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Category:Memoranda
MONTHYEARML23146A1672023-05-31031 May 2023
Public Meeting Summary2022 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50?348, and 50?364 Meeting Number 20230610
ML22108A1382022-04-18018 April 2022
Annual Assessment Public Meeting Summary
ML21280A2962021-10-22022 October 2021
Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150)
ML21124A1232021-05-0404 May 2021
April 27, 2021, Public Meeting Summary Joseph M. Farley Nuclear Plant Units 1 and 2, Edwin I. Hatch Nuclear Plant Units 1 and 2, Docket No. 50-348, 50-364, 50-321, 50-366, Meeting Number ML21117A030
ML20154K7242020-06-0202 June 2020
EOC Meeting Summary
ML19149A4222019-05-29029 May 2019
Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361
ML18337A0422018-12-0303 December 2018
Reissue- Farley 2019 Exam Corporate Notification Letter
ML17104A1382017-04-14014 April 2017
Summary of Meeting to Discuss the Annual Assessment of Farley Nuclear Plant, Units 1 and 2
ML16138A6512016-06-0202 June 2016
Audit of Supporting Design, Licensing & Other Documents Related to License Amendment Requests to Support the Adoption of Technical Specification Task Force Traveler 312
ML16126A0812016-05-0505 May 2016
Summary of Public Meeting with Joseph M. Farley, Units 1 and 2
ML16103A5722016-04-21021 April 2016
Transmittal of Final Farley Nuclear Plant Unit 2, Accident Sequence Precursor Analysis
ML16097A6022016-04-0808 April 2016
Audit of Supporting Design, Licensing and Other Documents Related to License Amendment Requests to Support Adoption of Technical Specification Task Force Traveler 312
ML15253A4032016-03-11011 March 2016
Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants
ML15120A5942015-04-30030 April 2015
Summary of Public Meeting to Discuss 2014 Annual Performance Assessment of the Joseph M. Farley Nuclear Plant
ML15055A5622015-02-26026 February 2015
Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Joseph M. Farley Nuclear Plant, Units 1 and 2
ML14197A5932014-08-0606 August 2014
June 26, 2014, Summary of Category 1 Public Meeting with Southern Nuclear Operating Company to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1
ML14133A0392014-06-0303 June 2014
Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, and Southern Nuclear Company to Discuss Dam Failure for the Joseph Farley Nuclear Plant
ML14115A4052014-04-25025 April 2014
2013 End of Cycle Farley Public Meeting Summary Memo
ML14066A0472014-03-0707 March 2014
Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742
ML14017A3712014-01-17017 January 2014
Special Inspection Charter to Evaluate the Failure of B Train Solid State Protection System Operability Surveillance Test at Farley Unit 2
ML13067A2692013-03-11011 March 2013
03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2
ML13050A2862013-02-22022 February 2013
3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology
ML11208B3162011-07-28028 July 2011
Notice of Closed Meeting with the Southern Nuclear Operating Company, Inc. to Discuss Plant Security Projects and Actions for Upcoming Inspection Activities at the Joseph M. Farley Nuclear Plant
ML1108105442011-03-22022 March 2011
Notice of Cancelled Forthcoming Meeting with Southern Nuclear Operating Company, Inc. (Snc), to Discuss NFPA 805 License Amendment for Joseph M. Farley Nuclear Plant, Units 1 and 2
ML1104804052011-03-0707 March 2011
Notice of Forthcoming Meeting with Southern Nuclear Operating Company to Discuss NFPA 805 License Amendment for Farley
ML1016704282010-06-17017 June 2010
Meeting Summary Notice
ML0929906142009-10-29029 October 2009
Michael Lesar Memo FRN Order (Effective Immediately) Prohibiting Involvement in NRC-Licensed Activities (NRC Office of Investigations Report No. 2-2008-055)
ML0917301322009-06-25025 June 2009
06/07-11/2009-Report on Trip to the Institute of Electrical and Electronics Engineers Stationary Battery Committee Meeting in Rohnert Park, CA
ML0908607892009-01-16016 January 2009
3. FEMA Response to NRC Regarding Farley TARs Seven Question, FEMA Memo from Burnside, January 16, 2009
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0730404832007-10-31031 October 2007
Supplemental Augmented Inspection Team Charter to Evaluate a Farley 1B Residual Heat Removal (RHR) Pump 4.16-kV Breaker Failure
ML0703002272007-02-0606 February 2007
Facsimile Transmission of Draft Request for Additional Information on Emergency Action Level Revision
ML0626902022006-09-20020 September 2006
Facsimile Transmission of Draft Request for Additional Information
ML0614505922006-05-26026 May 2006
Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report
ML0611602422006-04-26026 April 2006
Special Inspection Charter to Evaluate Farley Unit 1 Main Steam Isolation Valve Failures
ML0534901782005-12-0909 December 2005
Safety Evaluation for Proposed Change of Technical Specification to Eliminate the Reactor Coolant Pump Breaker Position Reactor Trip Function.
