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MONTHYEARML0603301702006-02-0101 February 2006 Slides on Emergency Diesel Generator Completion Time Extension License Amendment Request Project stage: Request ML0604001982006-02-10010 February 2006 Summary of Meeting with Nuclear Management Company, LLC Regarding Emergency Diesel Generators at Prairie Island Nuclear Generating Plant, Units 1 and 2 (TAC No.'S MC9001 & MC9002) Project stage: Meeting ML0609506132006-04-0404 April 2006 E-Mail, Request for Additional Information on PI LAR - MC9001/MC9002 Project stage: RAI L-PI-06-031, Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-06-16016 June 2006 Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0622100052006-08-0808 August 2006 LAR for EDG Extension and Completion Time Project stage: Other L-PI-06-069, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time (TAC MC9001 & MC9002)2006-08-31031 August 2006 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time (TAC MC9001 & MC9002) Project stage: Supplement ML0624904012006-09-0808 September 2006 Notice of Meeting with Nuclear Management Company, LLC Regarding Extension of Completion Time for Emergency Diesel Generators for Prairie Island Units 1 and 2 Project stage: Meeting L-PI-06-073, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-09-29029 September 2006 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0627202922006-10-20020 October 2006 Summary of September 21, 2006, Category 1 Meeting with Nuclear Management Company, LLC (Nmc), to Discuss Extension of Completion Time for Emergency Diesel Generators Project stage: Meeting L-PI-06-077, Supplement to License Amendment Request for Extension of Technical Specification 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-10-30030 October 2006 Supplement to License Amendment Request for Extension of Technical Specification 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement L-HU-07-009, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2007-03-15015 March 2007 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement L-PI-07-039, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2007-05-10010 May 2007 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0713100232007-05-30030 May 2007 Issuance of Amendments Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generators DG Completion Time Tac Nos. MC9001 and MC9002 Project stage: Approval ML0714900042007-05-30030 May 2007 Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generator (EDG) Completion Time (Tac Nos. MC9001 and MC9002) Project stage: Other ML0717005682007-07-0505 July 2007 Correction Letter - Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generators (DG) Completion Time Project stage: Other 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 Project stage: Request 2006-08-08
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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
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L-PI-06-069 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) For Extension Of Technical Specification (TS) 3.8.1, "AC Sources-Operating," Emergencv Diesel Generator Completion Time (TAC Nos. MC9001 and MC9002)
By letter dated November 21,2005, Nuclear Management Company (NMC) submitted an LAR to revise the Emergency Diesel Generator (EDG) Completion Time in TS 3.8.1 Condition B.4 from 7 days to 14 days. By letter dated June 16, 2006, NMC provided supplemental information to this LAR. This letter supplements the LAR to address an NRC request for additional information (RAI) regarding the LAR and the June 16, 2006 supplement. NMC submits this supplement in accordance with the provisions of 10 CFR 50.90. provides the NRC RAI and the NMC response.
The supplemental information provided in this letter and enclosure does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the November 21, 2005 submittal as supplemented June 16, 2006.
In accordance with 10 CFR 50.91, NMC is notifying the State of Minnesota of this LAR by transmitting a copy of this letter and enclosure to the designated State Official.
Summaw of Commitments This letter contains no new commitments and no revisions to existing commitments.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on BUG 3 1 2006 Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota
Enclosure 1 NRC Question:
During an August 9, 2006 conference call, the NRC Staff requested additional information related to the response the Nuclear Management Company (NMC) provided for the NRC request for additional information (RAI) Question 13 in to the supplement dated June 16, 2006. Specifically, the NRC Staff requests NMC to provide the ACDF and ALERF values when 14 days of Completion Time unavailability are added to the existing Preventive Maintenance (PM) values.
Nuclear Management Company, LLC (NMC) response:
As stated in RAI Question 13, the baseline emergency diesel generator (EDG) preventive maintenance values used in the risk analysis provided in the submittal were based on a plant-specific data collection over a 10-year period (81111994 to 91112004).
These values include preventive maintenance performed within the current Technical Specification (TS) allowed 7-day Completion Time, and unavailability associated with surveillance and other testing performed on the EDGs. Surveillance testing unavailability is a consideration for the Prairie Island Nuclear Generating Plant (PINGP)
Unit 1 EDGs, D l and D2, which have mechanical governors. Unavailability time is conservatively counted whenever the speed droop governor setting on the EDG set is adjusted away from normal during load testing (including during the monthly test). The PINGP Unit 2 EDGs, D5 and D6, have an electronic governor system and are not subject to this type of unavailability during routine testing.
