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Category:Memoranda
MONTHYEARML24089A0712024-04-0101 April 2024 3/20/24 & 3/27/24 2023 TVA Public Annual Assessment Meeting Summary ML23142A2132023-05-22022 May 2023 Public Meeting Summary - 2022 Annual Assessment Meetings for Browns Ferry, Sequoyah and Watts Bar Nuclear Plants ML23121A0772023-05-11011 May 2023 Transmittal of Final Accident Sequence Precursor Report Regarding Centrifugal Charging Pump 1B-B ML21246A2812021-09-29029 September 2021 Memo to File ML21137A0022021-05-17017 May 2021 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plants, Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391, Meeting Number 20210392 ML20164A1442020-06-0303 June 2020 Memorandum from David Lochbaum 2.206 Petition - Review of TVA Employee Concerns Program ML20127H8412020-05-0606 May 2020 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plant, Meeting No. 20200384 ML19142A2772019-05-21021 May 2019 Summary of Public Meeting - Sequoyah Nuclear Plant ML18164A3092018-06-13013 June 2018 June 6, 2018 Summary of Public Meeting - Sequoyah Nuclear Plant - Docket Nos. 50-327 and 50-328 ML18024A0252018-01-24024 January 2018 Approval for Credit for the Sequoyah Operational Safety Review Team to the Baseline Inspection Samples/Hours ML17108A2952017-04-17017 April 2017 Public Meeting Summary - Sequoyah Nuclear Plant ML16131A6202016-05-12012 May 2016 Summary of Public Meeting - Sequoyah, Units 1 and 2 to Provide Opportunities to Discuss the Annual Assessment ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML15092A8092015-09-21021 September 2015 Renewal of Full Power Operating License for the Sequoyah Nuclear Plant, Units 1 and 2 ML15103A5852015-08-14014 August 2015 SQN Continued Storage Note to File - OGC Comments ML15107A1042015-04-17017 April 2015 4/20/2015 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority (TVA) on Sequoyah Nuclear Plant Planned Submittal of Relief Request Regarding Flaws in the Reactor Closure Vessel Head Nozzles ML15106A5462015-04-15015 April 2015 Meeting Summary with Public to Discuss Annual Assessment of Sequoyah Nuclear Plant, Unit 1 & 2, in Soddy Daisy, Tn ML15079A0922015-03-19019 March 2015 Memo 3/19/3015: Sequoyah Nuclear Plant Units 1 and 2 License Renwal Application ML15037A7192015-02-0606 February 2015 Minutes of the ACRS Plant License Renewal Subcommittee Meeting - November 5, 2014 ML14281A5842014-10-24024 October 2014 Federal Register Notice Regarding the ACRS Plant License Renewal (Sequoyah), November 5, 2014 ML14197A6082014-08-0606 August 2014 July 1, 2014, Summary of Category 1 Public Meeting with Tennessee Valley Authority to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML13239A0772013-10-0707 October 2013 8/13/13 - Summary of Meeting Between the Nuclear Regulatory Commission & Tennessee Valley Authority for Clarification of Cultural Resource Request for Additional Information Related to the Sequoyah Nuclear Plant License Renewal Environmenta ML13247A4272013-09-23023 September 2013 Summary of Telephone Conference Call Held on August 19, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA ML13255A3682013-09-0606 September 2013 Written Limited Appearance Statements ML13231A2202013-08-15015 August 2013 Memorandum from the Atomic Safety and Licensing Board Dated August 15, 2013, Forwarding Written Limited Appearance Statements from Various Individuals ML13225A2152013-08-0606 August 2013 Memorandum from the Atomic Safety and Licensing Board Forwarding Written Limited Appearance Statements from Beverly Kerr Dated July 23, 2013 and Stewart Horn Dated August 2, 2013 ML13171A0362013-08-0101 August 2013 Summary of Telephone Conference Call Held on June 13, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA ML13126A2522013-07-25025 July 2013 Request for Additional Information on the 2013 Decommissioning Funding Status Report ML13105A3942013-04-16016 April 2013 Location Change - Notice of Forthcoming Meeting for Public Meeting with Tennessee Valley Authority (TVA) on 2.1 Response Extension Request, Sequoyah Nuclear Plant and Watts Bar Nuclear Plant ML13102A2522013-04-16016 April 2013 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) Regarding Sequoyah Nuclear Plant, Units 1 and 2 Conversion to Improved Technical Specifications (ITS) ML13067A3312013-03-20020 March 2013 03/03/2013 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for Tennessee Valley Authority, Sequoyah Nuclear Plant, Units 1 and 2 ML13078A4212013-03-19019 March 2013 Public Meeting Notice Tennessee Valley Authority, Browns Ferry, Sequoyah, Watts Bar for Commercial Grade Dedication Program ML12215A4212012-10-10010 October 2012 9/5/12 Meeting Summary for Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Units 1 and 2 Appendix R (Fire Protection) ML12234A7582012-08-22022 August 2012 Notice of Forthcoming Meeting with Tennessee Valley Authority (Tva), Regarding Sequoyah Nuclear Plant, Units 1 and 2 Appendix R (Fire Protection) ML12215A4202012-08-0909 August 2012 8/23/12 Forthcoming Notice of Meeting with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Units 1 and 2, Appendix R (Fire Protection) IR 05000390/20100082012-07-0606 July 2012 Errata for Electronic Closure of Watts Bar Inspection Report 05000390/2010-008 Memo Dated July 21, 2011 (ML 112020591) ML12178A4742012-06-28028 June 2012 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Units 1 and 2 Unit Station Service Transformers Amendment Request(Tac Nos. ME8772 & ME8773) ML1120205912011-07-21021 July 2011 IR 05000327-10-008, 05000328-10-008 for Electronic Closure of Sequoyah, and IR 05000390-10-008 for Watts Bar IR 05000327/20100082011-07-21021 July 2011 IR 05000327-10-008, 05000328-10-008 for Electronic Closure of Sequoyah, and IR 05000390-10-008 for Watts Bar ML1119507132011-07-15015 July 2011 the Nuclear Regulatory Commission Staff Spot-Check Review of Tennessee Valley Authority'S One Hundred Percent Ownership Interest of Sequoyah Nuclear Plant, Unit 2, on July 7, 2011 - Finding of No Potential Issues ML1119507002011-07-15015 July 2011 the Nuclear Regulatory Commission Staff Spot-Check Review of Tennessee Valley Authority'S One Hundred Percent Ownership Interest of Sequoyah Nuclear Plant, Unit 1, on July 7, 2011 - Finding of No Potential Issues ML1107000312011-04-15015 April 2011 Notice of Meeting with Tennessee Valley Authority to Discuss Responses to NRC Requests for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pre ML1100600842011-01-0707 January 2011 Notice of Meeting with Tennessee Valley Authority to Discuss the Steam Generator Replacement During the Fall 2012 Refueling Outage for Sequoyah Nuclear Plant, Unit 2 ML1031600802010-11-12012 November 2010 Notice of Forthcoming Conference Call with Tennessee Valley Authority ML1029901502010-10-26026 October 2010 Cancelled - Notice of Meeting with (Tva), to Discuss Responses to the NRC Requests for Additional Information (Rals) for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis. ML1027404372010-10-12012 October 2010 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss Responses to the NRC Requests for Additional Information (Rais) for General Letter 2004-02 ML1024402482010-09-0101 September 2010 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss the Fuel Transition from Existing AREVA-MARK Bw Fuel to New AREVA-High Thermal Performance Fuel for Sequoyah Nuclear Plant, Units 1 and 2 ML1016203602010-06-17017 June 2010 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss the Complete Status of TVA Hydrology Issues Including the Flooding Effects on the TVA Operating Nuclear Plants ML1010407332010-05-0707 May 2010 Notice of Conference Call with Tennessee Valley Authority for Sequoyah, Units 1 and 2, Watts Bar, Unit 1 to Discuss Responses to NRC Requests for Additional Information for Generic Letter 2004-02 2024-04-01
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February 1, 2007 MEMORANDUM TO: Mark E. Speck, Resident Inspector Sequoyah Nuclear Plant Reactor Projects Branch 6 Division of Reactor Projects FROM: William D. Travers, Regional Administrator /RA/
SUBJECT:
SPECIAL INSPECTION CHARTER TO EVALUATE OPERATIONS AND MAINTENANCE ON TIME CRITICAL MANUAL VALVES AT SEQUOYAH You have been selected to lead a Special Inspection to assess the circumstances surrounding the inability to operate manual valve 2-62-527 within the required time of Abnormal Operating Procedure (AOP)-N.08 Appendix R Fire Safe Shutdown, at Sequoyah Unit 2 on November 27, 2006. Your inspection should begin on February 5, 2007. Ronald F. Aiello will be assisting you in this effort.