ML0520701182005-08-0303 August 2005
Unit 2 - Closeout Letter for NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0508705022005-03-29029 March 2005
Memo to John a Harris, Correction of License Authority Files (Tac No. MC3231, MC3232)
ML0504901422005-02-17017 February 2005
Summary of January 13, 2005, Meeting Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Energy Institute (NEI) on Updating the License Renewal Guidance Documents
ML0425402692004-09-15015 September 2004
Memo Issuing Audit and Review Report for Plant Aging Management Reviews and Programs for the Joseph M. Farley Nuclear Plant, Units 1 and 2
ML0415302092004-06-0101 June 2004
Docketing of Questions and Responses Transmitted Electronically or by Facsimile
ML0414701282004-05-26026 May 2004
Notice of Meeting with Southern Nuclear Operating Company Re Forthcoming Meeting to Discuss the Staff'S RAIs on LRA for Farley Nuclear Plant, Units 1 & 2
ML0414005382004-05-0707 May 2004
Input to SER for Section 2.4, Scoping and Screening Results: Containments, Structures, and Component Supports, Joseph M. Farley Nuclear Plant LRA
ML0335000882003-12-15015 December 2003
Commissioner-District 4 - Acknowledgment of Receipt of Your Letter Supporting the Application for Renewal of the Operating Licenses for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Jason Rudd
ML0331604772003-11-12012 November 2003
Email on EOF Relocation
ML0323902222003-08-25025 August 2003
Results of the Joseph M. Farley Nuclear Plant Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit
ML0828803132002-02-0101 February 2002
Observations Noted from Examination of the Farley-PWR 4.6% Power Uprate: Staff Template for Review of PWR Uprates
NRC Generic Letter 1989-111989-06-30030 June 1989
NRC Generic Letter 1989-011: Resolution of Generic Issue 101 Boiling Water Reactor Water Level Redundancy
2023-05-31
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October 31, 2007 MEMORANDUM TO: Michael Ernstes, Branch Chief Reactor Safety Training and Development Branch Division of Reactor Projects FROM: William D. Travers, Regional Administrator /RA/
SUBJECT:
SUPPLEMENTAL AUGMENTED INSPECTION TEAM CHARTER TO EVALUATE A FARLEY 1B RESIDUAL HEAT REMOVAL (RHR) PUMP 4.16-kV BREAKER FAILURE You have been selected to lead a continuation of an Augmented Inspection Team (AIT) to assess the circumstances surrounding 4.16-kV breaker failures at Farley Unit 1. Your inspection should begin on October 22, 2007. Steve Alexander and Russ Lewis will be assisting you in this effort. The need for additional technical support to the team in the area of 4.16-kV breaker design and operation should be evaluated during the initial portion of the inspection. Walt Rogers will provide Senior Reactor Analyst support.
A. Basis On September 14, the NRC completed the on-site portion of an Augmented Inspection at the Farley Nuclear Plant (FNP), Units 1 and 2. This original AIT reviewed two coincident failures of safety-related 4.16-kV breakers at FNP. Specifically, on September 4, 2007, in support of planned maintenance on the 1B component cooling water (CCW) pump, the licensee needed to start the 1C CCW pump (Train A), when the licensee attempted to manually start the 1C CCW pump from the control room, its Cutler-Hammer breaker failed to close. Then on September 5, 2007, during post-maintenance testing of the 1B CCW pump, the licensee attempted to start the 1A CCW pump (Train B). The 1A CCW pump Allis-Chalmers breaker also failed to close when manually started from the control room.
Onsite inspection activities were completed for the original AIT on September 14, 2007.
Subsequently, on October 16, 2007, the 1B RHR pump failed to successfully start on two individual attempts. Preliminary indications are that the recently installed Cutler-Hammer breaker failed to function. The 1B RHR pump was being started to support restoring lower internals into the vessel. The pump had been successfully started at 9:30 a.m., on October 16, 2007, and operated for five hours to support reactor cavity chemistry sampling prior to these start failures.
