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MONTHYEARML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. Project stage: Request ML1000500852010-01-0606 January 2010 Notice of Forthcoming Pre-Submittal Meeting (Conference Call) with Exelon Generation Co, LLC, to Discuss Limerick, Units 1 & 2, Proposed Technical Specification Amendment Re Change to High Pressure Coolant Injection Isolation Differential.. Project stage: Request ML1002605512010-02-0303 February 2010 Summary of Pre-Application Meeting with Exelon to Discuss Proposed High Pressure Coolant Injection Isolation Setpoint Change License Amendment Request Project stage: Meeting ML1002010322010-02-0303 February 2010 Meeting Handouts for January 21, 2010 Pre-Submittal Meeting Project stage: Request ML1005701342010-02-25025 February 2010 Acceptance Review of LAR to Apply Leak-Before-Break Methodology (TAC Nos. ME2976 and ME2977 Project stage: Acceptance Review ML1011802112010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1011708332010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1011708142010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generation Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1015506682010-06-10010 June 2010 Request for Additional Information Related to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-before-Break Project stage: RAI L-PI-10-077, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Additional ...2010-07-23023 July 2010 Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Additional ... Project stage: Supplement L-PI-10-085, Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology2010-08-20020 August 2010 Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology Project stage: Response to RAI L-PI-10-094, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI2010-10-0808 October 2010 Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI Project stage: Supplement ML1032803982010-12-14014 December 2010 RAI, Related to Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of LBB Methodology Project stage: RAI L-PI-11-006, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI2011-01-14014 January 2011 Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI Project stage: Supplement L-PI-11-019, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Requests for Clarification2011-02-23023 February 2011 Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Requests for Clarification Project stage: Supplement L-PI-11-038, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology2011-04-0606 April 2011 Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Project stage: Supplement ML1120106962011-07-22022 July 2011 RAI, Related to Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Project stage: RAI L-PI-11-070, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI2011-08-0909 August 2011 Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI Project stage: Supplement ML1122008562011-10-27027 October 2011 Operating Plant, Units 1 and 2 - Issuance of Amendments Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Project stage: Approval 2010-06-10
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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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Xcel Energy' AUG 2 0 2010 L-PI-10-085 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 Clarification of Responses to Requests for Additional lnformation Regardinq a License Amendment Request for Certain Applications of Leak-Before-Break Methodologv (TAC Nos. ME2976 and ME29771
References:
- 1. Letter from Northern States Power Company, a Minnesota corporation, to the Nuclear Regulatory Commission, "Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures From the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Request for Additional lnformation (TAC Nos. ME2976 and ME2977),11L-PI-10-077, dated July 23, 2010, ADAMS Accession Number ML102040612.
- 2. Letter from Northern States Power Company, a Minnesota corporation, to the Nuclear Regulatory Commission, "License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures From the Licensing Basis Based Upon Application of Leak-Before-Break Methodology," L-PI-09-134, dated December 22, 2009, ADAMS Accession Number M L I 00200129.
This letter provides clarifications to information provided in Reference 1, regarding the application of Leak-Before-Break (LBB) methodology to piping systems attached to the reactor coolant system at the Prairie Island Nuclear Generating Plant (PINGP). In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, submitted responses to a Request for Additional lnformation (RAI) from the Nuclear Regulatory Commission (NRC) regarding the LBB License Amendment Request (LAR) submitted in Reference 2.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 During a subsequent telephone conference with the NRC Staff on August 5, 2910, NSPM agreed to clarify the responses to two RAI questions regarding the LBB supporting analyses. The clarifying information is provided in Enclosure 1. NSPM submits this clarification in accordance with the provisions of 10 CFR 50.90.
The information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in Reference 2.
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 Sam Chesnutt at 651-267-7546.
Summaw 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 AUG 2 0 2010 Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
4 ENCLOSURE 1 CLARIFICATION OF RESPONSES TO A REQUEST FOR ADDITIONAL INFORMATION REGARDING APPLICATION OF LEAK-BEFORE-BREAK METHODOLOGY TO PIPING ATTACHED TO THE REACTOR COOLANT SYSTEM AT THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT This enclosure clarifies information previously provided by the Northern States Power Company, a Minnesota corporation (NSPM) doing business as Xcel Energy, in a letter dated July 23, 2010 (ADAMS Accession Number MLI 02040612). This information supports a License Amendment Request (LAR) to apply Leak-Before-Break (LBB) methodology to piping attached to the reactor coolant system (RCS) at the Prairie Island Nuclear Generating Plant (PINGP).
