|
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:OCT 2 0 2QM1 L-PI-10-104 10 CFR 50.99 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Unit I Docket 50-282 License No. DPR-42 Sup~lement to Exiaent License Amendment Request to Modifv Technical Specifications Surveillance Requirement 3.8.1 .I0 for Prairie lsland Nuclear Generatina Plant Unit 1 /TAC No. ME48711 | | {{#Wiki_filter:OCT 2 0 2QM1 L-PI-10-104 10 CFR 50.99 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Unit I Docket 50-282 License No. DPR-42 Sup~lementto Exiaent License Amendment Request to Modifv Technical Specifications Surveillance Requirement 3.8.1. I 0 for Prairie lsland Nuclear Generatina Plant Unit 1 |
| | /TAC No. ME48711 |
|
| |
|
| ==References:== | | ==References:== |
| : 1) Letter from Northern States Power Company, a Minnesota corporation, (NSPM) to the Nuclear Regulatory Commission (NRC), "Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1 .I0 for Prairie lsland Nuclear Generating Plant Unit 1 ," L-PI-10-098, dated October 14, 2010. 2) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 15, 201 0 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1 ," L-PI-10-100, dated October 16, 201 0. 3) Letter from NSPM to the NRC, "Second Response to NRC Request for Additional lnformation received October 15, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit I ," L-PI-10-101, dated October 17, 2010. 4) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 17, 201 0 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1 ," L-PI-10-102, dated October 18, 201 0. 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: | | : 1) Letter from Northern States Power Company, a Minnesota corporation, (NSPM) to the Nuclear Regulatory Commission (NRC), |
| 651.388.1 121 Document Control Desk Page 2 In Reference 1, NSPM, doing business as Xcel Energy, submiged a License Amendment Request (LAR) to request an exigent amendment to the Prairie Island Nuclear Generating Plant (PINGP) | | "Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1 . I 0 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-098, dated October 14, 2010. |
| Unit I Technical Specifications (TS) surveillance requirements (SR). The proposed TS change would allow emergency diesel generator (EDG) D2 to be operable until SR 3.8,1 .I 0 can be performed during the scheduled Unit 1 201 1 refueling outage, Reference I also identified 12 Battery Charger performance issues that should be corrected prior to perFormanw of SR 3.8'1 .I0 for 02. In References 2, 3 and 4, NSPM provided supplemental information in support of the license amendment request. The NRC review of this LAR has identified the need for a dynamic electrical model for evaluation of the Unit I emergency diesel generator performance, As stated below, this letter provides an NSPM commitment to develop a dynamic electrical model. Enclosure 1 provides a listing of issues identified and documented in NSPM's corrective action process (CAP). Enclosure 2 provides proposed TS page 3.8.1-10 revised to clarify that repowering of the battery charger is automatic. | | : 2) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 15, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-100, dated October 16, 2010. |
| Reference 4 contains a numerical error in the third sentence of the first paragraph on page 8 of Enclosure | | : 3) Letter from NSPM to the NRC, "Second Response to NRC Request for Additional lnformation received October 15, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit I," L-PI-10-101, dated October 17, 2010. |
| : 1. The sentence should state:
| | : 4) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 17, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-102, dated October 18, 2010. |
| Using these values, the MCC voltages on EDGs Dl and D2 would remain above 67.7% (80% - 12.3%) and the MCC voltages on EDGs D5 and D6 would remain above 69.3% (85% - 15.7%). The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in the Reference 1 submittal as supplemented in References 2, 3 and 4. In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and enclosures to the designated State Official. | | 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121 |
| If there are any questions or if additional information is needed, please contact Jon Anderson at 651 -388-1 121 x7309. Summarv of Commitments This letter contains no revisions to existing commitments. This letter makes the following new commitment: Northern States Power Company, a Minnesota corporation, will develop a dynamic electrical model for the Prairie Island Nuclear Generating Plant Unit 1 emergency diesel generators by December 15,201 1. | | |
| Document Control Desk Page 3 I declare under penalty of perjury that the hrwaing is true and correct. Executed on OCT % @ 20@ Mark A. Schimmel Site Vice President, Prairie island Nuclear Generating Plant Northern States Power Campany - Minnesota I I Enclosures (2) ! I cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota Enclosure I Supplement to Exifient License Amendment Request to Modify This enclosure provides a list of issues identified and documented in the Northern States Power Company, a Minnesota corporation (NSPM), corrective action process (CAP) to support NRC review the exigent license amendment request (LAR) to modify Technical Specifications (TS) Surveillance Requirement (SR) 3.8.1 -10 for Prairie Island Nuclear Generating Plant (PINGP) Unit 1. For completeness, the list includes the CAP numbers previously provided by letter dated October 18, 201 0. following PINGP design basis accidents and applicability to the Page 1 of 1 ENCLOSURE 2 Technical SpsciFieatlon Pages (Markup) 1 page follows AC Sources-Operating 3.8.1 SR 3.8.1.10 -..-------------- | | Document Control Desk Page 2 In Reference 1, NSPM, doing business as Xcel Energy, submiged a License Amendment Request (LAR) to request an exigent amendment to the Prairie Island Nuclear Generating Plant (PINGP) Unit ITechnical Specifications (TS) surveillance requirements (SR). The proposed TS change would allow emergency diesel generator (EDG) D2 to be operable until SR 3.8,1.I 0 can be performed during the scheduled Unit 1 2011 refueling outage, Reference Ialso identified 12 Battery Charger performance issues that should be corrected prior to perFormanw of SR 3.8'1 . I 0 for 02. |
| ----..- -----.. T\fOTES--------------------------- | | In References 2, 3 and 4, NSPM provided supplemental information in support of the license amendment request. |
| : 1. All DG star& may be preceded by an engine preIube period. 2 - --This Surveillance shall not be perfomed in &-- MODE l,2,3, or 4. a. De-energization of emergency buses; Verif). on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated safety injection actuation signal: | | The NRC review of this LAR has identified the need for a dynamic electrical model for evaluation of the Unit Iemergency diesel generator performance, As stated below, this letter provides an NSPM commitment to develop a dynamic electrical model. |
| : b. Load shedding from emergency buses; and 24 months c. DG auto-starts from standby condition and energizes emergency loads in 5 60 seconds. SR 3.8.1.11 ............................ | | Enclosure 1 provides a listing of issues identified and documented in NSPM's corrective action process (CAP). Enclosure 2 provides proposed TS page 3.8.1-10 revised to clarify that repowering of the battery charger is automatic. |
| NOTE ............................ | | Reference 4 contains a numerical error in the third sentence of the first paragraph on page 8 of Enclosure 1. The sentence should state: |
| All DG starts may be preceded by an engine prelube period. ................................................................ | | Using these values, the MCC voltages on EDGs D l and D2 would remain above 67.7% (80% - 12.3%) and the MCC voltages on EDGs D5 and D6 would remain above 69.3% (85% - 15.7%). |
| *A riipdification | | The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in the Reference 1 submittal as supplemented in References 2, 3 and 4. |
| \till bc insti.llcd durinn or prior to tlie Unit 1-20 1 1-refueling ou&ge to aut~~mnatica~y shed the 12 E33en. Charger from its 11i3r1nal bus and then automatically repower the charger from tlze bus within 60 seconds. -- Compliance wit11 this SR will. be demonstrated after implementa_tion of the m_odificatio~i. Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.8.1-10 Unit 2 - Amendment No. 149 Verify on an actual or simulated loss of offsite power signal that the DG auto-starts fiom standby condition. 24 months}} | | In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and enclosures to the designated State Official. |
| | If there are any questions or if additional information is needed, please contact Jon Anderson at 651-388-1121 x7309. |
| | Summarv of Commitments This letter contains no revisions to existing commitments. This letter makes the following new commitment: |
| | Northern States Power Company, a Minnesota corporation, will develop a dynamic electrical model for the Prairie Island Nuclear Generating Plant Unit 1 emergency diesel generators by December 15,2011. |
| | |
| | Document Control Desk Page 3 I declare under penalty of perjury that the hrwaing is true and correct. |
| | Executed on OCT % @ 20@ |
| | Mark A. Schimmel Site Vice President, Prairie island Nuclear Generating Plant Northern States Power Campany - Minnesota I Enclosures (2) |
| | ! |
| | I cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota |
| | |
| | Enclosure I Supplement to Exifient License Amendment Request to Modify This enclosure provides a list of issues identified and documented in the Northern States Power Company, a Minnesota corporation (NSPM), corrective action process (CAP) to support NRC review the exigent license amendment request (LAR) to modify Technical Specifications (TS) Surveillance Requirement (SR) 3.8.1 -10for Prairie Island Nuclear Generating Plant (PINGP) Unit 1. For completeness, the list includes the CAP numbers previously provided by letter dated October 18, 2010. |
| | following PINGP design basis accidents and applicability to the Page 1 of 1 |
| | |