Unit 1 was in a defueled mode during the failure of the recently installed Cutler-Hammer breaker. Therefore, the 1B RHR pump was not required for system operability when the breaker failure occurred. Unit 2 was operating at approximately 100 percent power.
M. Ernstes 2 A conference call was held October 18, 2007, between NRR, OE, RII, and NSIR to discuss the most recent 1B RHR breaker failure. It was concluded that the NRC would amend the original AIT Charter to extend the inspection to include a review of the most recent failure.
The extended AIT will review the root cause of the most recent failure and other replacement breaker installation issues to determine whether any represents a failure mode different from those identified during the original AIT and review the extent of condition for this recent failure and any other conditions which could affect the operating unit.
A recent 95001 inspection regarding breaker failures was conducted and documented in NRC Inspection Report 348,364/2007-008. This report should be referenced for key background information regarding other historical 4.16-kV breaker issues at the Farley site.
A Preliminary Notification (PN) and press release were issued on October 23.
B. Scope The inspection is expected to perform data gathering and fact-finding in order to address the following:
- 1. Develop a complete description of the 1B RHR 4.16-kV breaker failure on October 16, 2007, and a complete sequence of events related to the breaker failure.
- 2. Determine probable cause(s) for the 1B RHR pump 4.16-kV breaker failure on October 16, 2007, as well as the conditions and circumstances relevant to issues directly related to the event.
- 3. Compare the failure mechanism for the 1B RHR pump breaker to the root causes for the original AIT failures involving CCW breakers to evaluate whether it represents a failure mode different from those identified during the original AIT.
- 4. Review the maintenance program for the 4.16-kV breakers, specifically those which could have led to the identified failure mechanism.
- 5. Review the corrective actions (CAs) and maintenance work order databases to determine the failure history of recently installed Cutler-hammer 4.16-kV breakers.
- 6. Monitor the licensees root cause analysis and extent of condition for thoroughness.
Assess the adequacy of the licensees implemented and/or planned CAs to address the root cause and the time line for completing the CAs on both units.
- 7. Assess if any common mode failure modes have been established for both Unit 1 and Unit 2, if they are being addressed by the licensee, and what generic implications may exist.
- 8. Assess the adequacy of the licensees operability determination for similar Cutler-Hammer 4.16-kV breakers installed on Unit 2.
M. Ernstes 3
- 9. Review industry operating experience (OE) and licensees actions in response to any related OE items.
- 10. Collect data necessary to develop and assess the safety significance of any findings in accordance with IMC 0609, Significance Determination Process.
- 11. Identify any potential generic safety issues and make recommendations for appropriate follow-up actions (e.g., Information Notices, Generic Letters, Bulletins).
C. Guidance Inspection Procedure 93800, "Augmented Inspection Team," provides additional guidance to be used during the conduct of the Augmented Inspection. Your duties will be as described in Inspection Procedure 93800. The inspection should emphasize fact-finding and determination of probable cause(s) in its review of the circumstances surrounding the event. Safety or security concerns identified that are not directly related to the event should be reported to the Region II office for appropriate action.
It is anticipated that the on-site portion of the inspection will be completed during the week of October 26, 2007. A status briefing of Region II management will be provided the second day on-site at 4:00 p.m., (EDT). The results of this inspection may be documented with the original AIT Chartered inspection which began on September 10, 2007, and should be issued within 30 days of the completion of this inspection.
This Charter may be modified should you develop significant new information that warrants review. Should you have any questions concerning this Charter, contact Scott M. Shaeffer at (404) 562-4521.
Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8 cc: W. Kane, OEDO B. Mallett, OEDO L. Trocine, OEDO E. Marinos, NRR M. Ross-Lee, NRR K. Cotton, NRR R. Martin, NRR J. Shea, RII C. Casto, RII V. McCree, RII S. Shaeffer, RII
OFFICE RII:DRP RII:DRS IOEB RII:DRP NRR NSIR SIGNATURE SMS /RA/ KMK /RA for/ CAC /RA/
NAME SShaeffer JShea MRoss-Lee CCasto TMcGinty TBlount DATE 10/22/2007 10/26/2007 10/22/2007 E-MAIL COPY? YES YES YES YES NO YES YES NO
