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| | number = ML092570367 | | | number = ML092570367 |
| | issue date = 09/15/2009 | | | issue date = 09/15/2009 |
| | title = Prairie Island Nuclear Generating Plant, Units 1 and 2 - Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) | | | title = Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Schimmel M A | | | addressee name = Schimmel M |
| | addressee affiliation = Northern States Power Co | | | addressee affiliation = Northern States Power Co |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
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Line 14: |
| | page count = 3 | | | page count = 3 |
| | project = TAC:MD9142, TAC:MD9143 | | | project = TAC:MD9142, TAC:MD9143 |
| | stage = RAI | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 15, 2009 Mr. Mark A. Schimmel Site Vice President | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 15, 2009 Mr. Mark A. Schimmel Site Vice President - Acting Prairie Island Nuclear Generating Plant Northern States Power - Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MD9142 AND MD9143) |
| -Acting Prairie Island Nuclear Generating Plant Northern States Power -Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MD9142 AND MD9143) | |
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| ==Dear Mr. Schimmel:== | | ==Dear Mr. Schimmel:== |
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| On July 1, 2009 (Agencywide Documents Access and Management System Accession No. ML091460809), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. DPR-42 and Amendment No. 181 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), respectively. | | On July 1, 2009 (Agencywide Documents Access and Management System Accession No. ML091460809), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. DPR-42 and Amendment No. 181 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), |
| The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 26,2008, as supplemented by letters dated August 4, August 26, and November 14, 2008, and January 30, February 9, February 20, March 12, and May 4 (2 letters) 2009. The amendments revised the PINGP TSs to allow the use of Westinghouse 422 VANTAGE+ nuclear fuel and made changes to certain references identified in the Design Features section of the TSs. TS page 2.0-1, issued with the amendments, contained two editorial errors. In TS section 2.1.1.1, the phrase "... for OFA fuel" was inadvertently retained in the issued TS page. The marked-up TS page submitted with the June 26, 2008, application, correctly showed the change to remove these words from the sentence. | | respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 26,2008, as supplemented by letters dated August 4, August 26, and November 14, 2008, and January 30, February 9, February 20, March 12, and May 4 (2 letters) 2009. |
| Also, in TS Section 2.1.1.2 (b), the abbreviation for weight percent (w/o) was erroneously notated in subscript font. TS page 2.0-1 has been revised to correct the editorial errors that were inadvertently introduced when the NRC processed Amendment Nos. 192 and 181. Please replace the corresponding page from the TS with the corrected page 2.0-1 enclosed with this letter. | | The amendments revised the PINGP TSs to allow the use of Westinghouse 422 VANTAGE+ |
| M. Schimmel This correction does not change any of the conclusions in the safety evaluation associated with these amendments. | | nuclear fuel and made changes to certain references identified in the Design Features section of the TSs. |
| Please contact me at (301) 415-4037 if you have any questions on this issue. Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and Corrected TS Page cc w/encls: Distribution via SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded: | | TS page 2.0-1, issued with the amendments, contained two editorial errors. In TS section 2.1.1.1, the phrase "... for OFA fuel" was inadvertently retained in the issued TS page. The marked-up TS page submitted with the June 26, 2008, application, correctly showed the change to remove these words from the sentence. Also, in TS Section 2.1.1.2 (b), the abbreviation for weight percent (w/o) was erroneously notated in subscript font. |
| 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> | | TS page 2.0-1 has been revised to correct the editorial errors that were inadvertently introduced when the NRC processed Amendment Nos. 192 and 181. Please replace the corresponding page from the TS with the corrected page 2.0-1 enclosed with this letter. |
| 1.17 for WRB-1 DNB correlation. | | |
| 2.1.1.2 The peak fuel centerline temperature shall be maintained as follows: a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gd z 0 3), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained | | M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue. |
| ::s 2735 psig. 2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. 2.2.2 If SL 2.1.2 is violated: In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. In MODE 3, 4, or 5, restore compliance within 5 minutes. Prairie Island Unit 1 -Amendment No. 192 Units land 2 2.0-1 Unit 2 -Amendment No. -l-49 BJ. 181 Revised hy letter dated 15, 200Q M. Schimmel This correction does not change any of the conclusions in the safety evaluation associated with these amendments. | | Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 |
| Please contact me at (301) 415-4037 if you have any questions on this issue. Sincerely, IRA by M. Chawla fori Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and Corrected TS Page cc w/encls: Distribution via DISTRIBUTION PUBLIC LPL3-1 rlf RidsNrrPMPrairielsland Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrDirsltsb Resource ADAMS Accession No ML092570367 OFFICE NRRlLPL3-11 PM NRRlLPL3-11 LA NRRlLPL3-1/(A)BC NAME TWengert BTuily TWengert (M. Chawla for) (T. Harris for) DATE 09/15/09 09/15/09 09/15/09 OFFICIAL RECORD COpy}} | | |
| | ==Enclosure:== |
| | |
| | Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ |
| | |
| | SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded: |
| | 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> 1.17 for WRB-1 DNB correlation. |
| | 2.1.1.2 The peak fuel centerline temperature shall be maintained as follows: |
| | a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gdz0 3 ), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained |
| | ::s 2735 psig. |
| | 2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. |
| | 2.2.2 If SL 2.1.2 is violated: |