2 The subject LAR was submitted by NSPM on December 22,2009 (ADAMS Accession Number L
d MLI 00200129), and the Nuclear Regulatory Commission (NRC) Staff issued a Request for I Additional Information (RAI) in a letter dated June 10, 2010 (ADAMS Accession Number i[ ML101550668). NSPM's July 23, 2010 letter cited above provided responses to the NRC's RAI.
r During a subsequent telephone conference on August 5, 2010, the NRC requested further 1 clarification of two RAls, which are addressed as follows (RAI designations are consistent with 8
the NRC's June 10, 2010 letter):
RAI E3-3.
Summarv of Original RAI:
I This RAI addresses the PINGP Unit 2 Pressurizer Surge Line weld overlay and the analysis provided with the LAR as Enclosure 3, Structural Integrity Associates evaluation SIA 0900634.402, "Updated Leak-Before-Break (LBB) Report for Prairie lsland Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle." The original RAI requested justification for not combining thermal stratification loads with safe shutdown earthquake (SSE) loads in Table 4-2 of Enclosure 3. NSPM's response indicated that the duration of the transients (e.g., heatup) that cause large stratification loads is relatively short and the likelihood of an SSE during those transients is extremely low. Therefore, it is reasonable to use the larger of the two loads in the LBB evaluation.
Request for Clarification:
The licensee stated that thermal stratification loads are not added to safe shutdown earthquake (SSE) because of the low probability of these two events occurring at the same time. A regulatory argument would be that the thermal stratification loads are not added to the SSE load because the ASME Code does not require the subject load combination. Absence of ASME Code permitting subject loads not to be combined, the thermal stratification loads should be combined with the SSE loads. Please address the staff's concern.
NSPM Clarification Response:
The ASME Boiler and Pressure Vessel Code does not specify loads or load combinations for design of Class 1 components. Rather, the loads and load combinations are specified in the Design Specification for the component. Moreover, the PINGP Unit 2 pressurizer surge line was designed in accordance with USA Standard (USAS) B31. I , Code for Pressure Piping -
Power Piping, 1967, which also does not specify loads or load combinations for upset, emergency, or faulted conditions. For the PINGP Unit 2 pressurizer surge line, the loads and
Enclosure 1 NSPM LBB-Clarification of RAI Responses load combinations are described in USAR Table 12.2-13, "Loading Combinations and Stress Limits: Pressure Piping in Accordance with USAS 831.1,"The Table 12 2-13 and the discussion in USAR Section 12.2.1, "Design Basis,"do not identify thermal stratification as a design basis load for the pressurizer surge line. Therefore, thermal stratification has not been combined with other loads for design basis piping analyses.
Thermal stratification has been considered in the analysis in Enclosure 4 to the LBB LAR to address fatigue concerns, as were described in Bulletin 88-1 1, but these loads have not been combined with SSE loads.
RAI E4-4.
Summarv of Orisrinal RAI:
This RAI addresses the Unit 2 Pressurizer Surge Line and the analysis provided with the LAR as Enclosure 4, Westinghouse evaluation WCAP-15379, "Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Prairie Island Unit 2 Nuclear Plant." The original RAI noted that Section 4.4 of WCAP-15379 identified three normal operation cases (A, B, C) and four faulted load cases (D through G), and questioned why load combinations AIE, AIG, BID, CID, CIE, and CIF were not evaluated. The RAI response described each of these combinations and stated that they would not be logical combinations.
Request for Clarification:
The licensee provided the reason why load combinations of AIE, AIG, BID, CID, CIE, and CIF are not considered in the LBB evaluation. The licensee's reason does not explain exactly why the load combinations are not considered. Please provide additional technical basis.
