Letter Sequence Other |
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TAC:MB0695, Ventilation System Envelope Allowed Outage Time (Approved, Closed) TAC:MB0696, Ventilation System Envelope Allowed Outage Time (Approved, Closed) |
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MONTHYEARML0135504172002-01-0808 January 2002 Request for Additional Information, Application for Conversion to Improved Technical Specifications, Section 3.7 Project stage: RAI ML0215400082002-06-0303 June 2002 Draft Safety Evaluation Conversion to Improved Technical Specifications Project stage: Draft Approval ML0215403012002-06-0303 June 2002 Draft of Safety Evaluation Project stage: Draft Approval ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs Project stage: Other ML0222100432002-07-26026 July 2002 Technical Specifications for License Amendment Nos. 158 and 149, Pages 1.1-1 to 3.4.13-1 (174 Pages) Project stage: Acceptance Review ML0220706582002-07-26026 July 2002 Individual Notice of Issuance, License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications Project stage: Other ML0221403592002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B2.1.1-1 to B3.3.1-66 200 Pages) Project stage: Acceptance Review ML0221403702002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B.3.3.2-1 to B3.4.13-13 (185 Pages) Project stage: Acceptance Review ML0221403942002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.4.14-1 to B3.7.7-7 (186 Pages) Project stage: Other ML0221404122002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.7.8-1 to B3.9.6-4 (194 Pages) Project stage: Acceptance Review ML0222100542002-07-26026 July 2002 Technical Specifications for License Amendment Nos. 158 and 149, Pages 3.4.13-1 to 5.0-4.5 (215 Pages) Project stage: Acceptance Review ML0230400542002-07-26026 July 2002 Attachment 2 to Safety Evaluation of Amendment No. 149 - Table a - Administrative Controls Project stage: Approval ML0230401182002-07-26026 July 2002 Attachment 4 to Safety Evaluation of Amendment No. 149 - Table L - Less Restrictive Changes Project stage: Approval ML0230401212002-07-26026 July 2002 Attachment 3 to Safety Evaluation of Amendment No. 149 - Table M - More Restrictive Changes Project stage: Approval ML0230401282002-07-26026 July 2002 Attachment 5 to Safety Evaluation of Amendment of 149 - Table Lr - Less Restrictive - Relocated Details Project stage: Approval ML0230401442002-07-26026 July 2002 Attachment 6 to Safety Evaluation of Amendment No. 149 - Table R - Relocated Specifications Project stage: Approval ML0230401512002-07-26026 July 2002 Attachment 7 to Safety Evaluation of Amendment No. 149 - Table U - Unused Numbers Project stage: Approval ML0220706542002-07-26026 July 2002 License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Safety Evaluation) Project stage: Approval ML0220706132002-07-26026 July 2002 License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Cover Letter, Amendment, License Pages) Project stage: Other 2002-06-03
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Category:Environmental Assessment
MONTHYEARML20275A3422020-10-0101 October 2020 Environmental Assessment for the Proposed Amendment of the U.S. Nuclear Regulatory Commission License Number SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation in Goodhue County, Minnesota ML20265A1042020-09-30030 September 2020 Environmental Assessment for the Proposed Amendment of the U.S. Nuclear Regulatory Commission License Number SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation in Goodhue County, Minnesota ML13205A1202013-11-0707 November 2013 Draft Environmental Assessment for the Proposed Renewal of the Prairie Island Independent Spent Fuel Storage Installation ML1017202402010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML1017201962010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact NRC-2010-0324, Environmental Assessment and Finding of No Significant Impact2010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML0932900262010-02-0202 February 2010 Environmental Assessment ML0932900222010-02-0202 February 2010 Letter - Environmental Assessment and Finding of No Significant Impact (Tac Nos. ME2529 and ME2540) ML0611100952006-05-11011 May 2006 Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs 2020-09-30
[Table view] Category:Federal Register Notice
MONTHYEARML23235A0762023-09-0101 September 2023 FRN: Docketing- Prairie Island ISFSI Amendment Request 12 ML21280A3852021-10-15015 October 2021 FRN -Prairie Island Nuclear Generating Plant, Units 1 and 2 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity Fo ML21280A3842021-10-15015 October 2021 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML20335A0902020-12-21021 December 2020 Federal Register Notice - November 2020 COVID-19 Exemptions ML20247J3972020-10-30030 October 2020 Federal Register - Notice of Issuance of License Amendment Application ML20035C4082020-02-18018 February 2020 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020 ML19168A0842019-06-26026 June 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019 ML19162A1632019-06-21021 June 2019 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations NRC-2019-0065, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/20192019-02-28028 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/2019 