| | 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. |
| | 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. |
| | Prairie Island Unit 1 - Amendment No. ~ ~ 192 Units land 2 2.0-1 Unit 2 - Amendment No. -l-49 BJ. 181 Revised hy letter dated Septe~her 15, 200Q |
| | |
| | M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue. |
| | Sincerely, IRA by M. Chawla fori Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 |
| | |
| | ==Enclosure:== |
| | |
| | Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 rlf RidsNrrDorlLpl3-1 Resource RidsOgcRp Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsNrrDirsltsb Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No ML092570367 OFFICE NRRlLPL3-11 PM NRRlLPL3-11 LA NRRlLPL3-1/(A)BC NAME TWengert BTuily TWengert (M. Chawla for) (T. Harris for) |
| | DATE 09/15/09 09/15/09 09/15/09 OFFICIAL RECORD COpy}} |
Letter Sequence Other |
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MONTHYEARL-PI-08-047, License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel2008-06-26026 June 2008
License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel
Project stage: Request
ML0822101322008-07-22022 July 2008
Email - Prairie Island Acceptance Review Questions for LAR to Allow Use of West. 14X14 Vantage+ Fuel (TACs MD9142/MD9143)
Project stage: Acceptance Review
ML0820605722008-07-28028 July 2008
Request for Supplemental Information, Acceptance Review of License Amendment Request
Project stage: Acceptance Review
L-PI-08-071, Supplement to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2008-08-26026 August 2008
Supplement to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel
Project stage: Supplement
ML0822614492008-08-28028 August 2008
Acceptance of Requested Licensing Action Technical Specification Changes to Allow Use of Westinghouse 0.422-inch OD 14X14 Vantage+ Fuel
Project stage: Acceptance Review
ML0828106452008-10-17017 October 2008
Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage+Fuel (Tac No. MD9142, MD9143)
Project stage: RAI
L-PI-08-096, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse. 0.422- Inch OD 14x14 Vantage + Fuel2008-11-14014 November 2008
Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse. 0.422- Inch OD 14x14 Vantage + Fuel
Project stage: Response to RAI
ML0833002102008-12-15015 December 2008
Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel (TAC Nos. MD9142/9143)
Project stage: RAI
ML0835200472008-12-30030 December 2008
Request Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Tac Nos. MD9142 and MD9143)
Project stage: Other
ML0835800982009-01-12012 January 2009
Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel (TAC Nos. MD9142/9143)
Project stage: RAI
L-PI-09-011, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2009-01-30030 January 2009
Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel
Project stage: Response to RAI
L-PI-09-022, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2009-02-0909 February 2009
Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel
Project stage: Response to RAI
ML0901403342009-02-11011 February 2009
RAI for TS Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+Fuel
Project stage: RAI
L-PI-09-025, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel2009-02-20020 February 2009
Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel
Project stage: Response to RAI
L-PI-09-034, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage + Fuel2009-03-12012 March 2009
Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage + Fuel
Project stage: Response to RAI
ML0907210882009-03-12012 March 2009
Enclosure 1, Non-Proprietary Responses to Requests for Additional Information License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 422V+ Fuel
Project stage: Response to RAI
ML0907102152009-03-25025 March 2009
Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2
Project stage: Withholding Request Acceptance
L-PI-09-066, 422V+Fuel Transition Project RAI Response-EMCB RAI-1(a)2009-04-27027 April 2009
422V+Fuel Transition Project RAI Response-EMCB RAI-1(a)
Project stage: Other
L-PI-09-065, Supplemental Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+Fuel2009-05-0404 May 2009
Supplemental Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+Fuel
Project stage: Supplement
ML0913103842009-05-0404 May 2009
Clarification of Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel
Project stage: Response to RAI
ML0914905612009-06-0808 June 2009
Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2
Project stage: Withholding Request Acceptance
ML0917402012009-06-25025 June 2009
Public Letter Draft Safety Evaluation for License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel
Project stage: Draft Approval
ML0914608092009-07-0101 July 2009
Issuance of Amendments Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel
Project stage: Approval
ML0922403322009-08-31031 August 2009
Correction to Safety Evaluation Supporting Amendment Nos. 192 and 181 Technical Specification Changes to Allow Use of Westinghouse 0.422-Inch OD 14 X 14 Vantage+ Fuel (TAC Nos. MD9142/MD9143)
Project stage: Approval
ML0925703672009-09-15015 September 2009
Correction to Technical Specifications (TAC Nos. MD9142 and MD9143)
Project stage: Other
2009-02-11
[Table View] |
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Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024
Response to Alternative RR-10, Auxiliary Feedwater Valve Testing
IR 05000282/20244032024-10-25025 October 2024
– Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403
05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024
Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies
L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024
Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program
ML24277A1012024-10-0303 October 2024
Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software
ML24221A3622024-09-27027 September 2024
Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3
ML24241A1682024-09-23023 September 2024
Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024
Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies
IR 05000282/20243012024-09-13013 September 2024
NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301
IR 05000282/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005)
L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024
Post-Submittal Package Letter
IR 05000282/20245012024-08-0505 August 2024
Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501
ML24213A1592024-07-31031 July 2024
Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant
IR 05000282/20240022024-07-30030 July 2024
Integrated Inspection Report 05000282/2024002 and 05000306/2024002
ML24208A1502024-07-26026 July 2024
Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1)
ML24197A2012024-07-15015 July 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004
IR 05000282/20240102024-06-28028 June 2024
Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010
L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024
– Preparation and Scheduling of Operator Licensing Examinations
ML24158A5912024-06-0606 June 2024
CFR 50.46 LOCA Annual Report
L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024
Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)
L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024
License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption
05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
ML24155A1922024-05-31031 May 2024
Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections
ML24149A3712024-05-29029 May 2024
(Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
ML24262A1992024-05-29029 May 2024
L-PI-24-018 PINGP 75 Day Letter
L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1
ML24141A1292024-05-22022 May 2024
Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information
ML24141A0452024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML24128A2572024-05-16016 May 2024
ISFSI A13 Acceptance Letter
IR 05000282/20240012024-05-15015 May 2024
Integrated Inspection Report 05000282/2024001 and 05000306/2024001
ML24130A2362024-05-0909 May 2024
Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report
ML24130A2392024-05-0909 May 2024
2023 Annual Radioactive Effluent Report
ML24071A1162024-05-0101 May 2024
Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System
ML24128A0882024-04-30030 April 2024
Submittal of Updated Safety Analysis Report (Usar), Revision 38
05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
ML24089A2382024-04-29029 April 2024
Summary of Nuclear Property Insurance
IR 05000282/20244012024-04-25025 April 2024
– Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401
ML24100A8042024-04-24024 April 2024
– Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing
ML24114A0882024-04-23023 April 2024
Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP)
ML24113A1182024-04-12012 April 2024
NRC Letter Re NRC Office of Investigations Report No. 3-2023-004
ML24100A1212024-04-0909 April 2024
Submittal of Revised Pressure and Temperature Limits Report
ML24093A2832024-04-0202 April 2024
Nuclear Material Transaction Report
L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024
Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)
ML24089A2402024-03-29029 March 2024
Guarantee of Payment of Deferred Premiums
ML24060A1232024-03-27027 March 2024
To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds
05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024
Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables
ML24262A1512024-03-15015 March 2024
L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam
ML24010A0582024-03-0505 March 2024
Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024
Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023
IR 05000282/20230062024-02-28028 February 2024
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006)
2024-09-27
[Table view]
Category:Technical Specifications
MONTHYEARML24221A3622024-09-27027 September 2024
Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3
ML24071A1162024-05-0101 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
ML11172A0202011-06-27027 June 2011
Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
ML11172A0222011-06-27027 June 2011
Technical Specifications, Unit 2, 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
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(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
2024-09-27
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 15, 2009 Mr. Mark A. Schimmel Site Vice President - Acting Prairie Island Nuclear Generating Plant Northern States Power - Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MD9142 AND MD9143)
Dear Mr. Schimmel:
On July 1, 2009 (Agencywide Documents Access and Management System Accession No. ML091460809), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. DPR-42 and Amendment No. 181 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP),
respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 26,2008, as supplemented by letters dated August 4, August 26, and November 14, 2008, and January 30, February 9, February 20, March 12, and May 4 (2 letters) 2009.
The amendments revised the PINGP TSs to allow the use of Westinghouse 422 VANTAGE+
nuclear fuel and made changes to certain references identified in the Design Features section of the TSs.
TS page 2.0-1, issued with the amendments, contained two editorial errors. In TS section 2.1.1.1, the phrase "... for OFA fuel" was inadvertently retained in the issued TS page. The marked-up TS page submitted with the June 26, 2008, application, correctly showed the change to remove these words from the sentence. Also, in TS Section 2.1.1.2 (b), the abbreviation for weight percent (w/o) was erroneously notated in subscript font.
TS page 2.0-1 has been revised to correct the editorial errors that were inadvertently introduced when the NRC processed Amendment Nos. 192 and 181. Please replace the corresponding page from the TS with the corrected page 2.0-1 enclosed with this letter.
M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded:
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> 1.17 for WRB-1 DNB correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained as follows:
a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gdz0 3 ), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained
- s 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
Prairie Island Unit 1 - Amendment No. ~ ~ 192 Units land 2 2.0-1 Unit 2 - Amendment No. -l-49 BJ. 181 Revised hy letter dated Septe~her 15, 200Q
M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.
Sincerely, IRA by M. Chawla fori Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 rlf RidsNrrDorlLpl3-1 Resource RidsOgcRp Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsNrrDirsltsb Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No ML092570367 OFFICE NRRlLPL3-11 PM NRRlLPL3-11 LA NRRlLPL3-1/(A)BC NAME TWengert BTuily TWengert (M. Chawla for) (T. Harris for)
DATE 09/15/09 09/15/09 09/15/09 OFFICIAL RECORD COpy