The current preventive maintenance (PM) program schedules an overhaul for each diesel every 18 months. The response to RAI Question 13 in Reference 1 assumed EDG PM unavailability due to a 14 day major overhaul normalized over the 18 month maintenance cycle (2.7E-02).
In the updated analysis for this supplement, revised PM values were determined by summing the existing PM unavailability term for each EDG with the EDG PM unavailability due to a 14 day major overhaul. The existing Unit 1 EDG PM term is 1.47E-02 and the existing Unit 2 PM term is 1.23E-02. The 14 day overhaul PM was calculated in response to RAI Question 13 in Reference 1 (2.7E-02). These revised PM values were used to determine core damage frequency (CDF) and large early release frequency (LERF) values.
These revised PM values are conservative. The original PM value already accounts for EDG preventive maintenance activities under the current Technical Specification 7 day Page 1 of 3
L-PI-06-069 allowed Completion Time, including unavailability due to surveillance testing. This supplement assumes an additional 14 day PM is performed every 18 months. The increased preventive maintenance values are shown in Table 1 below.
Table 1 Increased PM Terms Diesel Original PM 14-Day CT Revised PM Generator Value PM Value Value Dl 1.47E-02 2.70E-02 4.17E-02 D2 1.47E-02 2.70E-02 4.17E-02 D5 1.23E-02 2.70E-02 3.93E-02 D6 1.23E-02 2.70E-02 3.93E-02 The ACDF and ALERF results for increased preventive maintenance can be found in Table 2 below. Table 2 below corresponds to Table 2 in the original license amendment request (LAR) submittal (Reference 2).
Table 2 ACDF and ALERF Results for lncreased PM 1I Riskparameter 11 ( 1 Unit 2 (peryr) 1 RG' 1.174 criteria 1
Base Line CDF 1.47E-05 ( 1.63E-05 1 NA I Base Line LERF 5.74E-07 5.74E-07 NA I New CDF I 1.51E-05 1 1.68E-05 1 NA I I New LERF 1 5.74E-07 ( 5.74E-07 1 NA I ACDF 3.80E-07 5.05E-07 < 1E-6 I I Regulatory Guide The results presented in Table 2 above show that the ACDF and ALERF results are less than the RG 1.174 values for very small risk increases.
As a sensitivity study, it was assumed that the corrective maintenance (CM) term may increase as a result of extended outage time available for emergent work. The existing CM term was scaled by the ratio of the proposed and current Completion Time or 1417.
The resulting values are shown in the response to RAI Question 13, Table 13-4 in Reference 1. These PM and CM increases were applied to all EDGs. The ACDF and Page 2 of 3
L-PI-06-069 ALERF results for increased preventive maintenance and corrective maintenance can be found in Table 3 below. Table 3 below corresponds to Table 3 in the original LAR submittal (Reference 2).
Table 3 ACDF and ALERF Results for Increased PM and CM Risk Parameter 1 ) I Unit 2 (per yr) 1 RG' 1.174 criteria 1
Base Line CDF 1.47E-05 1.63E-05 NA Base Line LERF 5.74E-07 5.74E-07 NA New CDF 1.52E-05 1.70E-05 NA P P P New LERF 5.74E-07 5.74E-07 NA ACDF 5.00E-07 6.72E-07 <1E-6 ALERF 1 I
< 5E-10 I I
< 5E-10 I I
clE-7 1 1
Regulatory Guide The results presented in Table 3 above show that the ACDF and ALERF results are less than the RG 1.I74 values for very small risk increases.
References:
1.) Supplement to License Amendment Request (LAR) For Extension of Technical Specification (TS) 3.8.1, "AC Sources-Operating," Emergency Diesel Generator Completion Time (TAC Nos. MC9001 and MC9002), L-PI-06-031, dated June 16, 2006.
2.) License Amendment Request (LAR) For Extension of Technical Specification (TS) 3.8.1, "AC Sources-Operating, Emergency Diesel Generator Completion Time, L-PI-05-036, dated November 2 1, 2005.
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