Letter Sequence Response to RAI |
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Category:Code Relief or Alternative
MONTHYEARML23257A1222023-09-19019 September 2023 Authorization and Safety Evaluation for Alternative Request for Valve 251130 ML23207A1762023-08-0101 August 2023 Authorization and Safety Evaluation for Relief Request 4RR-10 ML21095A3042021-04-19019 April 2021 Relief Request 4RR-02 Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML16069A1992016-05-10010 May 2016 Relief Requests for the Third 10-Year Inservice Inspection Interval (CAC Nos. MF6302 Through MF6307) PLA-7418, Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-212015-12-10010 December 2015 Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-21 ML15183A3962015-07-10010 July 2015 Supplemental Information Needed for Acceptance of Requested Licensing Action Proposed Relief Requests for the Third Ten-Year Inservice Inspection Interval (TAC Nos. MF6302 Through MF6307) ML15098A4782015-04-28028 April 2015 Relief Requests 4RR-01: Use of a Risk-Informed Inservice Inspection Alternative for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF5097 and MF5098) ML14141A0732014-06-0909 June 2014 Relief Requests for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF2705 Through MF2714) ML14122A1972014-05-22022 May 2014 Relief Requests for the Fourth 10-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2912 and MF2915) ML13326A0022013-11-27027 November 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action Proposed Relief Requests for the Fourth Ten-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2915) ML12046A0462012-02-23023 February 2012 Relief Request No. 3RR-18, Regarding Relief from the Requirements of the ASME Code for Successive Inspections PLA-5960, Relief Requests 1RR06 and 2RR06 for Third Ten-Year Interval Inservice Testing Program Plans2005-09-29029 September 2005 Relief Requests 1RR06 and 2RR06 for Third Ten-Year Interval Inservice Testing Program Plans ML0519903302005-07-28028 July 2005 Code Relief, Third 10-Year Inservice Inspection Interval Program Plan ML0512205682005-06-22022 June 2005 Relief from American Society of Mechanical Engineers (ASME) Code, Section XI, Appendix Viii, Supplement 11 Requirements and Code Case N-504-2 and N-638 Requirements ML0503202502005-02-0101 February 2005 Third 10-Year Inservice Inspection Interval Program Plan ML0503104062005-01-31031 January 2005 Relief for Qualification Requirements for Dissimilar Metal Piping Welds (Tac Nos. MC4027 and MC4028) PLA-5837, Response to Request for Additional Information from NRC on Proposed Relief Request Nos. RR-01, RR-02, RR-04, & RR-05 to the Third Ten-year In-service Testing Program for Pumps and Valves for Susquehanna Ses Units 1 & 22004-12-0606 December 2004 Response to Request for Additional Information from NRC on Proposed Relief Request Nos. RR-01, RR-02, RR-04, & RR-05 to the Third Ten-year In-service Testing Program for Pumps and Valves for Susquehanna Ses Units 1 & 2 ML0426800782004-09-24024 September 2004 Third 10-Year Inservice Inspection Interval Program Plan ML0427303382004-09-20020 September 2004 Third Ten Year Inservice Inspection Interval Request for Relief No. 04-ON-006 PLA-5806, Proposed Revision to Relief Requests Irroi and 2RR01 for Proposed Third Ten-year Interval Inservice Testing Program Plans2004-09-10010 September 2004 Proposed Revision to Relief Requests Irroi and 2RR01 for Proposed Third Ten-year Interval Inservice Testing Program Plans PLA-5783, Proposed Relief Request No. 3RR-13 to the Third 10-year Inservice Inspection Program for Plant Units 1 and 2 PLA-57832004-07-14014 July 2004 Proposed Relief Request No. 3RR-13 to the Third 10-year Inservice Inspection Program for Plant Units 1 and 2 PLA-5783 PLA-5744, Proposed Relief Request No. 31 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1, PLA-57442004-04-0808 April 2004 Proposed Relief Request No. 31 to the Second 10-Year Inservice Inspection Program for Susquehanna Ses Unit 1, PLA-5744 ML0304404092003-02-13013 February 2003 Relief Request for Authorization to Use Sample Disassembly and Inspection Program as an Alternative to the ASME Code, Section XI, Requirements PLA-5543, Relief Request No. RR-35 to Inservice Inspection Plan for Pump and Valve Operational Testing for Units 1 & 22002-11-27027 November 2002 Relief Request No. RR-35 to Inservice Inspection Plan for Pump and Valve Operational Testing for Units 1 & 2 2023-09-19
[Table view] Category:Letter type:PLA