ML19056A5352019-02-28028 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/2019 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 ML18173A1792018-08-0707 August 2018 OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C NRC-2018-0096, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 20182018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 ML18127B7232018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 ML18068A1792018-04-0404 April 2018 Federal Register Notice: 72-10 Renewed License Amendment 10 ML17200A0652017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement FRN, Paul Gunter, Beyond Nuclear, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and ML17198A3292017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement Letter, Paul Gunter, Beyond Nuclear, Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Jap ML15239A6882015-09-17017 September 2015 Withdrawal of an Amendment Request ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 ML14266A1912014-08-11011 August 2014 Draft FRN - Issuance of Environmental Assessment and Finding of No Significant Impact (Prairie Island ISFSI Exemption) ML14189A6652014-07-24024 July 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information - August 5, 2014 ML14100A3112014-04-0909 April 2014 Frn/Draft - Issuance of Environmental Assessment and Finding of No Significant Impact - PI-PSP Exemption NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 20142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML14037A4142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML11349A0052011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 20112011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 ML11237A0072011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 NRC-2011-0205, FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/112011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 NRC-2009-0507, Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision2011-06-27027 June 2011 Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision ML11147A1232011-06-27027 June 2011 Issuance of Renewed Facility Operating Licenses for Prairie Island Nuclear Generating Plant ML11147A1402011-06-27027 June 2011 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision ML1107400442011-05-17017 May 2011 Notice of Availability of the Final Plant-Specific Supplement 39 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2 ML1105303992011-02-23023 February 2011 FRN: General Notice: Prairie Island Nuclear Generating Plant, Unit 1 - Correction to Notice of Consideration of Issuance of Amendments to Facility Operating Licenses Involving No Significant Hazards Consideration; Correction ML1104103732011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 NRC-2011-0040, Sholly Report for Fr Publication on February 22, 20112011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 ML1024302392010-11-22022 November 2010 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50, to Allow Use of Optimized Zirlo as Fuel Rod Cladding Material ML1026407762010-10-0101 October 2010 Withdrawal of an Amendment Request ML1026407802010-10-0101 October 2010 United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License NRC-2010-0325, United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License2010-10-0101 October 2010 United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License ML1017201962010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact NRC-2010-0324, Environmental Assessment and Finding of No Significant Impact2010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML1016500342010-07-20020 July 2010 G20090510/EDATS: OEDO-2009-0541 - Federal Register Notice of Issuance of Director'S Decision Under 10 CFR 2.206 ML0934105312010-02-23023 February 2010 Cover Letter - Exemption from the Requirements of 10 CFR Part 73 Section 73.55 NRC-2010-0046, Exemption2010-02-23023 February 2010 Exemption 2023-09-01
[Table view] Category:Finding of No Significant Impact
MONTHYEARML21055A5982021-03-25025 March 2021 Final Environmental Assessment and Finding of No Significant Impact for the Northern States Power Company'S Initial and Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(B) and (C) ML1105303992011-02-23023 February 2011 FRN: General Notice: Prairie Island Nuclear Generating Plant, Unit 1 - Correction to Notice of Consideration of Issuance of Amendments to Facility Operating Licenses Involving No Significant Hazards Consideration; Correction ML1017202402010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML0932900262010-02-0202 February 2010 Environmental Assessment ML0932900222010-02-0202 February 2010 Letter - Environmental Assessment and Finding of No Significant Impact (Tac Nos. ME2529 and ME2540) ML0611100952006-05-11011 May 2006 Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs 2021-03-25
[Table view] Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] |
Text
July 15, 2002 Mr. Mano Nazar Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR THE PROPOSED CONVERSION TO THE IMPROVED TECHNICAL SPECIFICATIONS (TAC NOS. MB0695 AND MB0696)