NSPM Clarification Response:
As described in Section 4.4 of the analysis in Enclosure 4 to the LBB LAR, the evaluation considers cracks or flaws in the RCS piping that would result in a 2 gpm leak (leakage flaw size), and then evaluates the stability of these flaws during various faulted conditions. Stability evaluations determine the flaw size that would become unstable (critical flaw size) and the analysis demonstrates that there is a margin of at least two between the leakage flaw size and the critical flaw size.
The analysis evaluates three different operating conditions to determine the leakage flaw size.
The applicable loads for these three conditions, Cases A, B, and C, are identified in Table 4-2 on page 4-5 of LAR Enclosure 4. These cases include various combinations of thermal expansion, thermal stratification, and heatuplcooldown loads.
The analysis then evaluates various faulted conditions to determine the critical flaw size at which point the leak would no longer be stable and a rupture could occur. The loads for these faulted conditions, Cases D, E, F, and GI are also shown in Table 4-2 on page 4-5 of LAR . These faulted cases include various combinations of safe shutdown earthquake (SSE), thermal expansion, thermal stratification, and heatuplcooldown loads.
The analysis in LAR Enclosure 4 combines the leak detection load cases (A, B, and C) and the critical flaw load cases (D, E, F, and G) to determine whether the crack producing the leak will remain stable for various normal and postulated faulted conditions. For example, if a leak were detected during normal full power operations without thermal stratification (Case A), the plant Page 2 of 3
Enclosure 1 NSPM LBB-Clarification of RAI Responses could then potentially experience an SSE (Case D), and the load combination AID is evaluated in the analysis as shown in Table 4-3, page 4-6 sf LAR Enclosure 4.
Load combinations that the plant would not encounter before a detected flaw could be repaired were not evaluated in the analysis. Examples of these combinations include the following:
The existence of thermal stratification conditions should be the same for both leak detection evaluations and stability evaluations under faulted conditions (SSE), because factors such as piping configurations and flow rates that affect thermal stratification would not be affected by an SSE event. That is, combinations AID and BIE are logical combinations, but N E and BID are not. Also, as shown below, combinations N E and BID are bounded by other combinations.
h If a leak is detected during heatup conditions described by Case C, and the leak is found L
to be through a nonisolable fault in the RCS pressure boundary, the PlNGP Technical E
f Specifications would preclude the operating mode changes that would result in Cases D f or E, which include normal operating temperature and pressure conditions. Based on
! this, combinations CID and CIE need not be considered.
h e In addition, operating conditions where leakage flaw sizes would be bounded by other E conditions were not evaluated in the analysis. Examples of combinations that are bounded by other combinations include the following:
The leakage flaw from Case A would be bounded by a leakage flaw in Case B, as shown in Table 5-1 on page 5-5 of LAR Enclosure 4. Therefore, load combinations N E and N G are bounded by load combinations BIE and BIG.
The critical flaw for Case F is bounded by the critical flaw for Case G, as shown by the critical flaw sizes in Table 5-2 on page 5-5 of LAR Enclosure 4. Therefore, combination CIF is bounded by load combination CIG.
The critical flaw size for Case D is bounded by the critical flaw for Case G, as shown by the critical flaw sizes in Table 5-2 on page 5-5 of LAR Enclosure 4. Therefore, combination BID is bounded by load combination BIG.
The completeness of the load combinations selected for evaluation in the LAR analysis can also be seen by comparing the leakage flaw sizes and critical flaw sizes shown in Tables 5-1 and 5-2 on page 5-5 of Enclosure 4 to the LBB LAR. From Table 5-1, it can be seen that Case B results in the largest leakage flaw size. From Table 5-2, it can be seen that Case G results in the shortest critical flaw length. The margin to failure is determined by ratioing the leakage flaw length to the critical flaw length and, as shown on Table 7-1, page 7-2, the most limiting ratio of Case B to Case G well exceeds the factor of 2.
Based on the above, the load combinations evaluated in the LAR Enclosure 4 analysis address a credible range of conditions under which a postulated RCS leak would be detected, and the range of conditions that could be encountered until the leak could be repaired. The load combinations evaluated in the analysis conservatively bound other combinations and there is no need to evaluate combinations N E , A/G, BID, CID, CIE, or CIF in the LBB analysis.
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