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MONTHYEARPLA-7287, Flood Hazards Reevaluation Report PLA-72872015-03-0303 March 2015 Flood Hazards Reevaluation Report PLA-7287 Project stage: Request ML15153A1632015-06-0404 June 2015 Nuclear Regulatory Commission Plan for the Audit of PPL Susquehanna Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Susquehanna Steam Electric Station, Units 1 and 2. Project stage: Other PLA-7389, Flood Hazards Reevaluation Report, Information to Support Audit2015-09-24024 September 2015 Flood Hazards Reevaluation Report, Information to Support Audit Project stage: Request ML15288A5632015-10-0202 October 2015 NRR E-mail Capture - (External_Sender) Susquehanna: Follow-on Audit Question Project stage: Request ML15281A1562015-10-21021 October 2015 U. S. Nuclear Regulatory Commission Report for the Audit of Susquehanna Nuclear, Llc'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Susquehanna Units 1 and 2 (Tac. MF6037 Project stage: Other ML15303A3142015-11-0303 November 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR 50.54(f) Information Request -Flood Causing Mechanism Reevaluation Project stage: Other ML15239B2212015-11-0303 November 2015 Master Report - Tables 1 and 2 Project stage: Request ML15314A7472015-11-12012 November 2015 Correction to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request Flood-Causing Mechanism Reevaluation Project stage: Other 2015-11-03
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Category:Audit Plan
MONTHYEARML23010A0872023-01-11011 January 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Control Rod Technical Specifications ML22056A0122022-03-0404 March 2022 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications for Reactor Steam Dome Pressure Low Instrumentation Function Allowable Values ML21153A1372021-06-15015 June 2021 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20189A1822020-07-15015 July 2020 Regulatory Audit for License Amendment Request to Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit ML19311C7952019-11-14014 November 2019 Regulatory Audit Plan Regarding Application of Framatome Methodologies to Support Transition to Atrium 11 Fuel ML17220A3282017-08-10010 August 2017 Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15153A1632015-06-0404 June 2015 Nuclear Regulatory Commission Plan for the Audit of PPL Susquehanna Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Susquehanna Steam Electric Station, Units 1 and 2. ML14323A6802014-11-24024 November 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 2023-01-11
[Table view] 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2015 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467
SUBJECT:
NUCLEAR REGULATORY COMMISSION PLAN FOR THE AUDIT OF PPL SUSQUEHANNA, LLC'S FLOOD HAZARD REEVALUATION REPORT SUBMITTAL RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (TAC NOS. MF6037 AND MF6038)
Dear Mr. Rausch:
This letter documents the U.S. Nuclear Regulatory Commission (NRC) staff's plan to perform a regulatory audit of PPL Susquehanna, LLC's (the licensee) supporting calculations for the Flood Hazard Reevaluation Report (FHRR) submittal related to the Near-Term Task Force Recommendation 2.1, Flooding for Susquehanna Steam Electric Station, Units 1 and 2 (Susquehanna). This technical audit will be performed consistent with NRC Office of Nuclear Reactor Regulation, Office Instruction LIC-111, "Regulatory Audits," dated December 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082900195). The audit will be conducted over multiple sessions, as needed, and the NRC staff will develop an audit summary report to document its observations and conclusions within 90 days of the final audit session.
The audit will provide the NRC staff with a better understanding of the Susquehanna FHRR which was submitted on March 3, 2015 (ADAMS Accession No. ML15063A319). Specifically, the audit will provide the NRC staff with a better understanding of the analyses of the flooding hazards presented in the Susquehanna FHRR. The audit is intended to support completion of the staff's review of the FHRR and the subsequent issuance of a Staff Assessment.
The enclosed audit plan outlines the process that will allow the NRC staff to identify additional information potentially necessary for licensees to supplement their FHRRs, and resolve potential technical concerns. The details of this audit have been discussed with Mr. Mike Crowthers of your staff.
T. Rausch If you have any questions, please contact me at (301) 415-6197 or by e-mail at Tekia.Govan@nrc.gov.
Sincerely, JL(}~*-
Tekia V. Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
Audit Plan cc w/encl: Distribution via Listserv
NRC PLAN FOR THE AUDIT OF PPL SUSQUEHANNA. LLC'S FLOOD HAZARD REEVALUATION REPORT SUBMITTAL RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING FOR SUSQUEHANNA STEAM ELECTRIC STATION.
UNITS 1AND2 BACKGROUND AND AUDIT BASIS By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.54(f) "Conditions of license" (hereafter referred to as the "50.54(f) letter). The request was issued in connection with implementing lessons-learned from the 2011 accident at the Fukushima Dai-ichi nuclear power plant, as documented in The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Recommendation 2.1 of that document recommended that the staff issue orders to all licensees to reevaluate seismic and flooding for their sites against current NRC requirements and guidance. Subsequent Staff Requirements Memoranda associated with Commission Papers SECY 11-0124 and SECY-11-0137, instructed the NRC staff to issue requests for information to licensees pursuant to 10 CFR 50.54(f).
By letter dated March 3, 2015, PPL Susquehanna, LLC (PPL, the licensee) submitted its Flood Hazard Reevaluation Report (FHRR) for Susquehanna Steam Electric Station, Units 1 and 2 (Susquehanna) (Agencywide Documents Access and Management System Accession No. ML15063A319). The NRC staff has begun its review of the aforementioned submittals and plans to conduct a regulatory audit PPL to aid in its review of the licensee's FHRR.
REGULATORY AUDIT SCOPE AND METHODOLGY The areas of focus for the regulatory audit is the information contained in the Susquehanna FHRR submittal, and all associated and relevant supporting documentation used in the development of the aforementioned document including, but not limited to, methodology, process information, calculations, computer models, etc. The audit will be conducted and completed over several meetings that are to be determined, as necessary.
Enclosure
INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT The information required for the audit is the licensee's models and supporting calculations, as well as documentation related to the storm surge and site specific probable maximum precipitation analyses. Other information needs will be discussed as audit meetings are scheduled.
NRC AUDIT TEAM Title Team Member Affiliation Team Leader, NRR/JLD Tekia Govan NRC Branch Chief, NRO/DSEA Chris Cook NRC Technical Lead Nebiyu Tiruneh NRC Technical Manager Mike Willingham NRC Technical Support Various Contractors Department of Energy National Laboratory LOGISTICS The audit meetings will be coordinated with PPL staff.
DELIVERABLES The NRC team will develop an audit summary report to convey the audit results. The report will be placed in ADAMS within 90 days of the completion of the final audit session, and will be publicly available.
The information discussed in the audit may be included, fully or in part, in the development of the NRC technical staff's assessments as a result of the FHRR review.
T. Rausch If you have any questions, please contact me at (301) 415-6197 or by e-mail at Tekia.Govan@nrc.gov.
Sincerely, IRA/
Tekia V. Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
Audit Plan cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC JLD R/F RidsNRRJLD Resource RidsNrrDorllpl1-2 KSee, NRO MShams, NRR LQuinn-Willingham, NRO CCook, NRO ARivera, NRO KErwin, NRO MFranovich, NRR JBowen, NRR BHarvey,NRO VHall, NRR RidsNrrPMSusquehanna Resource ADAMS Accession No.: ML15153A163 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME TGovan Slent MS hams TGovan DATE 06/03/15 06/02/15 06/04/15 06/04/15 OFFICAL RECORD COPY