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| | issue date = 01/31/2012 | | | issue date = 01/31/2012 |
| | title = Cancellation of Licensee Event Report 2011-010-00, Diesel Generator Declared Inoperable Due to Inadequate Adjustment of the Diesel Generator Governor. | | | title = Cancellation of Licensee Event Report 2011-010-00, Diesel Generator Declared Inoperable Due to Inadequate Adjustment of the Diesel Generator Governor. |
| | author name = Smith R A | | | author name = Smith R |
| | author affiliation = Wolf Creek Nuclear Operating Corp | | | author affiliation = Wolf Creek Nuclear Operating Corp |
| | addressee name = | | | addressee name = |
Revision as of 04:34, 29 June 2019
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). 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4 WKLF CREEK'NUCLEAR OPERATING CORPORATION Russell A. Smith Plant Manager January 31, 2012 WO 12-0010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
Letter WO 11-0085, dated October 31, 2011, from R. A. Smith, WCNOC, to USNRC
Subject:
Docket No. 50-482: Cancellation of Licensee Event Report 2011-010-00, "Diesel Generator Declared Inoperable Due to Inadequate Adjustment of the Diesel Generator Governor" Gentlemen:
The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the cancellation of Wolf Creek Generating Station (WCGS) Licensee Event Report (LER) 2011-010-00, "Diesel Generator Declared Inoperable Due to Inadequate Adjustment of the Diesel Generator Governor." The cancellation of this LER is consistent with the guidance in NUREG-1022, Revision 2, "Event Reporting Guidelines 10 CFR 50.72 and 50.73," Sections 2.8 and 5.1.2.The Reference reported an event under 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications and 10 CFR 50.73(a)(2)(v)(A) through (D) as a condition that could have prevented fulfillment of a safety function.
The Reference indicated that an evaluation was being conducted to determine whether the "A" diesel generator (DG) was capable of performing its specified safety function during period of May 21, 2011 through September 4, 2011.The evaluation of the governor adjustment made in May 2011 to reduce fuel rack movement at steady state load has been completed.
The evaluation determined that the governor adjustment would have had minimal affect on dynamic governor response.
The evaluation utilized vendor information and computer modeling as well as completed test data and concluded that the "A" DG was capable of performing its specified safety function for the period of May 21, 2011 through September 4, 2011.P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET I WO 12-0010 Page 2 of 2 Since the "A" DG was capable of performing its specified safety function, the Technical Specification Conditions/Required Actions were met when the "B" DG was taken out of service for maintenance during the period of May 21, 2011 through September 4, 2011. Limiting Condition for Operation (LCO) 3.0.4 was met (since LCO 3.8.1 was met) when transitioning from MODE 5 to MODE 1. As such, this event is not reportable per 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
Additionally, the 50.73(a)(2)(v) criteria is not applicable since both DGs were not inoperable at the same time. Section 3.2.7 of NUREG-1022 (event or condition that could have prevented the fulfillment of a safety function) indicates the event would be reportable under 50.73(a)(2)(v) if either offsite power or onsite emergency power (i.e., DGs) is unavailable to the plant.Based on the above, WCNOC determined that this condition does not meet the criteria for reporting in accordance with 10 CFR 50.73. Therefore, LER 2011-010-00 is being cancelled.
This letter contains no commitments.
If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Gautam Sen at (620) 364-4175.Sincerely, Russell A. Smith RAS/rlt cc: E. E. Collins (NRC)J. R. Hall (NRC)N. F. O'Keefe (NRC)Senior Resident Inspector (NRC)