|
|
Line 34: |
Line 34: |
| 1 The 50.54(f) letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12053A340. | | 1 The 50.54(f) letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12053A340. |
| 2 The prioritization letter is available in ADAMS under Accession No. ML12097A509. | | 2 The prioritization letter is available in ADAMS under Accession No. ML12097A509. |
| 3 The request for assistance in obtaining USAGE analysis is available in ADAMS under Accession No. | | 3 The request for assistance in obtaining USAGE analysis is available in ADAMS under Accession No. ML13274A343. |
| ML13274A343. | |
| 4 The extension request from Southern is available in ADAMS under Accession No. ML14072A486. | | 4 The extension request from Southern is available in ADAMS under Accession No. ML14072A486. |
| 5 A summary of the May 16, 2014 meeting is available in ADAMS under Accession No. ML14134A031. | | 5 A summary of the May 16, 2014 meeting is available in ADAMS under Accession No. ML14134A031. |
|
---|
Category:Letter
MONTHYEARML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the “Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 IR 05000348/20230062024-02-28028 February 2024 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2023006 and 05000364/2023006 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers IR 05000348/20230042024-02-0909 February 2024 Integrated Inspection Report 05000348/2023004 and 05000364/2023004 and Exercise of Enforcement Discretion NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers ML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter 2024-09-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2- RELAXATION OF RESPONSE DUE DATES REGARDING FLOODING HAZARD REEVALUATIONS FOR RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF THE INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT (TAC NOS.
MF3638 and MF3639)
Dear Mr. Pierce:
By letter dated March 12, 2012, 1 the Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f)
(henceforth referred to as the 50.54(f) letter). The request was issued as a part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to perform a reevaluation of all external flooding hazards using present-day guidance and methodologies.
By letter dated May 11, 2012, 2 the NRC issued a prioritization of due dates for all sites. The flooding hazard reevaluation report (FHRR) was due on March 12, 2014, for Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley).
By letter dated September 26, 2013, 3 Southern Nuclear Operating Company, Inc. (Southern, the licensee) requested NRC assistance in obtaining the U.S. Army Corps of Engineers (USACE) analysis of dams that could impact the flood levels at the Farley site. By letter dated February 28, 2014, 4 Southern requested a delay in submittal of the FHRR for Farley to within 120 days of receiving the USACE final analysis. The reason for this request is that the USACE analysis is necessary to complete the flooding hazard reevaluation (FHR) and 120 days is necessary to incorporate the results.
On May 16, 2014, 5 the NRC staff held a public meeting with Southern to discuss the requested extension. On May 21, 2014, 6 Southern provided additional information supporting its requested extension for providing the Farley FHRR.
1 The 50.54(f) letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12053A340.
2 The prioritization letter is available in ADAMS under Accession No. ML12097A509.
3 The request for assistance in obtaining USAGE analysis is available in ADAMS under Accession No. ML13274A343.
4 The extension request from Southern is available in ADAMS under Accession No. ML14072A486.
5 A summary of the May 16, 2014 meeting is available in ADAMS under Accession No. ML14134A031.
6 The May 21, 2014 letter is available in ADAMS under Accession No. ML14141A629.
C. Pierce The NRC reviewed the justification provided and considered the following factors when reviewing the new schedule:
- Southern has completed the analysis required for the Farley FHR not related to the information request to USAGE and has implemented interim actions to account for the higher than anticipated local intense precipitation event.
- As stated in the NRC's interim staff guidance (ISG) JLD-ISG-2013-01 ,7 "Guidance for Assessment of Flooding Hazards Due to Dam Failure," evaluating flooding hazards for nuclear power plants needs to include consideration of floods resulting from dam failures. The FHR for Farley needs to consider dams that are operated by various government agencies including the USAGE. The NRC has entered into an interagency agreement with the USAGE to provide the necessary information for Farley to complete its FHR. Therefore, the FHRR for Farley cannot be completed until the NRC provides the analysis of the USAGE dams to the licensee.
- As stated in NRC letter dated March 1, 2013, 8 "incomplete hazard reports that only contain an analysis of some flooding hazard mechanisms would not be of substantitive benefit for staff and would not be acceptable." Therefore, the information requested from the USAGE is necessary before an FHRR can be acceptably submitted to the NRC in compliance with the request in the 50.54(f) letter.
- The limited duration of the proposed extension (120 days after receiving the necessary information) and the fact that Farley has implemented interim actions to account for unbounded reevaluated flooding hazards support the proposed schedule.
Given these considerations, the NRC considers the revised schedule proposed by Southern to be acceptable. Accordingly, and based upon the authority granted to the Director, Office of Nuclear Reactor Regulation, the revised required response date for submitting the FHRR for Farley is 120 days after Southern receives the information from USAGE. The NRC will include the date when the Farley FHRR is due when the requested USAGE information is transmitted to the licensee. The transmittal letter will also note that if the USAGE analysis results in a higher flood hazard relative to the design basis, the NRC staff will request that, within 60 days of receipt of the USAGE analysis, Southern provide interim actions it will take or plans to take to address the higher flooding hazard.
7 JLD-ISG-2013-01 is available in ADAMS under Accession no. ML13151A153 8
NRC's March 1, 2013 letter is available in ADAMS under Accession no. ML13044A561.
C. Pierce If you have any questions regarding this matter, or if it is necessary to revise the submittal schedule, please contact your NRC project manager, Shawn Williams, at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov.
Sincerely, Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Listserv
ML14174A938 *via email **Previously concurred OFFICE NRRIJLD/JHMB/PM NRRIJLD/JHMB/LA** NRR!DORULPL2-1/PM* NRRIJLD/JHMB/BC DSENRHM1/BC*
NAME JSebrosky Slent SWilliams MMitchel CCook (KErwin for)
DATE 07/17/14 06/23/14 07/08/14 07/02/14 06/30/14 OFFICE DSENRHM2/BC* OGC NLO NRRIJLD/D NRRID NAME RKaras BHarris DSkeen DOorman DATE 06/27/14 06/27/14 07/03/14 07/17/14