MONTHYEARPLA-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) 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 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) 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 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 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) 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 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 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) 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) 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 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) 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 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 PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) PLA-8036, Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-80362022-11-30030 November 2022 Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-8036 PLA-8035, Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-80352022-11-0808 November 2022 Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-8035 PLA-8031, Emergency Plan Revision 66 (PLA-8031)2022-11-0707 November 2022 Emergency Plan Revision 66 (PLA-8031) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-8019, Nd Refueling Outage Owner'S Activity Report, PLA-80192022-07-13013 July 2022 Nd Refueling Outage Owner'S Activity Report, PLA-8019 PLA-8013, Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-80132022-06-27027 June 2022 Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-8013 PLA-8012, 10 CFR 50.46 Annual Report2022-06-10010 June 2022 10 CFR 50.46 Annual Report PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)2022-05-23023 May 2022 Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005) PLA-8001, Radiation Exposure Information and Reporting System - PLA-80012022-04-28028 April 2022 Radiation Exposure Information and Reporting System - PLA-8001 PLA-7986, 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-79862022-04-26026 April 2022 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-7986 PLA-7987, Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987)2022-04-26026 April 2022 Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987) PLA-7985, Annual Radiological Environmental Operating Report2022-04-22022 April 2022 Annual Radiological Environmental Operating Report PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7995, Property Insurance Program (PLA-7995)2022-03-30030 March 2022 Property Insurance Program (PLA-7995) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7991, Proof of Financial Protection and Guarantee of Payment of Deferred Premium2022-03-24024 March 2022 Proof of Financial Protection and Guarantee of Payment of Deferred Premium PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 2024-01-04
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARPLA-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-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) PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8013, Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-80132022-06-27027 June 2022 Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-8013 PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)2022-05-23023 May 2022 Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005) PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7865, Response to Request for Additional Information Regarding Proposed License Amendment Requesting Revision to the Dose Consequence Analysis for a Loss of Coolant Accident (PLA-7865) Loss of Coolant Accident2020-06-0202 June 2020 Response to Request for Additional Information Regarding Proposed License Amendment Requesting Revision to the Dose Consequence Analysis for a Loss of Coolant Accident (PLA-7865) Loss of Coolant Accident PLA-7853, Ninety-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-78532020-04-0101 April 2020 Ninety-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7853 PLA-7841, Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies2020-02-0606 February 2020 Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies PLA-7830, Response to Second Request for Additional Information Regarding Proposed License Amendment Requesting a Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping2019-12-0909 December 2019 Response to Second Request for Additional Information Regarding Proposed License Amendment Requesting a Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping PLA-7793, Response to Request for Additional Information Regarding Proposed License Amendment Requesting a Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping2019-06-0303 June 2019 Response to Request for Additional Information Regarding Proposed License Amendment Requesting a Temporary Change to the Technical Specifications to Allow Replacement of Emergency Service Water System Piping PLA-7704, Response to Generic Letter 2016-01, Request for Supplemental Information2018-05-24024 May 2018 Response to Generic Letter 2016-01, Request for Supplemental Information PLA-7701, Response to NRC Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examination.2018-04-11011 April 2018 Response to NRC Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examination. PLA-7673, Proposed Amendment to Licenses NPF-14 and NPF-22: Response to Request for Additional Information and Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-76732018-02-16016 February 2018 Proposed Amendment to Licenses NPF-14 and NPF-22: Response to Request for Additional Information and Supplement to Application to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control PLA-7673 PLA-7655, Response to Request for Additional Information, (CAC Nos. MF9131 and MF9132) PLA-76552017-12-0404 December 2017 Response to Request for Additional Information, (CAC Nos. MF9131 and MF9132) PLA-7655 PLA-7619, Response to Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits2017-08-0404 August 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits PLA-7583, Response to NRC Request for Supplemental Information for License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits (PLA-7583)2017-03-21021 March 2017 Response to NRC Request for Supplemental Information for License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits (PLA-7583) PLA-7518, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2016-10-31031 October 2016 Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. PLA-7537, Response to Request for Additional Information License Amendment Request Extending Completion Times in Support of 480V Ess Load Center Transformer Replacements2016-10-10010 October 2016 Response to Request for Additional Information License Amendment Request Extending Completion Times in Support of 480V Ess Load Center Transformer Replacements ML16097A4872016-04-0606 April 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Temporary Change of Technical Specifications 3.7.1 and 3.8.7, Applicable Drawings PLA-7418, Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-212015-12-10010 December 2015 Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-21 PLA-7406, Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-4252015-11-11011 November 2015 Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425 ML15296A0602015-10-16016 October 2015 Enclosure 3, Revised (Clean) Copy of the SSES EAL Basis Document Which Includes the Changes Made in Enclosure 2 ML15296A0592015-10-16016 October 2015 Enclosure 1, Response to NRC Request for Additional Information Regarding License Amendment Request to Adopt Nuclear Energy Institute 99-0 1, Revision 6 and Enclosure 2, Mark-up of the Changes Made to the SSES EAL Basis.. ML15296A0532015-10-15015 October 2015 Enclosure 4 to PLA-7399 Revised (Clean) Copy of the SSES EAL Basis Document ML15296A0522015-10-15015 October 2015 Attachments 1 Through 9 - EP-RM-004 to Enclosure 3 to PLA-7399 Mark-up of Proposed Additional Changes Made to the SSES EAL Basis Document ML15296A0502015-10-15015 October 2015 Enclosures 1 and 2 to PLA-7399 - List of Proposed Additional Changes to the Susquehanna Steam Electric Station Emergency Action Level Basis Document and Mark-up of Proposed Additional Changes Made to the SSES EAL Comparison Matrix (Revision PLA-7399, Proposed Additional Changes to the SSES Emergency Plan Basis Document Since Submittal of Response to NRC Request for Additional Information PLA-73992015-10-15015 October 2015 Proposed Additional Changes to the SSES Emergency Plan Basis Document Since Submittal of Response to NRC Request for Additional Information PLA-7399 PLA-7389, Flood Hazards Reevaluation Report, Information to Support Audit2015-09-24024 September 2015 Flood Hazards Reevaluation Report, Information to Support Audit PLA-7381, Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-4252015-09-21021 September 2015 Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425 PLA-7371, Response to Request for Supplemental Information for the Third Interval Relief Requests 3RR-19, 3RR-20, and 3RR-212015-08-0606 August 2015 Response to Request for Supplemental Information for the Third Interval Relief Requests 3RR-19, 3RR-20, and 3RR-21 PLA-7334, Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-4252015-07-0202 July 2015 Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425 ML18024A1091978-09-0808 September 1978 Letter Attaching a Schedule for Responses to NRC Question List of June 5, 1978 ML18026A1161978-08-31031 August 1978 Letter Responding to the Letter of May 17, 1978 Enclosing Information for Antitrust Review of Operating License. ML18025A5151978-08-31031 August 1978 Letter Regarding Information for Antitrust Review of Operating License Application ML18024A0921978-04-14014 April 1978 Letter Responding to the Commission Request for Additional Information with a Schedule for Response on Containment ML18024A0891978-03-31031 March 1978 Letter Replying to the Questionnaire Contained in the December 6, 1977 Letter and Attaching an Updated Response for Unit 1 and a Complete Response for Unit 2 ML18024A0851978-03-0707 March 1978 Letter Regarding the Commission Letter of February 15, 1978 Containing the Staff Position on the Use of Austenitic Stainless Steel and Advising That PP&L Will Provide a Response by September 1, 1978 ML18025A2481977-06-14014 June 