Letter Sequence Response to RAI |
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TAC:ME2609, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME2610, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
Results
Other: L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5, L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement, ML102300296, ML102300297, ML102300298, ML111822669
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MONTHYEARL-PI-09-114, License Amendment Request to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request ML0935704512009-12-23023 December 2009 Acceptance Review of LAR to Adopt Alternative Source Term Methodology (TAC Nos. ME2609 & ME2610) Project stage: Acceptance Review L-PI-10-041, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-04-29029 April 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-046, Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology2010-05-25025 May 2010 Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-06-23023 June 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 Project stage: Other ML1023002982010-07-23023 July 2010 Calculation No. GEN-PI-082, Revision 1, Control Rod Ejection Accident - AST, Attachment 4 Project stage: Other ML1023002972010-07-23023 July 2010 Calculation No. GEN-PI-081, Revision 1, Eab, LPZ, and CR Doses Due to Steam Generator Tube Rupture Accident - AST, Attachment 3 Project stage: Other ML1023002962010-07-23023 July 2010 Calculation No. GEN-PI-078, Revision 1, Main Steam Line Break (MSLB) Accident Analysis Using AST, Attachment 2 Project stage: Other ML1022200872010-08-10010 August 2010 Forthcoming Meeting with Northern States Power Company - Minnesota (Nspm), to Discuss the Prairie Island Nuclear Generating Plant Steam Generator Margin-to-Overfill Analysis as It Relates to Pingp'S License Amendment Request to Adopt... Project stage: Meeting ML1023002952010-08-12012 August 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant Project stage: Request ML1025903972010-09-23023 September 2010 Prairie Island, Summary of Meeting with Northern States Power Company to Discuss the Alternative Source Term License Amendment Request Project stage: Meeting ML1032205572010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI ML1032205552010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI L-PI-10-112, Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102)2010-12-17017 December 2010 Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102) Project stage: Response to RAI ML1110400212011-04-0404 April 2011 NRR E-mail Capture - Prairie Island - Revised Alternative Source Term LAR Draft RAI 4-4-2011 Project stage: Draft RAI ML1035404332011-05-12012 May 2011 Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term Project stage: RAI L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-06-22022 June 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1118226692011-06-29029 June 2011 PINGP - AST Methodology - ME2609 and ME2610 Project stage: Other L-PI-11-068, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-07-11011 July 2011 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1120819672011-07-20020 July 2011 E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Project stage: RAI L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-08-0909 August 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1125503562011-09-0101 September 2011 Ngp - Draft RAI Concerning SGTR Instrumentation for Alternative Source Term LAR Project stage: Draft RAI ML1125503572011-09-0101 September 2011 PINGP Draft RAI - AST Instrumentation Project stage: Draft RAI ML1131100842011-11-0202 November 2011 Alternative Source Term Draft Request for Additional Information Project stage: Draft RAI ML1131100942011-11-0202 November 2011 RAI Prairie PINGP, Units 1 and 2 Project stage: RAI L-PI-11-099, Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology2011-12-0808 December 2011 Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI L-PI-12-010, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology2012-02-13013 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology Project stage: Response to RAI 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 Project stage: Response to RAI L-PI-12-082, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2012-09-13013 September 2012 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1125212892013-01-22022 January 2013 Issuance of Amendments Adoption of Alternative Source Term Methodology Project stage: Approval L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement2014-01-13013 January 2014 Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement Project stage: Other 2011-12-08
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Category:Letter type:L
MONTHYEARL-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations 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 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 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) 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 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing 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 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) 2024-06-05
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DEC 1 7 2010 L-PI-10-112 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Response to Reuuest for Additional Information RE: License Amendment Reauest to Adopt the Alternative Source Term Methodoloav (TAC NOS. ME2609 and ME26102
References:
- 1. Xcel Energy Letter to US NRC, "License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology," dated October 27, 2009 (ADAMS Accession No. ML093160583).
- 2. US NRC Letter to Xcel Energy, "Prairie lsland Nuclear Generating Plant, Units 1 and 2 - Requests for Additional lnformation RE: License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME261O)," dated March 26,2010 (ADAMS Accession No. ML100820298).
- 3. Xcel Energy Letter to US NRC, "Response to Requests for Additional lnformation RE: License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME261O)," dated May 25,201 0 (ADAMS Accession No. ML101460064).
- 4. US NRC Email to Xcel Energy, "Prairie lsland - Draft RAI for Alternative Source Term LAR (SRXB and SCVB)," dated September 21,2010.
In Reference 1, the Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, hereby requested an amendment to the Technical Specifications (TS) for Prairie lsland Nuclear Generating Plant (PINGP). The proposed amendment requested to adopt the Alternative Source Term (AST) methodology, in addition to TS changes supported by the AST design basis accident radiological consequence analyses.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 In Reference 2, the Nuclear Regulatory Cammission (NRC) Staff requested additional information to support. their review of Referenw 1. In Reference 3, NSPM provided the responses to the Reactor Systems Branch request far additional information (RAI). In Referenw 4, the NRC sent follow-up questions via electronic mail.
Enclosure 1 to this letter provides a response to one of the NRC Staff RAls, specifi~lly, a response to the Containment and Ventilation Systems Branch (SCVE3) FPAI, SCVS-1.
NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the October 27, 2009 submittal as supplemented on April 29,2010, May 25,2010, June 23,201 0, and August 12,2010, 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 to the designated State Official.