Dear Mr. Nazar:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendments dated December 11, 2000, as supplemented by letters dated March 6, July 3, August 13, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002. The proposed amendments would convert the current Technical Specifications (TSs) for Prairie Island Nuclear Generating Plant, Units 1 and 2, to a set of improved TSs based on NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 1, dated April 1995.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Tae Kim, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Environmental Assessment cc w/encl: See next page
ML021830089 *No legal objection OFFICE PDIII-1/PM PDIII-1/LA RLEP OGC/NLO* PDIII-1/SC NAME TKim THarris for REmch for RWeisman LRaghavan RBouling JTappert DATE 07/03/02 07/02/02 07/08/02 07/12/02 07/15/02 7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NOS. 50-282 AND 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Facility Operating License Nos. DPR-42 and DPR-60, issued to Nuclear Management Company, LLC (the licensee) for operation of the Prairie Island Nuclear Generating Plant, Units 1 and 2, located in Goodhue County, Minnesota. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Sections 51.21 and 51.32, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would be a full conversion from the current technical specifications (CTS) to a set of improved technical specifications (ITS) based on NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 1, dated April 1995. The proposed action is in accordance with the licensees application dated December 11, 2000, as supplemented by letters dated March 6, July 3, August 13, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002.
The Need for the Proposed Action:
The Commissions Proposed Policy Statement on Technical Specifications
Improvements for Nuclear Power Reactors (52 FR 3788), dated February 6, 1987, contained an Interim Policy Statement that set forth objective criteria for determining which regulatory requirements and operating restrictions should be included in the technical specifications (TS).
When it issued the Interim Policy Statement, the Commission also requested comments on it.
Subsequently, to implement the Interim Policy Statement, each reactor vendor owners group and the NRC staff began developing standard TS (STS) for reactors supplied by each vendor.
The Commission then published its Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (58 FR 39132), dated July 22, 1993, in which it addressed comments received on the Interim Policy Statement, and incorporated experience in developing the STS. The Final Policy Statement formed the basis for a revision to 10 CFR 50.36 (60 FR 36953), dated July 19, 1995, that codified the criteria for determining the content of TS. The NRC Committee to Review Generic Requirements reviewed the STS, made note of their safety merits, and indicated its support of conversion by operating plants to the STS. For the Prairie Island Nuclear Generating Plant, Units 1 and 2, the STS are NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 1, dated April 1995. This document formed the basis for the Prairie Island Nuclear Generating Plant, Units 1 and 2, conversion.
The proposed changes to the CTS are based on NUREG-1431 and guidance provided in the Final Policy Statement. The objective of this action is to completely rewrite, reformat, and streamline the CTS (i.e., to convert the CTS to ITS). Emphasis was placed on human factors principles to improve clarity and understanding. The Bases section has been significantly expanded to clarify and better explain the purpose and foundation of each specification. In addition to NUREG-1431, portions of the CTS were also used as the basis for the development
of the Prairie Island Nuclear Generating Plant, Units 1 and 2 ITS. Plant-specific issues (i.e.,
unique design features, requirements, and operating practices) were discussed at length with the licensee.
The proposed changes from the CTS can be categorized into five general groupings.
These groupings are characterized as administrative changes, more restrictive changes, less restrictive changes, less restrictive relocated details, and relocated specifications.
Administrative changes include those changes that are editorial in nature or involve the reorganization or reformatting of CTS requirements without affecting technical content or operational restrictions.
More restrictive changes include those changes that result in added restrictions or reduced flexibility. The licensee, in electing to implement the specifications of the STS, proposed a number of requirements more restrictive than those in the CTS. The ITS requirements in this category include requirements that are either new, more conservative than corresponding requirements in the CTS, or have additional restrictions that are not in the CTS but are in the STS.
Less restrictive changes include deletions and relaxations to portions of the CTS in order to conform to the guidance of NUREG-1431, which would result in reduced restrictions or added flexibility. When requirements have been shown to provide little or no safety benefit, their relaxation or removal from the TSs may be appropriate. In most cases, relaxations previously granted to individual plants on a plant-specific basis were the result of (1) generic NRC actions, (2) new staff positions that have evolved from technological advancements and operating experience, or (3) resolution of the Owners Groups comments on STS.
