter 2 of the Technical Specifications. and Safety Analysis Report (TS/SAR) for the Prairie -Island ISFSI.
- 12. The Technical Specifications containe dain Appendix A attached hereto are incorporated into the license.
- 1. NSPM NSPM shall fullyt the~
shall operate the installd'irh in accordance with the Tech i/a-Specifications pyia-inscrty Appendix urA.
- 13. NSPM shall fully implemeýNtand maintain in effect all provisions of th ISFSI physical security, guard training and qualification, and-safeguards contingency plans previously aoproved by the Commission andwhihallc~ntin amendments maeinforýSl!M*.ndr1 safeguaMIS pursuant the authority of 10 CCF -plans, 1
which contain safe inf -* petected under 10 CF 1, are entitled: "Prairie Island Nuclear Generating Plant lndependirntVSpent EubfuSterage Qtation -j Physical Security'Plan,"
'Revision 0, submittedIby letter dat&A__ach 10,
- Independent Spent -Fuel Storage Instdiation Seburityvc*.Frer 1 ,992,; PA I-ai~if*ind Nuclear,?G-enerating Plant submitted by letter d&ait-d Marclf* 1h I S- Idee Spet F`u g ain,ing and
."**.*rl
ýe_ Qualification Plan," Revision 0, su e bd ePrairie .sla clea" Generating Plant Independent Spent, Fuel Storage InsItallatiei Sg s Re*isi*n 0, moIrnitted by letter dated March 10, 1992. ' "
The Technical nM I contained in Appendix A attached *hereto are incorporated into the license Specifications required pursuaNt to 10 CFR 72.44(d), stating limits on the release of radioactive materials for compliance with~ii6Ats of 10 CFR Part 20 and ".as low~s is reasonably achievable objective" for effluents
... . *.*'X1-* TN-40 are not applicable. A cask A. &, external
,_-* . suf ace contamination
.. within
- the limits of Technical Specification 3.4.1 ensures tlhatIee offsite dose willbe inconsequential. In addition, there are no normal or off-normal releases or effluenfrexpected 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 storage casks at the ISFSI, no effluent releases. Also, cask loading and unloading operations and waste treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of its operating licenses.
- 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 TN-40 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:
- NRC FORM 588A . U. S. NUCLEAR REGULATORY COMMISSION . PAGE, 3 OF 4 PAGES (10-2000) License No: SNM-2506 Amendment No. 6 10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET
- 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 storage pad
- e. Returning the cask to the auxiliary building
- f. Unloading the cask
- g. Decontaminating the cask
- h. All dry-run activities'ghall`b done usingwritt~enhprocedures i The activitie above shall be performed or mdifi*ed aind performed to show that each ,activity can be successfully executed beforeactu*al fuel loading.
The Prairie Island-Nuc0iar-Generating Plant Emergency Pan:ha*
reviewed and modified,
-as required, to lude the-,lS*.SI C A training movie shall be, pped for rair NuclearG 'enerating Plant Training
- Program, estdiblishing an lf&E*SITraining'and Certificatori -rogram thijill include the following
a.
- b. -ISFSrac
- c. ISFSI SafE
- d. Fuel loadir
- e. ISFSI License (ovei 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.
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.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION. PAGE 4 OF 4 PAGES (I0-200o) License No. SNM-2506 Amendment No. 6 OF SPENT NUCLEAR LICENSE FOR INDEPENDENT STORAGE FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10
._ SUPPLEMENTARY SHEET H Written procedures shall be implemented to describe actions to be taken during operation, off-normal, and emergency conditions.
1 6. The design, construction, and operation of the ISFSI shall be accomplished in accordance with the U.S.
Nuclear Regulatory Commission Regulations specified in Title 10 of the U.S. Code of Federal Regqulations. All commitments to the applicable NRC regulatory guides and to engineering and construction codes shall be carried out.
- 17. Fuel and cask movement and handling activities that are to be performed in the Prairie Island Nuclear Generating Plant Auxiliary Building will be governed by the requirements of the Prairie Island Nuclear Generating Plant Facility Operating Licenses (DRP-42 and -60) and associated Technical Specifications.
- 18. This license is effective as of the date of issuance shown below.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Eriic J. enner, Chief Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: October 19, 1993 As amended by Amendment 6 dated September 22, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 6 TO MATERIALS LICENSE NO. SNM-2506 DOCKET NO. 72-10 Replace the following page of Appendix A, "Technical Specifications," with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 6-1 6-1
6.0 ADMINISTRATIVE CONTROLS 6.1 GENERAL The Prairie Island ISFSI is located on the Prairie Island Nuclear Generating Plant site and will be managed and operated by Northern States Power Company, ' Minnesota corporation (NSPM) staff. The administrative controls shall be in accordance with the requirements of the Prairie Island Nuclear Generating Plant Facility Operating'Licenses (DPR-42 and -60) and associated Technical Specifications, as appropriate.
6.2 ENVIRONMENTAL MONITORING PROGRAM The licensee shall include the Prairie Island ISFSI in the environmental monitoring program for the Prairie Island Nuclear Generating Plant.. An environmental monitoring program is required pursuant to 10 CFR 72.44(d)(2). The licensee shall include the ISFSI in the environmental monitoring report for the Prairie Island Nuclear Generating Plant, and a copy shall be sent to the Director, Office of Nuclear Material Safety and Safeguards.
6.3 ANNUAL ENVIRONMENTAL REPORT An annual report, as required by 10 CFR 72.44(d)(3), shall be submitted to the NRC Region Ill, Office, with a copy to the Director, Office of Nuclear Material Safety and Safeguards, within 60 days after January 1 of each year. This report should specify the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous year of operation and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent release.
6-1 Amendment 4 dated September 22, 2008