| | ENCLOSURE 2 Technical SpsciFieatlon Pages (Markup) 1 page follows |
| | |
| | AC Sources-Operating 3.8.1 SR 3.8.1.10 -..-------------- ----..- -----..T\fOTES--------------------------- |
| | : 1. All DG star& may be preceded by an engine preIube period. |
| | 2 - --This Surveillance shall not be perfomed in |
| | &-- |
| | MODE l , 2 , 3 , or 4. |
| | Verif). on an actual or simulated loss of offsite power 24 months signal in conjunction with an actual or simulated safety injection actuation signal: |
| | : a. De-energization of emergency buses; |
| | : b. Load shedding from emergency buses; and |
| | : c. DG auto-starts from standby condition and energizes emergency loads in 5 60 seconds. |
| | SR 3.8.1.11 ............................ NOTE ............................ |
| | All DG starts may be preceded by an engine prelube period. |
| | ................................................................ |
| | Verify on an actual or simulated loss of offsite power 24 months signal that the DG auto-starts fiom standby condition. |
| | *A riipdification \till bc insti.llcd durinn or prior to tlie Unit 1-2011-refuelingou&ge to aut~~mnatica~y shed the 12 E33en. Charger from its 11i3r1nalbus and then automatically repower the charger from tlze bus within 60 seconds. |
| | - -Compliance wit11 this SR will. be demonstrated after implementa_tionof the m_odificatio~i. |
| | Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.8.1-10 Unit 2 - Amendment No. 149}} |
Letter Sequence Supplement |
---|
|
|
MONTHYEARL-PI-10-100, Prairie Lsland, Unit 1 - Response to NRC Request for Additional Information Received October 15, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-16016 October 2010 Prairie Lsland, Unit 1 - Response to NRC Request for Additional Information Received October 15, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 Project stage: Response to RAI L-PI-10-101, Prairie Lsland, Unit 1, Second Response to NRC Request for Additional Information Received October 15, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-17017 October 2010 Prairie Lsland, Unit 1, Second Response to NRC Request for Additional Information Received October 15, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 Project stage: Response to RAI L-PI-10-102, Prairie Lsland, Unit 1 - Response to NRC Request for Additional Information Received October 17, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-18018 October 2010 Prairie Lsland, Unit 1 - Response to NRC Request for Additional Information Received October 17, 2010 Related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 Project stage: Response to RAI 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 Project stage: Supplement ML1029102062010-10-22022 October 2010 Issuance of Amendment No. 198 Regarding Technical Specification Surveillance Requirement 3.8.1.10 Project stage: Approval 2010-10-18
[Table View] |
|
---|
Category:Letter type:L
MONTHYEARL-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 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 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 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy 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 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 L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles 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 L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request 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 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 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-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
[Table view] Category:Technical Specifications
MONTHYEARML22357A1002023-03-31031 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) ML0728403542007-10-31031 October 2007 Tech Spec Page for Amendments 181 and 171, Revise TS 3.7.2 Main Steam Valves Closure Times by Relocating the Isolation Valve Closure Times to a Licensee-Controlled Document Identified as a Bases Reference L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007 License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load 2023-03-31
[Table view] |
Text
OCT 2 0 2QM1 L-PI-10-104 10 CFR 50.99 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Unit I Docket 50-282 License No. DPR-42 Sup~lementto Exiaent License Amendment Request to Modifv Technical Specifications Surveillance Requirement 3.8.1. I 0 for Prairie lsland Nuclear Generatina Plant Unit 1
/TAC No. ME48711
References:
- 1) Letter from Northern States Power Company, a Minnesota corporation, (NSPM) to the Nuclear Regulatory Commission (NRC),
"Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1 . I 0 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-098, dated October 14, 2010.
- 2) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 15, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-100, dated October 16, 2010.
- 3) Letter from NSPM to the NRC, "Second Response to NRC Request for Additional lnformation received October 15, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit I," L-PI-10-101, dated October 17, 2010.