Less restrictive relocated details include those changes to the CTS that eliminate details and relocate the details to licensee-controlled documents. Typically, this involves details of
system designs, system descriptions including design limits, descriptions of system or plant operation, procedural details for meeting TS requirements and relocated reporting requirements, and redundant requirement references.
Relocated specifications include those changes to the CTS that relocate certain requirements which do not meet the 10 CFR 50.36 selection criteria. These requirements may be relocated to the Bases, updated safety analysis report, core operating limits report (COLR),
operational quality assurance plan, plant procedures, or other licensee-controlled documents.
Relocating requirements to licensee-controlled documents does not eliminate them, but rather, places them under more appropriate regulatory controls (i.e., 10 CFR 50.54(a)(3), and 10 CFR 50.59) to manage their implementation and future changes.
In addition to the proposed changes solely involving the conversion, there are also changes proposed that are (1) different from the requirements in both the CTS and the STS and, (2) in addition to those changes that are needed to meet the overall purpose of the conversion. These changes are referred to as beyond-scope changes and include:
- 1. Extension of the certain surveillance interval from 18 months to 24 months to support the proposed refueling cycle of 24 months;
- 2. Extension of the allowed outage time for the emergency core cooling system accumulators from 1 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;
- 3. Missed surveillance consolidated line item improvement to extend the delay period for a missed surveillance requirement from the current limit of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to ...up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater;
- 4. Revision to the ventilation filter testing program to incorporate the guidance provided in NRC Generic Letter 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, dated June 3, 1999;
- 5. A new methodology (to be incorporated by reference into ITS Section 5.0) that describes the method by which the shutdown margin limit during physics testing is established for inclusion within the COLR;
- 6. A new methodology (to be incorporated by reference to ITS Section 5.0) that describes the method by which a factor, FQA , (in support of ITS 3.2.1, Heat Flux Channel Factor) is to be determined; and
- 7. Plant-specific instrument setpoint methodology in support of new instrument allowable values and trip setpoints in the ITS.
Environmental Impacts of the Proposed Action:
The NRC staff has completed its evaluation of the proposed action and concludes that the proposed TS conversion would not increase the probability or consequences of accidents previously analyzed and would not affect facility radiation levels or facility radiological effluents.
Specifically, the proposed TS changes will not increase the probability or consequences of accidents, no changes are being made in the types or amounts of any effluent that may be released offsite, and there is no significant increase in the allowable individual or cumulative occupational radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites because no previously undisturbed area will be affected by the proposed TS changes. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for the Prairie Island Nuclear Generating Plant, Units 1 and 2, dated May 1973.
Agencies and Persons Consulted:
On July 8, 2002, the staff consulted with Ms. Linda Bruemmer of Minnesota State Division of Environmental Health regarding the environmental impact of the proposed action.
The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated December 11, 2000, as supplemented by letters dated March 6, July 3, August 13, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible electronically from the
Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams\adams.html.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 15th day of July 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
J. E. Silberg, Esquire Tribal Council Shaw, Pittman, Potts and Trowbridge Prairie Island Indian Community 2300 N Street, N. W. ATTN: Environmental Department Washington, DC 20037 5636 Sturgeon Lake Road Welch, MN 55089 Site Licensing Manager Prairie Island Nuclear Generating Plant Mr. Roy A. Anderson Nuclear Management Company, LLC Executive Vice President and 1717 Wakonade Drive East Chief Nuclear Officer Welch, MN 55089 Nuclear Management Company, LLC 700 First Street Adonis A. Neblett Hudson, WI 54016 Assistant Attorney General Office of the Attorney General Nuclear Asset Manager 455 Minnesota Street Xcel Energy, Inc.
Suite 900 414 Nicollet Mall St. Paul, MN 55101-2127 Minneapolis, MN 55401 U.S. Nuclear Regulatory Commission Resident Inspectors Office 1719 Wakonade Drive East Welch, MN 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 March 2002