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Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23334A1502023-11-30030 November 2023 NRC Request for Additional Information Re. Susquehanna Relief Request RR-02 ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information ML23013A2082023-01-13013 January 2023 Request for Additional Information ML22146A1022022-05-26026 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000387/2022404 and 05000388/2022404 ML22146A0742022-05-25025 May 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22111A3132022-04-21021 April 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22041A1562022-02-10010 February 2022 Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000387/2022013 and 05000388/2022013 ML21316A1242021-11-18018 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications ML20056E4392020-02-21021 February 2020 Ti 2515/194 Inspection Documentation Request ML20010D2012020-01-0909 January 2020 Request for Additional Information Related to Request to Allow Application of Framatome Analysis Methodologies Necessary to Support a Planned Transition to Atrium 11 Fuel Under Maximum ML19319B1922019-11-14014 November 2019 NRR E-mail Capture - RAI for Susquehanna, 1 and 2 License Amendment Request - Replace the Emergency Service Water System and Residual Heat Removal Service Water System ML19319A0092019-11-14014 November 2019 NRR E-mail Capture - Draft RAI for SSES Units 1 and 2 LAR to Replace ESW Piping ML19128A0232019-05-0707 May 2019 Request for Additional Information: Susquehanna Steam Electric Station, Units 1 and 2 License Amendment Request for ESW Piping Replacement ML18352B1832018-12-13013 December 2018 Enclosurequest for Additional Information (Letter to K. Cimorelli Request for Additional Information Regarding Susquehanna Nuclear, Llc'S Decommissioning Funding Plan Update for Susquehanna Steam Electric Station Independent Spent Fuel Stor ML17180A2002017-07-0707 July 2017 Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits ML17059D2142017-03-0606 March 2017 Susquehanna Steam Electric Station - Supplemental Information Needed for Acceptance of Requested Licensing Action Re: License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage Frequency Limits ML16251A0652016-09-0909 September 2016 Susquehanna Steam Electric Station, Unit 2 - RAI Regarding Temporary Change of Unit 2, Technical Specifications 3.7.1 & 3.8.7 to Allow Replacement of Unit 1, 480 Volt Engineered Safeguard System Load Center Transformers(CAC No. MF7298) ML16245A2052016-09-0101 September 2016 Draft Request for Additional Information Replacement of Load Center Transformers ML16243A0952016-08-30030 August 2016 Draft Request for Additional Information Application for Approval of Indirect Transfer of Control of Licenses ML16060A2302016-03-24024 March 2016 Acceptance of Requested Licensing Action License Amendment Request for Temporary Change of Unit 2 Technical Specifications 3.71 and 3.87 to Allow Replacement of Unit 1 480V Ess Load Center Transformers ML15316A5632015-11-13013 November 2015 Request for Additional Information Regarding Proposed Relief Requests for the Third 10-Year Inservice Inspection Interval(Cac Nos. MF6302 Through MF6307) ML15292A1782015-10-15015 October 2015 TSTF-425 LAR Draft 3rd RAIs ML15230A0802015-08-26026 August 2015 Request for Additional Information Regarding License Amendment Request to Adopt NEI 99-01, Revision 6, EAL Scheme Change ML15209A9742015-08-24024 August 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 ML15229A2002015-08-17017 August 2015 E-mail from J. Whited to J. Jennings SSES Draft TSTF-425 RAIs ML15229A2092015-08-17017 August 2015 SSES Draft Request for Additional Information Licensee Request to Adopt TSTF-425 ML15230A0462015-08-17017 August 2015 Draft RAIs SSES EAL Scheme Change LAR in Accordance with NEI 99-01 Rev 6 ML15183A3502015-07-0202 July 2015 SSES Relief Requests 3RR-19, 3RR-20, and 3RR-21 Draft Identified Information Insufficiencies (TAC Nos. MF6302 Through MF6307) ML15103A3962015-05-22022 May 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 (TAC Nos. MF5151 and MF5152) ML15128A5162015-05-0808 May 2015 SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15128A5092015-05-0808 May 2015 E-mail from J. Whited to D. Filchner SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15008A4702015-01-30030 January 2015 Request for Additional Information Request to Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits. ML15016A2742015-01-16016 January 2015 Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML15016A2722015-01-16016 January 2015 E-mail from J. Whited to D. Filchner Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML14343A9842015-01-0808 January 2015 Request for Additional Information Relief Request 4RR-01 ML14345A2412014-12-16016 December 2014 Request for Additional Information Request for Order Approving Indirect Transfer of Control and Conforming License Amendments ML14346A1022014-12-12012 December 2014 Draft License Transfer Revised 2nd RAIs ML14346A4022014-12-12012 December 2014 Draft RAIs Relief Request 4RR-01 ML14346A4012014-12-12012 December 2014 E-mail from J. Whited to D. Filchner Susquehanna Steam Electric Station Draft RAIs Relief Request 4RR-01 ML14346A1002014-12-12012 December 2014 E-mail from J. Whited to R. Sgarro Susquehanna Steam Electric Station Draft License Transfer Revised 2nd RAIs ML14342A8082014-12-0808 December 2014 E-mail from J. Whited to R. Sgarro (PPL) SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14342A8132014-12-0808 December 2014 SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14233A2772014-08-27027 August 2014 Request for Additional Information License Amendment Request to Change the Low Pressure Safety Limit ML14233A3392014-08-21021 August 2014 Draft RAIs for Susquehanna Steam Electric Station Units 1 and 2 License Amendment Request for Changes to the Low Pressure Safety Limits ML13298A7582014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage (TAC ME9607 and ME960) ML13298A7812014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirement 3.8.1.19 to Increase Diesel Generator Minimum Steady State Frequency (TACs ME9609. ML14013A1502014-01-31031 January 2014 Request for Additional Information Regarding Relief Requests for the Fourth 10-Year Inservice Testing Interval ML14024A4752014-01-24024 January 2014 Draft 4th IST RRs 1RR05 RAIs ML13338A4422013-12-19019 December 2013 Request for Additional Information Regarding Relief Requests for the Fourth Ten-Year Inservice Inspection Interval ML13312A9142013-12-18018 December 2013 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements 3.5.1.12 2023-11-30