If there are any questions or if additional information is needed, please contact Ms. Amy Hazelhoff, at 269-370-7445.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on KC 1 2 2010 Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
NSPM Enclosure 1 Nuclear Regulatory Commission (NRQ Raqutaist for Additional Infomation ( M I )
CONTAINMENT AND VEN7"iUTiQN SYSTEMS BRANCH (SCVB)
NRC RAI SCVB-I Calculation No. GEN-PI-079, "Post-LOCAEAB, LPZ, and CR Doses AST" (Attachment 6 to Enclosure to the October 27, 2009 application), assumes a specific Shield Building leakage rate as shown in Table 2 (Page 64 of 257 of the calculation). This leakags rate helps determine the recirculation and holdup time of any source term leaking into the Shield Building annulus.
Describe the periodic verificationperformed to assure that the Shield Building leakage rate remains within the values assumed in the accident analyses.
Northern States Power Company, a Minnesota corporation (NSPM) Response SCVB-1 RAI The Shield Building leakage rates shown in Table 2, of Calculation No. GEN-PI-079, "Post-LOCA EAB, LPZ and CR Doses - AST," are not specifically used in the calculation. Section 5.0 in Calculation No. GEN-PI-079 describes the design inputs that are used in the calculation. As shown in Section 5.0, the key inputs related to the Shield Building are as follows:
Design lnput 5.3.2.3, Identified as L,, shows leakage from Containment to the Shield Building. Figure 2 provides a schematic of the Containment leakage paths. As shown on Figure 2, leakage from Containment to the Shield Building is modeled as bypassing the Shield Building and being released directly to the environment during the first 22 minutes following initiation of the accident. After 22 minutes, this leakage is modeled as released to the Shield Building. 22 minutes is consistent with Design lnput 5.3.2.6, for the time of initiation of Shield Building recirculation.
Design lnput 5.3.2.8 shows that a Shield Building exhaust rate of 2000 cfm is used in the analysis. This is applicable after the initial 22 minutes. Table 2 indicates that the exhaust flow rate after 20 minutes is 1000 cfm. Note that the 22 minutes is used to be conservative relative to the 20 minutes in Table 2. As described in the Reference column for Design lnput 5.3.2.8, the Shield Building exhaust flow rate in Table 2 is doubled to simulate 50% mixing in the Shield Building after 22 minutes.
As described above, the capability for the Shield Building Ventilation System (SBVS) to collect and filter containment leakage is credited in the analysis. In order to perform this function, the SBVS must be capable of producing and maintaining a negative pressure in the Shield Building Annulus. Inleakage can affect the ability to produce and maintain a negative pressure in the Shield Building Annulus. The inleakage rate can also affect the SBVS exhaust flow rate.
Periodic verification of the Shield Building integrity is performed per Technical Specification Surveillance Requirements (SR). Specifically, the capability for the Shield Building Ventilation Page 1 of 2
NSPM Enclosure 1 System to produce and maintain a negative pressure in the Shield Building Annulus is verified monthly per Technical Specification SF? 3.6.10.2. The Bases for SR 3.6.10.2 states:
"The SBVS produces a negative pressure to prevent leakage from the building. SR 3.6.10.2 verifies that the shield building can be npidly drawn down to -2.00 inch water gauge and maintains a pressure equal to or more negative then -1.82 inches of water gauge in the annulus after the recirculation damprs open and equilibrium is established.
Equilibrium negative pressure equal to or more negative than -1.82 inches water gauge is that predicted for non-accident conditions and leakage equal to 75% of the maximum allowable shield building inleakage (Reference 2). Establishment of this pressure is confirmed by SR 3.6.10.2, which demonstrates that the shield building can be drawn down to a pressure equal to or more negative than -2.0 inches of water gauge in the annulus using one SBVS train."
Reference 2 in the Bases for SR 3.6.10.2 is, "Report to the United States Nuclear Regulatory Commission Division of Operating Reactors Prairie Island Containment Systems Special Analyses," dated April 9, 1976. A curve is provided in SR 3.6.10.2 Bases Reference 2, which predicts the pressure in the Shield Building Annulus with 75% of the maximum allowable shield building inleakage. As described in the Bases for SR 3.6.10.2, this curve is used to determine the acceptance criteria for the associated Surveillance Procedures. The associated Surveillance Procedures confirm that the following acceptance criteria are satisfied:
Peak differential pressure between the Shield Building Annulus and the Auxiliary Building is greater than (more negative) 2.0" H20. At 2.0" H20,the SBVS recirculation damper opens.
Equilibrium differential pressure between Shield Building Annulus and Turbine Building is maintained greater than (more negative) or equal to 1.82" H20.
The equilibrium differential pressure value of 1.82" H20corresponds to the equilibrium value predicted in Reference 2, cited in the Bases for SR 3.6.10.2. During the surveillance testing the equilibrium differential pressure would be affected by the inleakage rate. If the inleakage were higher than 75% of the maximum allowable shield building inleakage, the differential pressure would correspondingly be less than 1.82" H20 (i.e., less negative pressure condition).
This approach of using the drawdown testing to confirm Shield Building leak tightness was confirmed in NRC Safety Evaluation (SE) for License Amendments 62 and 56, dated February 23, 1983 (ADAMS Accession No. ML022180360)which concludes (page 10 of the SE) that drawdown performance testing provides assurance that the leakage rate requirements are met.
Therefore, through demonstration of the ability to produce and maintain a negative pressure in the Shield Building Annulus, adequate testing is performed to assure that leakage requirements are periodically verified.
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