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MONTHYEAR05000482/LER-2009-002, Revision to Commitment Completion Date Reported in LER 2009-002-00 Re Loss of Offsite Power Due to Lightning2011-02-23023 February 2011 Revision to Commitment Completion Date Reported in LER 2009-002-00 Re Loss of Offsite Power Due to Lightning Project stage: Request ML1109404522011-04-0404 April 2011 Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 3.3, Instrumentation, TS 3.7, Plant Systems, TS 3.8, Electrical Systems, and Updated Safety Analysis Report Project stage: Acceptance Review ML12275A1322012-10-0101 October 2012 Request for Additional Information, License Amendment Request to Revise Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems Project stage: RAI ML12310A1952012-10-25025 October 2012 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems Project stage: Response to RAI ML12318A1452012-12-0505 December 2012 Issuance of Amendment No. 200, Revision to Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems Project stage: Approval 2012-10-01
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LER-2009-002, Revision to Commitment Completion Date Reported in LER 2009-002-00 Re Loss of Offsite Power Due to Lightning |
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WLF CREEK
'NUCLEAR OPERATING CORPORATION Stephen E. Hedges February 23, 2011 Site Vice President WO 11-0009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Letter WO 10-0012, dated October 17, 2009, from M. W. Sunseri, WCNOC, to USNRC
Subject:
Docket No. 50-482: Revision to Commitment Completion Date Reported in Wolf Creek Generating Station LER 2009-002-00 Gentlemen:
In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," this letter provides notification to the Nuclear Regulatory Commission (NRC) of a change made to a commitment to the NRC and completion of such commitment.
On October 17, 2009, Wolf Creek Generating Station (WCGS) submitted Licensee Event Report 2009-002-00, "Loss of Offsite Power due to Lightning", as referenced above.
In the referenced submittal WCGS committed that "The owners of WCGS, utilizing industry guidance, shall update the RCM" (Reliability Centered Maintenance) "process to utilize the desired preventive and predictive maintenance activities, frequencies, spare parts, critical substation components and performance monitoring for Wolf Creek Switchyard and the Wolf Creek terminals at LaCygne, Rose Hill and Benton substations and interfacing transmission components."
This commitment was scheduled to be completed by December 31, 2010.
However, WCGS owners indicated that delays would result from the reassignment of resources necessary to conduct the North American Electric Reliability Council (NERC) audit that took place in 2010.
As of December 31, 2010, WCGSs owner companies reported that they had been working with Reliability Centers Inc. (RCI), an outside independent contractor, on an in-depth review of the RCM program for the equipment listed in the commitment. Site visits were conducted by RCI at Wolf Creek, Benton and Rose Hill substations to review the assets and components at each one of these locations. RCI has also been reviewing work processes and procedures for these assets. Weekly conference calls were held to discuss findings and observations after the data was analyzed. The owners received the recommendations from RCI for the Wolf Creek RCM review. The recommendations for the RCMs for Benton and Rose Hill substation along with the Transmission and Substation component trending were received by January 31, 2011.
The P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET
WO 11-0009 Page 2 of 2 LaCygne line terminal equipment has been entered into the Kansas City Power & Light (KCP&L) EMPAC Work Management System which is being used by KCP&L to track the scheduled tasks, responsible party, and completion dates. The LaCyne line terminal equipment work was completed by December 31, 2010. The completed RCM updates were provided to Wolf Creek Nuclear Operating Corporation (WCNOC) for information purposes.
Based on the foregoing reasons, the commitment made in LER 2009-002-00 was completed on January 31, 2011, instead of the original commitment date of December 31, 2010.
The attachment to this letter, List of Commitments, not only revises the original commitment date but also reflects the status of completion of the commitment on January 31, 2011.
If you have any questions concerning this matter, please contact me at (620) 364-4190, or Mr.
Gautam Sen at (620) 364-4175 Sincerely, Stephen E. Hedges SEH/rlt Attachment: List of Commitments cc:
E. E. Collins (NRC), w/a G. B. Miller (NRC), w/a B. K. Singal (NRC), w/a Senior Resident Inspector (NRC), w/a
Attachment to WO 11-0009 Page 1 of 1 LIST OF COMMITMENTS The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation in this document. Any other statements in this letter are provided for information purposes and are not considered regulatory commitments. Please direct questions regarding these commitments to Mr.
Gautam Sen, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4175.
This commitment is revised from that originally described in WCNOC's Licensee Event Report 2009-002-00, "Loss of Offsite Power due to Lightning," from Letter WO 09-0034.
REGULATORY COMMITMENT DUE DATE The owners of WCGS, utilizing industry guidance, shall update January 31, 2011 the RCM process to utilize the desired preventive and (Complete) predictive maintenance activities, frequencies, spare parts, critical substation components and performance monitoring for Wolf Creek Switchyard and the Wolf Creek terminals at LaCygne, Rose Hill and Benton substations and interfacing transmission components.
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| 05000482/LER-2009-001, For Wolf Creek, Regarding Reactor Protection System Actuation and Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed | For Wolf Creek, Regarding Reactor Protection System Actuation and Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-002, Revision to Commitment Completion Date Reported in LER 2009-002-00 Re Loss of Offsite Power Due to Lightning | Revision to Commitment Completion Date Reported in LER 2009-002-00 Re Loss of Offsite Power Due to Lightning | | | 05000482/LER-2009-003, Resubmittal of LER 09-003-00 for Wolf Creek Regarding Post Fire Safe Shutdown Issue During Postulated Control Room Fire | Resubmittal of LER 09-003-00 for Wolf Creek Regarding Post Fire Safe Shutdown Issue During Postulated Control Room Fire | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-004, Regarding Feedwater Isolation on High Water Level in a Steam Generator | Regarding Feedwater Isolation on High Water Level in a Steam Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-005, Regarding Loss of Both Diesel Generators with All Fuel in the Spent Fuel Pool | Regarding Loss of Both Diesel Generators with All Fuel in the Spent Fuel Pool | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-006, Regarding Inadequate Common Cause Failure Determination Results in Condition Prohibited by Technical Specifications | Regarding Inadequate Common Cause Failure Determination Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-007, Regarding Removal of Equipment from Service Required by Technical Specifications and NRC Safety Evaluation | Regarding Removal of Equipment from Service Required by Technical Specifications and NRC Safety Evaluation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-008, Regarding Potential for Containment Fan Coolers to Not Have Automatically Started in Slow Speed | Regarding Potential for Containment Fan Coolers to Not Have Automatically Started in Slow Speed | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-009-01, For Wolf Creek, Regarding Defeating Feedwater Isolation on Low Tavg Coincident with P-4 Function Results in Missed Mode Change | For Wolf Creek, Regarding Defeating Feedwater Isolation on Low Tavg Coincident with P-4 Function Results in Missed Mode Change | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-009, Regarding Defeating Feedwater Isolation on Low Tavg Coincident with P-4 Function Results in Missed Mode Change | Regarding Defeating Feedwater Isolation on Low Tavg Coincident with P-4 Function Results in Missed Mode Change | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-010-01, Regarding Failure to Meet LCO 3.0.4b. During Transition from Mode 4 to Mode 3 | Regarding Failure to Meet LCO 3.0.4b. During Transition from Mode 4 to Mode 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-010, Regarding Failure to Meet LCO 3.0.4b During Transition from Mode 4 to Mode 3 | Regarding Failure to Meet LCO 3.0.4b During Transition from Mode 4 to Mode 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2009-011, For Wolf Creek, Regarding Intermediate Range Detector NI-36 Inoperable | For Wolf Creek, Regarding Intermediate Range Detector NI-36 Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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