1977 Letter Submitting Additional Information Relative to the Commission'S Previous Request to Establish a Cold Weather Concrete Freeze-Protection Period of Three Days ML18025A2611977-01-19019 January 1977 Letter Documenting Responses to Questions Given to Mr. Singh Bawa of the NRC from Pp&L'S Mr. E.D. Testa in Telephone Conversations on 1/17/1977 and 01/18/1977 ML18025A2641976-12-30030 December 1976 Letter Responding to Letters Requesting That Certain Information Be Submitted to Address Anticipated Transients Without Scram (ATWS) for SSES Including Analysis and Justification of the GE Analysis Model ... ML18023B4951976-11-18018 November 1976 Letter Responding the November 3, 1976 Letter with Answer to Four Questions on the Susquehanna-Siegfried 500 Kv Line as Indicated in Amendment 5 and Attaching PA Dept. of Environmental Resources Approval for the Crossing ... ML18023A9051976-11-18018 November 1976 Response to Four Questions on the Susquehanna-Siegfried 500 Kv Line ML18025A4871976-10-15015 October 1976 Responses to Questions with Attached Drawings and Maps ML18023B4961976-10-15015 October 1976 Letter Responding to the October 6, 1976 Letter Requesting Additional Information on SSES Transmission Lines ML18025A2741976-09-0909 September 1976 Letter Responding to the Commission Letter of August 9, 1976 Relating to Annulus Pressurization and Cracks in the Feedwater Nozzle Blend Radii ML18025A4951975-06-0505 June 1975 Letter Responding to the April 17, 1975 Letter Requesting Additional Information Relative to the Design of the Containment for SSES and Attaching the Mark II Containment Program and Schedule ML18023A7651975-05-13013 May 1975 Letter Responding to NRC Letters Dated February 18, 1975 and March 14, 1975 Containing NRC Staff Positions ML18025A2971975-05-0808 May 1975 Letter Responding to Letters Dated April 17, 1975 and April 23, 1975 and Informing the NRC That a Schedule and Program for Resolution of This Matter Is Being Developed in Conjunction with Other Utilities Owning Mark II ... ML18025A5711975-05-0808 May 1975 Pennsylvania Power & Light'S 05/08/1975 Response to Request for Additional Information Mark II Containment Designs to Account for Suppression Pool Hydrodynamic Loads That Occur During Coolant Loss & Safety Valve Discharge 2024-01-04
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Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard TALEN ~
Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542 .1504 ENERGY jon.franke@talenenergy.com DEC .1 0 2DJ~
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON FOR THE THIRD INTERVAL RELIEF REQUESTS 3RR-19, 3RR-20 AND 3RR-21 Docket Nos. 50-387 PLA-7418 and 50-388
References:
I. Letter PLA-7338, "End of Interval ReliefRequests [3RR-19, 3RR-20 and 3RR-21} for Third Inservice Inspection Interval, "dated May 28, 2015 (Accession ML15148A774).
- 2. Letter PLA-7371, "Response to Request for Supplemental Information for the Third Interval ReliefRequests 3RR-19, 3RR-20 and 3RR-21 "dated August 6, 2015 (Accession ML15233A089).
- 3. NRC Letter, "Request for Additional Information Regarding Proposed ReliefRequests for the Third 10-Year Inservice Inspection Interval, (CAC Nos. MF6302 Through MF6307), "dated November 13, 2015 (Accession ML15316A563).
The purpose of this letter is for Susquehanna Nuclear, LLC to provide the requested additional information (RAI). With Reference 1, and as supplemented by additional information in Reference 2, Susquehanna Nuclear, LLC submitted requests in accordance with 10 CR 50.55(a)(g)(5)(iii), which involve determinations of impracticality that apply to certain required examinations for the third 10-year Inservice Inspection (IS I) Interval.
Their examinations demonstrated limitations experienced when attempting to comply with the required Code requirements for components described by these requests.
In Reference 3, the RAI includes the question RAI 1 about request 3RR-20. A response is provided in Attachment 1.
There are no new regulatory commitments associated with this response.
If you have any questions or require additional information, please contact Mr. Jas ennings (570) 542-3155 .
. A. Franke
Document Control Desk PLA-7418 : Response to Requested Additional Infmmation Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. M. Shields, P A DEP/BRP
Attachment 1 to PLA-7418 Response to Requested Additional Information
Attachment 1 to PLA-7418 Page 1 of 1 Response to Requested Additional Information
RAI 1
In Relief Request No. 3RR-20, the achieved examination coverage for weld DG-DH is 7.7 percent for SSES, Unit 1, during the third 10-year lSI interval. The NRC staff notes that the DG-DH achieved examination coverage is 23.7 percent for both SSES units for all previous 10-Year lSI Intervals for this weld. Please explain why the achieved examination coverage decreased from 23.7 percent to 7.7 percent for weld DG-DH for SSES, Unit 1, during the third 10-year lSI interval.
Response to RAI 1:
Susquehanna Nuclear, LLC has not determined the cause for the discrepancy between Unit 1 and 2 coverage obtained for the DG and DH Bottom Head Dollar Side Plate welds. Based on the documentation provided under the examination datasheet, (e.g.,
limited due to bottom head penetrations), the differences may have resulted from physical personnel limitations and/or the measurements taken from the covered area. With no cause for the apparent discrepancy determined, these differences in the obtained examination coverage are entered into the station's Corrective Action Program. This will provide an oppmiunity to investigate the cause further, by performing additional examination. This additional examination of the DG and DH welds will be done in an upcoming Unit 1 refueling outage, in Spring 2016. No compensatory measures are required. The examinations previously performed on the DG and DH welds in Unit 1 resulted in examination coverage of23.7 percent, which have remained consistent with the third Interval Unit 2 coverage. No relevant indications have been observed in any of these previous examinations resulting in the 23.7 percent Code volume achieved for the DG and DH Bottom Head Dollar Side Plate welds. This shows there is no history of indications detected from any of the previous examinations.
Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard TALEN ~
Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542 .1504 ENERGY jon.franke@talenenergy.com DEC .1 0 2DJ~
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON FOR THE THIRD INTERVAL RELIEF REQUESTS 3RR-19, 3RR-20 AND 3RR-21 Docket Nos. 50-387 PLA-7418 and 50-388
References:
I. Letter PLA-7338, "End of Interval ReliefRequests [3RR-19, 3RR-20 and 3RR-21} for Third Inservice Inspection Interval, "dated May 28, 2015 (Accession ML15148A774).
- 2. Letter PLA-7371, "Response to Request for Supplemental Information for the Third Interval ReliefRequests 3RR-19, 3RR-20 and 3RR-21 "dated August 6, 2015 (Accession ML15233A089).
- 3. NRC Letter, "Request for Additional Information Regarding Proposed ReliefRequests for the Third 10-Year Inservice Inspection Interval, (CAC Nos. MF6302 Through MF6307), "dated November 13, 2015 (Accession ML15316A563).
The purpose of this letter is for Susquehanna Nuclear, LLC to provide the requested additional information (RAI). With Reference 1, and as supplemented by additional information in Reference 2, Susquehanna Nuclear, LLC submitted requests in accordance with 10 CR 50.55(a)(g)(5)(iii), which involve determinations of impracticality that apply to certain required examinations for the third 10-year Inservice Inspection (IS I) Interval.
Their examinations demonstrated limitations experienced when attempting to comply with the required Code requirements for components described by these requests.
In Reference 3, the RAI includes the question RAI 1 about request 3RR-20. A response is provided in Attachment 1.
There are no new regulatory commitments associated with this response.
If you have any questions or require additional information, please contact Mr. Jas ennings (570) 542-3155 .
. A. Franke
Document Control Desk PLA-7418 : Response to Requested Additional Infmmation Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. M. Shields, P A DEP/BRP
Attachment 1 to PLA-7418 Response to Requested Additional Information
Attachment 1 to PLA-7418 Page 1 of 1 Response to Requested Additional Information
RAI 1
In Relief Request No. 3RR-20, the achieved examination coverage for weld DG-DH is 7.7 percent for SSES, Unit 1, during the third 10-year lSI interval. The NRC staff notes that the DG-DH achieved examination coverage is 23.7 percent for both SSES units for all previous 10-Year lSI Intervals for this weld. Please explain why the achieved examination coverage decreased from 23.7 percent to 7.7 percent for weld DG-DH for SSES, Unit 1, during the third 10-year lSI interval.
Response to RAI 1:
Susquehanna Nuclear, LLC has not determined the cause for the discrepancy between Unit 1 and 2 coverage obtained for the DG and DH Bottom Head Dollar Side Plate welds. Based on the documentation provided under the examination datasheet, (e.g.,
limited due to bottom head penetrations), the differences may have resulted from physical personnel limitations and/or the measurements taken from the covered area. With no cause for the apparent discrepancy determined, these differences in the obtained examination coverage are entered into the station's Corrective Action Program. This will provide an oppmiunity to investigate the cause further, by performing additional examination. This additional examination of the DG and DH welds will be done in an upcoming Unit 1 refueling outage, in Spring 2016. No compensatory measures are required. The examinations previously performed on the DG and DH welds in Unit 1 resulted in examination coverage of23.7 percent, which have remained consistent with the third Interval Unit 2 coverage. No relevant indications have been observed in any of these previous examinations resulting in the 23.7 percent Code volume achieved for the DG and DH Bottom Head Dollar Side Plate welds. This shows there is no history of indications detected from any of the previous examinations.