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Category:Memoranda
MONTHYEARML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter ML24138A0092024-05-17017 May 2024 Public Meeting Summary - 2023 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50-348, and 50-364 -Meeting Number 20240474 ML23146A1672023-05-31031 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 2024-07-24
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Contact: Curtis W. Rapp, RPB2/DRP (404) 562-4653April 26, 2006MEMORANDUM TO:James Baptist, Resident Inspector, Joseph M. Farley Nuclear PlantReactor Projects Branch 2 Division of Reactor ProjectsFROM:William D. Travers, Regional Administrator /RA/
SUBJECT:
SPECIAL INSPECTION CHARTER TO EVALUATE FARLEY UNIT 1MAIN STEAM ISOLATION VALVE FAILURESYou have been selected to lead a Special Inspection to assess the circumstances surrounding three outboard main steam isolation valves (MSIVs) that failed to close at Farley Unit 1 on or around April 8, 2006. Your inspection should begin on April 25, 2006. Mr. Mike Scott, Division of Reactor Safety, will be assisting you in this effort.A.BasisOn or around April 8, 2006, the licensee conducted an as-found closure test of the Unit1 MSIVs following unit shutdown for a scheduled refueling outage. Two of three outboard MSIVs failed to move and one outboard MSIV achieved only a partial stroke.
All inboard MSIVs, which are of similar design, appear to have functioned properly and fully closed.In accordance with Management Directive 8.3, "NRC Incident Investigation Program,"deterministic and conditional risk criteria were used to evaluate the level of NRC response for this operational event. The review concluded that the circumstances of the event met the MD 8.3 deterministic criteria due to the multiple failures which occurred exhibiting potential common mode repetitive failure scenarios. Specifically, three of six Unit 1 MSIVs failed to close on demand during valve closure testing. The failures also involved possible adverse generic implications as related to Unit 2 MSIV operability. The risk review indicated the CCDP for the event met criterion for a Special Inspection.
Subsequently, Region II determined that the appropriate level of NRC response was theconduct of a Special Inspection.This Special Inspection is chartered to identify the circumstances surrounding this eventand review the licensee's actions following discovery of the conditions.
2J. BaptistB.ScopeThe inspection is expected to perform data gathering and fact-finding in order toaddress the following:1.Develop a sequence of events, including applicable management decision pointsprior to the time the MSIVs failed through troubleshooting and repair activities.2.Review licensee documents to assess if the licensee had previous failures ofMSIVs to close and also review current and previous maintenance practices for the MSIVs.3.Assess any corrective action the licensee took prior to the event to addressMSIV closure problems and determine if the actions were appropriate and timely.4.Assess operating procedures and operator training concerning this scenario anddetermine if the procedures and training were adequate for operators to compensate for the lack of MSIV closure.5.As requested by the Regional SRA, assist in the collection of data necessary tosupport completion of the significance determination process.6.Review the licensee's MSIV operability determination for Unit 2.7.Review this event for generic safety implications.C.GuidanceInspection Procedure 93812, "Special Inspection," provides additional guidance to beused during the conduct of the Special Inspection. Your duties will be as described inInspection Procedure 93812. The inspection should emphasize fact-finding in its review of the circumstances surrounding the MSIV failures. Safety or security concerns identified that are not directly related to the event should be reported to the Region IIoffice for appropriate action.You will conduct an entrance and begin inspection no later than April 25, 2006. It isanticipated that the on-site portion of the inspection will be completed by May 2, 2006, atwhich time you should conduct an exit of the inspection results with the licensee. A daily Region II Management status briefing (4:00 p.m. EST) summarizing your inspection results should be provided beginning on April 26, 2006. A report documenting the results of the inspection should be issued within 45 days of the completion of the inspection.
3J. BaptistThis Charter may be modified should you develop significant new information that warrantsreview. Should you have any questions concerning this Charter, contact Scott Shaeffer at (404) 562-4521.
References:
- 1. NRC Inspection Procedure 93812, Special Inspection 2. Region II ROI 2296, Management Directive 8.3 Decision Documentation Form
- 3. Management Directive 8.3, NRC Incident Investigation Program4. Manual Chapter 0612, Power Reactor Inspection Reports
- 5. Manual Chapter 0609, Significance Determination ProcessDocket Nos.: 50-348 and 50-364License Nos.: NPF-2 and NPF-8cc: W. Kane, OEDO S. Lee, OEDO J. Dyer, NRR C. Haney, NRR R. Martin, NRR R. Zimmerman, NSIR L. Plisco, RII C. Casto, RII V. McCree, RII
_________________________OFFICERII:DRPRII:DRSRII:DRPRII:ORASIGNATURENAMESShaefferVMcCreeCCastoLPliscoDATE4/ /20064/ /20064/ /20064/ /2006 E-MAIL COPY? YESNO YESNO YESNO YESNO