- 4) Letter from NSPM to the NRC, "Response to NRC Request for Additional lnformation received October 17, 2010 related to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 for Prairie lsland Nuclear Generating Plant Unit 1," L-PI-10-102, dated October 18, 2010.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 In Reference 1, NSPM, doing business as Xcel Energy, submiged a License Amendment Request (LAR) to request an exigent amendment to the Prairie Island Nuclear Generating Plant (PINGP) Unit ITechnical Specifications (TS) surveillance requirements (SR). The proposed TS change would allow emergency diesel generator (EDG) D2 to be operable until SR 3.8,1.I 0 can be performed during the scheduled Unit 1 2011 refueling outage, Reference Ialso identified 12 Battery Charger performance issues that should be corrected prior to perFormanw of SR 3.8'1 . I 0 for 02.
In References 2, 3 and 4, NSPM provided supplemental information in support of the license amendment request.
The NRC review of this LAR has identified the need for a dynamic electrical model for evaluation of the Unit Iemergency diesel generator performance, As stated below, this letter provides an NSPM commitment to develop a dynamic electrical model.
Enclosure 1 provides a listing of issues identified and documented in NSPM's corrective action process (CAP). Enclosure 2 provides proposed TS page 3.8.1-10 revised to clarify that repowering of the battery charger is automatic.
Reference 4 contains a numerical error in the third sentence of the first paragraph on page 8 of Enclosure 1. The sentence should state:
Using these values, the MCC voltages on EDGs D l and D2 would remain above 67.7% (80% - 12.3%) and the MCC voltages on EDGs D5 and D6 would remain above 69.3% (85% - 15.7%).
The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in the Reference 1 submittal as supplemented in References 2, 3 and 4.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and enclosures to the designated State Official.
If there are any questions or if additional information is needed, please contact Jon Anderson at 651-388-1121 x7309.
Summarv of Commitments This letter contains no revisions to existing commitments. This letter makes the following new commitment:
Northern States Power Company, a Minnesota corporation, will develop a dynamic electrical model for the Prairie Island Nuclear Generating Plant Unit 1 emergency diesel generators by December 15,2011.
Document Control Desk Page 3 I declare under penalty of perjury that the hrwaing is true and correct.
Executed on OCT % @ 20@
Mark A. Schimmel Site Vice President, Prairie island Nuclear Generating Plant Northern States Power Campany - Minnesota I Enclosures (2)
!
I cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
Enclosure I Supplement to Exifient License Amendment Request to Modify This enclosure provides a list of issues identified and documented in the Northern States Power Company, a Minnesota corporation (NSPM), corrective action process (CAP) to support NRC review the exigent license amendment request (LAR) to modify Technical Specifications (TS) Surveillance Requirement (SR) 3.8.1 -10for Prairie Island Nuclear Generating Plant (PINGP) Unit 1. For completeness, the list includes the CAP numbers previously provided by letter dated October 18, 2010.
following PINGP design basis accidents and applicability to the Page 1 of 1
ENCLOSURE 2 Technical SpsciFieatlon Pages (Markup) 1 page follows
AC Sources-Operating 3.8.1 SR 3.8.1.10 -..-------------- ----..- -----..T\fOTES---------------------------
- 1. All DG star& may be preceded by an engine preIube period.
2 - --This Surveillance shall not be perfomed in
&--
MODE l , 2 , 3 , or 4.
Verif). on an actual or simulated loss of offsite power 24 months signal in conjunction with an actual or simulated safety injection actuation signal:
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses; and
- c. DG auto-starts from standby condition and energizes emergency loads in 5 60 seconds.
SR 3.8.1.11 ............................ NOTE ............................
All DG starts may be preceded by an engine prelube period.
................................................................
Verify on an actual or simulated loss of offsite power 24 months signal that the DG auto-starts fiom standby condition.
- A riipdification \till bc insti.llcd durinn or prior to tlie Unit 1-2011-refuelingou&ge to aut~~mnatica~y shed the 12 E33en. Charger from its 11i3r1nalbus and then automatically repower the charger from tlze bus within 60 seconds.
- -Compliance wit11 this SR will. be demonstrated after implementa_tionof the m_odificatio~i.
Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.8.1-10 Unit 2 - Amendment No. 149