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September 5, 2007Mr. Britt T. McKinneySr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THESUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
Dear Mr. McKinney:
By letter dated September 13, 2006, PPL Susquehanna, LLC submitted an application pursuantto Title 10 of the Code of Federal Regulations, Part 54, to renew the operating licenses forSusquehanna Steam Electric Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.These requests for additional information were discussed with Duane Filchner, and a mutuallyagreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4029 or via e-mail ehg2@nrc.gov
.Sincerely,/RA/Evelyn Gettys, Project ManagerLicense Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388
Enclosure:
Requests for Additional Informationcc w/encl: See next page
ML072360229OFFICELA:DLRPM:RLRA:DLRBC:RLRA:DLRNAMEIKingEGettysLLund DATE08/30/0709/04/0709/05/07 Letter to B. McKinney, from E. Gettys dated September 5, 2007
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THESUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATIONDISTRIBUTION
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YDiaz RGuzman BRogers EGettys Susquehanna Steam Electric Station, Units 1 and 2 cc:Robert A. SacconeVice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467Terry L. HarpsterGeneral Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Rocco R. SgarroManager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Walter E. MorrisseySupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Michael H. CrowthersSupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Steven M. CookManager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467Luis A. RamosCommunity Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467Bryan A. Snapp, Esq.Associate General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179Supervisor - Document Control ServicesPPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Richard W. OsborneAllegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266Director, Bureau of Radiation ProtectionPennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4Berwick, PA 18603-0035Regional Administrator, Region 1U.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406Board of SupervisorsSalem Township P.O. Box 405 Berwick, PA 18603-0035 Susquehanna Steam Electric Station, Units 1 and 2 cc:-2-Dr. Judith JohnsrudNational Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803Ms. Julie KeysNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Enclosure SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2LICENSE RENEWAL APPLICATIONREQUESTS FOR ADDITIONAL INFORMATION (RAIs)RAI 4.2.3-1License renewal application (LRA) Section 4.2.3 states, "It may be noted that ART [adjustedreference temperature] values are well below the 200 F [as] suggested in Section 3 ofRegulatory Guide 1.99 and are, thus, acceptable for the period of extended operation."
Section 3 of Regulatory Guide 1.99, Revision 2 is for new plants and is not applicable to Susquehanna Units. Unlike the pressurized-thermal-shock (PTS) screening criteria used for evaluating the pressurized water reactor RPV material reference temperatures at the end of license fluence, there is no criteria for evaluating the RPV ARTs. The significance of ARTs is considered in the pressure and temperature (P-T) limit evaluation. Please revise LRA Section 4.2.3 and the associated updated final safety analysis renewal review (UFSAR) Supplement summary description so that Section 3 of Regulatory Guide 1.99 is not referenced.RAI 4.2.4-1LRA Section 4.2.4 states that calculations were performed to develop P-T limits for both unitsfor the extended period of operation, using the 54 effective full-power year (EFPY) fluence values discussed in LRA Section 4.2.1. However, since the applicant did not include the revised P-T limits valid for 54 EFPY in the LRA for the staff review, it is inappropriate to state in LRA Section 4.2.4 that, "The 54 EFPY P-T curves for Units 1 and 2 demonstrate that there is sufficient operating margin for hydrostatic tests, heatup, cooldown, and core critical operation to the end of the period of extended operation." Please revise LRA Section 4.2.4 and its associated UFSAR Supplement summary description by taking this statement out. In addition, it is suggested to mention in the UFSAR Supplement summary description that Susquehanna Steam Electric Station (SSES) will submit the 54 EFPY P-T limits for NRC review and approval at the appropriate time to comply with Title 10 of the Code of Federal Regulations, Part 50,Appendix G.RAI 4.2.5-1In the July 28, 1998, safety evaluation report on Boiling Water Reactor Vessel and InternalsProject (BWRVIP)-05, the NRC staff concluded that examination of the RPV circumferential shell welds would need to be performed if the corresponding volumetric examinations of the RPV axial shell welds revealed the presence of an age-related degradation mechanism.
Confirm whether or not previous volumetric examinations of the RPV axial shell welds have shown any indication of cracking or other age-related degradation mechanisms in the welds.
Please also confirm whether there are any flaw evaluations performed to date on RPV flaws as a result of previous volumetric examinations of the RPVs, and, if flaw evaluations exist, why they are not considered as time-limited aging analysis (TLAAs). RAI 4.2.7-1LRA Section 4.2.7 states that the SSES RPVs are bounded by the generic analysis that isdiscussed in NEDO-10029, "An Analytical Study on Brittle Fracture of GE-BWR Vessels Subject to the Design Basis Accident," because the reference temperature nil ductility (RT NDT)shifts at 54 EFPY (35.9 °F for Unit 1 and 38.4 °F for Unit 2) are less than the RT NDT shift of 50 °Fused in the generic analysis. Please confirm whether the current licensing basis relies on the NEDO-10029 conclusions in addressing the reflood thermal shock issue and whether NEDO-10029 has been reviewed and approved by the NRC. If NEDO-10029 has been approved by the staff and utilized within the current SSES licensing basis, summarize the technical basis for determining the adequacy of this TLAA based solely on RT NDT shift (as opposed to the ART ofthe limiting material). If NEDO-10029 was not approved, please provide the report for staff review to determine the acceptance of the methodology and results for use in the extended period of operation. Further, please demonstrate that the driving force based on the plant-specific design basis accident and SSES RPV geometry is bounded by the generic analysis.RAI 4.2.7-2All recent LRAs for plants with BWRs (e.g., Monticello, Brunswick, and Browns Ferry units)addressed the issue of reflood thermal shock analysis of RPV core shroud. Please address this TLAA, or explain why this topic is not a TLAA for SSES, Units 1 and 2.RAI 4.7.3-1LRA Section 4.7.3 states that, based on BWRVIP-25, "BWR Core Plate Inspection and FlawEvaluation Guidelines," the core plate hold-down bolts will have at least 81-percent preloadremaining at 54 EFPY and, based on the GE extended power uprate (EPU) analyses of the core plate hold-down bolts, the preload at the end of 60 years would be adequate to prevent lateral motion of the core plate for the period of extended operation. This conclusion is not supported by any SSES plant-specific evaluation. Please provide the following additional information: (1)Demonstrate the applicability of the BWRVIP-25 loss of preload analysis to the SSESUnits. Identify the temperature of the bolts during the normal operation and the projected bolt neutron fluence at the end of the period of extended operation for the SSES Units. Provide a plant-specific evaluation demonstrating that the loss of preload due to stress relaxation for the SSES RPV core plate hold-down bolts is bounded by the value of 19 percent from Appendix B of BWRVIP-25.
(2)Perform a plant-specific core plate hold-down bolt analysis using the BWRVIP-25Appendix A methodology, demonstrating that the axial and bending stresses for the mean and highest loaded hold-down bolts will not exceed the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III allowable stresses for P m (primary membrane) and P m + P b (primary membrane plus bending) as a result of aplant-specific reduction in the bolt preload at the end of the extended period of operation. State clearly the assumptions on which the plant-specific analysis was
based. (3)Provide sufficient information regarding the "GE EPU analyses" on the core platehold-down bolts so that the staff can determine whether the SSES hold-down bolts are adequate to prevent lateral motion of the core plate for the period of extended operation.RAI 4.7.3-2LRA Appendix C discussed the applicant's response to BWRVIP report application action items. The BWRVIP reports addressing the TLAA regarding irradiation assisted stress corrosion cracking (IASCC) in austenitic stainless steel RPV internals are BWRVIP-25, BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines," BWRVIP-76, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines," and BWRVIP-47-A, "BWR Lower Plenum Inspection and Flaw Evaluation Guidelines." Although managing TLAA using aging management programs or other measures is stated in Appendix C in your response to BWRVIP report application action items, IASCC in austenitic stainless steel RPV internals should bediscussed in the TLAA section to build the connection between LRA Section 4.0 and Appendix C. Further, the fact that BWRVIP-47 is under the NRC staff review doesn't imply that you don't need to address it. In addition to your plant-specific evaluation using BWRVIP-76, you need to make a commitment to follow all BWRVIP-76 requirements and limitations, as adjusted by the NRC staff's safety evaluation on the BWRVIP-76 report.