A. Basis On November 27, 2006, the licensee shut valve 2-62-527 as part of a clearance activity to support Unit 2 outage maintenance and found the valve difficult to operate (i.e.,
required two operators approximately 30 minutes to close). Closing this valve is one of several manual operator actions required by AOP-N.08 to be completed in less than 13 minutes in order to restore Reactor Coolant Pump (RCP) seal flow and prevent RCP seal failure. Review of corrective action documents indicate that operators raised questions as to the ability to perform these actions as early as October 24, 2005.
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. Based on the deterministic criteria that involved possible adverse generic implications combined with the event characteristics that are beyond the scope and capability of the risk assessment for this degraded condition, Region II determined that the appropriate level of NRC response was the conduct of a Special Inspection in accordance with Manual Chapter 0309, Reactive Inspection Decision Basis for Reactors.
This Special Inspection is chartered to identify the circumstances surrounding this event and review the licensees actions following discovery of the conditions. In addition, the inspectors will review this event for generic aspects regarding time critical operator actions being impacted by maintenance activities.
CONTACT: Malcolm T. Widmann, DRP/RPB6 404-562-4550
M. Speck 2 B. Scope The inspection is expected to perform data gathering and fact-finding in order to address the following:
- 1. Develop a sequence of events including applicable management decision points from the time the concern for the inability to operate Appendix R manual valves was raised through troubleshooting and repair activities.
- 2. Review the extent of condition for this event for generic safety implications involving time constrained manual operator actions in emergency, abnormal and Appendix R fire/safe shutdown procedures, i.e., determine if processes or procedures assure manual action operability during post-maintenance testing.
- 3. Assess operating and maintenance procedures and operations and maintenance personnel training concerning Appendix R or emergency operating procedures manual actions manual valves and determine if operations and maintenance personnel are made aware of time constraints placed on operating these valves.
- 4. Assess the process for maintaining, recognizing and protecting time critical manual actions and if such processes are defeated (i.e., through tag-outs, impairment, etc.) if compensatory measures are implemented for the manual actions.
- 5. Determine if there are regulatory or licensee requirements to assure either fire or emergency operating manual actions are verified through post-maintenance testing procedures.
- 6. Collect data necessary to support completing the significance determination process for the associated Sequoyah Unresolved item (URI) and close the URI, if possible.
C. Guidance Inspection Procedure 93812, "Special Inspection," provides additional guidance to be used during the conduct of the Special Inspection. Your duties will be as described in Inspection Procedure 93812. The inspection should emphasize fact-finding 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.
You will report to the site, conduct an entrance, and begin inspection no later than February 5, 2007. It is anticipated that the on-site portion of the inspection will be completed during the week of February 5, 2007. A status briefing of Region II management will be provided the first day on-site at 4:00 p.m. A report documenting the results of the inspection should be issued within 30 days of the completion of the inspection.
M. Speck 3 This Charter may be modified should you develop significant new information that warrants review. Should you have any questions concerning this Charter, contact Malcolm Widmann at (404) 562-4550.
Docket Nos.: 50-327 and 50-328 License Nos.: DPR-77 and DPR-79 cc: W. Kane, OEDO S. Campbell, OEDO J. Dyer, NRR C. Haney, NRR B. Moroney, NRR R. Zimmerman, NSIR V. McCree, RII C. Casto, RII H. Christensen, RII J. Shea, RII K. Kennedy, RII M. Widmann, RII R. Haag, RII
OFFICE RII:DRP RII:DRP RII:DRS ORA SIGNATURE /RA/ /RA/ ./RA By K. Kennedy for/ /RA/
NAME MWidmann CCasto JShea VMcCree DATE 1/31/07 1/31/07 1/31/07 2/1/07 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO