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TAC:MF5151, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B, SDV Actions (Open) TAC:MF5152, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B, SDV Actions (Open) |
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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-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-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-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-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-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-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
[Table view] |
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Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 TALEN ~
Tel. 570.542.2904 Fax 570.542.1504 ENERGY jon.franke@talenenergy.com SEP 2 1 2015 U.S. Nuclear Regulatory Commission 10 CFR 50.90 Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGES TO ADOPT TRAVELER TSTF-425 Docket Nos. 50-387 PLA-7381 and 50-388
References:
- 1. Letter PLA-7119, [Proposed Amendments to License NPF-14 and NPF-22} Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Task Force (RITSTF) Initiative 5, "dated October 27, 2014 (AccessionML14317A052).
- 2. Letter PLA-7334, "Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425, "dated July 2, 2015 (Accession ML15183A248) .
- 3. NRC Letter, "Request for Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425, (TAC Nos.
MF5151 andMF5152), "dated August 24, 2015 (AccessionML15209A974) .
The purpose of this letter is for Susquehanna Nuclear, LLC to provide the requested additional information (RAI). By Reference 1, and as supplemented by additional information in Reference 2, Susquehanna Nuclear, LLC submitted a license amendment request (LAR) to modify Susquehanna Stearn Electric Station, Units 1 and 2 (SSES)
Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program. The program will implement Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5B, Risk-Informed Method for Control of Surveillance Frequencies," (Accession ML071360456). The changes adopt an NRC approved Technical Specification Task Force (TSTF) traveler, TSTF-425, Revision 3, (Accession ML080280275).
In Reference 3, the RAI includes two questions for which responses are provided in .
Susquehanna Nuclear, LLC has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The additional infmmation provided by this submittal does not
Document Control Desk PLA-7381 affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthe1more, the additional information also does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no new regulatory commitments associated with this response.
If you have any questions or require additional information, please contact Mr. Jeffery N. Grisewood (570) 542-1330.
I declare under penalty of pe1jury that the foregoing is tme and conect.
Executed on:
7 ranke : Response to Requested Additional Information Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Attachment 1 to PLA-7381 Response to Requested Additional Information
Attachment 1 to PLA-7381 Page 1 of 4 Response to Requested Additional Information By letter dated October 27, 2014,( 1) and as supplemented by additional infmmation in a letter dated July 2, 201s,CZ> Susquehanna Nuclear, LLC submitted a license amendment request (LAR) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. The proposed amendment would modify the SSES Technical Specifications by relocating specific frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies. "< 3 > The NRC requested additional information (RAI) in a letter dated August 24, 2015.(4) This Attachment provides the requested additional information.
RAI8:
In the response to request for additional information (RAI) 3, regarding Supporting Requirement (SR) HR-B2, the licensee clarified that the intent of the finding and observation (F&O) resolution was to indicate that there is no longer any reliance on staggered testing/maintenance principles for screening purposes, and that the pre-initiator process was used for screening. The licensee's response also seems to suggest that all common mode elTors were screened out. Discuss the justification and conclusions on screening pre-initiator common mode elTors. Also, discuss the considerations and the bases for the inclusion or exclusion of modeling of common-mode elTors in the probabilistic risk assessment (PRA).
SSES Response to RAI 8:
Both common mode miscalibration events and common mode misalignment events were considered for the SSES pre-initiator Human Reliability Analysis (HRA).
(1) Letter (PLA-7119), [Proposed Amendments to License NPF-14 and NPF-22] Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification Task Force (RITSTF)
Initiative 5, "dated October 27,2014 (Accession ML14317A052) .
(2) Letter (PLA-7334), "Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425, "dated July 2, 2015 (Accession ML15183A248).
(3) Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5B, Risk-Informed Method for Control ofSurveillance Frequencies," dated April30, 2007 (Accession ML071360456).
(4) NRC Letter, "Request for Additional Information Regarding License Amendment Request to Adopt Technical Specifications TaskForce Traveler (TSTF)-425, (TAC Nos. MF5151 and MF5152),"
dated August 24, 2015 (Accession ML15209A974).
Attachment 1 to PLA-7381 Page 2 of4 For common mode miscalibrations, the pre-initiator identification process identified those calibration activities during which a common error could occur that would prevent the automatic actuation of a function required in the PRA. For example, common mode miscalibration events are included in the PRA for the critical Reactor Pressure Vessel (RPV) pressure switch channels that would fail the low pressure permissive logic required for Low Pressure Coolant Injection and Core Spray injection (i.e., A and B, A and D, Band C, etc.).
Common mode calibration activities were screened from the analysis if:
- The activities could lead to calibration errors in non-PRA systems.
- The activities could lead to calibration errors for equipment within a component's boundary (i.e., miscalibrations of sensors/instruments that are within the component boundary are inherent in the component failure data and do not require additional failure events).
- The combination of miscalibration errors does not result in critical failure of the logic. For example, for an actuation signal that requires operation of channel "A" OR "B" AND channel "C" OR "D" for success, it is not necessary to include events of common cause miscalibration of channels "A" and "D" because the signal is not failed by that combination.
For common mode misalignment errors, the pre-initiator identification process identified single activities that could result in the misalignment of a component that would prevent operation of multiple redundant trains of a system or diverse systems. For example, a misalignment was included for a spray pond retum valve, which if left closed, would result in the failure of the "A" train of Emergency Service Water (for both Units 1 & 2) and the "A" train of Residual Heat Removal Service Water (also for both Units 1 & 2).
Activities leading to misalignment/restoration errors were screened if:
- The activities were related to non-PRA systems.
- The activities were related to n01mally operating systems and operation would reveal a misalignment. Components in multi-train systems in which one train may be assumed to be normally running and the other( s) assumed to be in standby were not screened. All trains were assumed to be in standby for the pre-initiator Human Error Probability (REP) identification process.
- Position indication is available in the main control room, automatic re-alignment occurs on system initiation, a status check is perf01med on a shiftly basis, or a signal exists that would identify the misalignment. This screening rule was not applied to misalignments/restoration errors that could simultaneously impact multiple redundant trains or diverse systems.
Common mode events impacting redundant system trains or diverse systems were specifically treated in accordance with HR-A3. This SR requires the identification of work practices that "involve a mechanism that simultaneously affects equipment in either
Attachment 1 to PLA-7381 Page 3 of4 different trains of a redundant system or diverse systems (e.g., use of common calibration equipment by the same crew on the same shift, a maintenance or test activity that requires realignment of an entire system (e.g., SLCS). " The intent of the SR was viewed to focus on capturing single activities that impact redundant trains of a system or diverse systems, not multiple, separate activities that impact redundant or diverse systems, even if they are performed in an outage. Any components that could be manipulated in a way that would disable different trains of a redundant system or diverse systems should be identified through the system review and developed as events. These activities may not be screened.
Quantification of the common mode pre-initiator events was performed using the pre-initiator Accident Sequence Evaluation Program (ASEP) methodology, which is identified in Section 3.2 of NUREG-1842, "Evaluation ofHuman Reliability Analysis Methods Against Good Practices," as a valid approach for evaluating risk-significant pre-initiator events.
RAI9:
The response to RAI 4 does not discuss reflecting the current plant configuration and operating experience when considering extemal events using NEI 04-10 guidance. (The response does confirm this for the intemal events analysis.) Please explain whether evaluation of the fire risk and other extemal events supporting this application reflects, or considers, the current plant configuration and operating experience.
SSES Response to RAI 9:
By following Steps 1Oa and 1Ob of the NEI 04-10 guidance, the evaluation of fire risk and other extemal events risk supporting this application will reflect and consider the current plant configuration and operating experience. The Individual Plant Examination for Extemal Events (IPEEE) is not a living document and has not been updated to the present plant configuration and operating experience. As a result, the fire risk and other extemal event risk information from the IPEEE is limited to qualitative insights. For the surveillance test interval (STI) change evaluations, the intent is not to directly use any numerical results from the IPEEE fire studies or other extemal events, but to qualitatively assess any available information to determine the impact on the proposed surveillance interval changes, consistent with Step 1Oa of the NEI 04-10 methodology. This qualitative assessment of fire risk and other extemal event risk will include a review of applicability to the current plant configuration and operating experience. Additionally, for some STI change evaluations, per Step lOb of the NEI 04-10 methodology, qualitative reasoning and very low changes to core damage frequency (~CDF) and large
Attachment 1 to PLA-7381 Page 4 of4 early release frequency (L1LERF) results from the internal events analysis may be sufficient to support the STI change evaluation where Step 1Ob reads in part:
"Alternative evaluations for the impact from external events and shutdown events are also deemed acceptable at this point. For example, if the !:l.eDF and MERF values have been demonstrated to be very small from an internal events perspective based on detailed analysis of the impact of the SSe being evaluated for the STI change, and if it is known that the eDF or LERF impact from external events (or shutdown events as applicable) is not specifically sensitive to the sse being evaluated (by qualitative reasoning), then the detailed internal events evaluations and associated required sensitivity cases (as described in Step 14) can be used to bound the potential impact from external events and shutdown PRA model contributors. "
Qualitative evaluation of fire and external events risk in support of Step 1Ob would also include consideration of applicability to the cunent plant configuration and operating expenence.
Therefore, by following Steps 1Oa and 1Ob of the NEI 04-10 guidance, the evaluation of fire risk and other external events will reflect and consider the cunent plant configuration and operating experience.