|
|
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: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 | | {{#Wiki_filter: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:== | | ==Reference:== |
| | | Letter WO 11-0085, dated October 31, 2011, from R. A. Smith, WCNOC, to USNRC |
| Letter WO 11-0085, dated October 31, 2011, from R. A. Smith, WCNOC, to USNRC | |
|
| |
|
| ==Subject:== | | ==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: | | 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 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 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 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 determined that the governor adjustment would have had minimal affect on dynamic governor response. | | 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. |
| 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. | | P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET |
| 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. | | 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. |
| 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)}} | | 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)}} |
|
---|
Category:Letter type:WO
MONTHYEARWO 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 WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations WO 23-0009, Financial Protection Levels2023-03-31031 March 2023 Financial Protection Levels WO 22-0056, Operating Corporations Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082022-12-19019 December 2022 Operating Corporations Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report WO 22-0015, Generation Station - Guarantee of Payment of Deferred Premiums2022-05-0606 May 2022 Generation Station - Guarantee of Payment of Deferred Premiums WO 22-0011, Operating Corp., Financial Protection Levels2022-03-29029 March 2022 Operating Corp., Financial Protection Levels WO 22-0007, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-0909 March 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations WO 21-0064, Operating Corporation, Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082021-12-29029 December 2021 Operating Corporation, Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 WO 21-0031, (Wcgs), Supplement to One-Time Request for Exemption from the Biennial Emergency Preparedness2021-08-12012 August 2021 (Wcgs), Supplement to One-Time Request for Exemption from the Biennial Emergency Preparedness WO 21-0027, One-Time Request for Exemption from the Biennial Emergency Preparedness2021-07-29029 July 2021 One-Time Request for Exemption from the Biennial Emergency Preparedness WO 21-0015, License Amendment Request (LAR) for Revision to the Emergency Plan2021-05-25025 May 2021 License Amendment Request (LAR) for Revision to the Emergency Plan WO 21-0020, Operating Corp - Guarantee of Payment of Deferred Premiums2021-05-0707 May 2021 Operating Corp - Guarantee of Payment of Deferred Premiums WO 21-0019, Operating Corp Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-14014 April 2021 Operating Corp Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations WO 21-0014, Financial Protection Levels2021-03-30030 March 2021 Financial Protection Levels WO 21-0010, Submittal of Revision 34 to Updated Safety Analysis Report2021-03-11011 March 2021 Submittal of Revision 34 to Updated Safety Analysis Report WO 21-0002, Notification of Readiness for Supplemental Inspection 927232021-01-28028 January 2021 Notification of Readiness for Supplemental Inspection 92723 WO 20-0058, Operating Corporation'S Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082020-12-23023 December 2020 Operating Corporation'S Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange WO 20-0040, Corrected Revision 33 of the Wolf Creek Generating Station Updated Safety Analysis Report2020-07-23023 July 2020 Corrected Revision 33 of the Wolf Creek Generating Station Updated Safety Analysis Report WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0047, Guarantee of Payment of Deferred Premiums2020-05-0707 May 2020 Guarantee of Payment of Deferred Premiums WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies WO 20-0024, Financial Protection Levels2020-03-31031 March 2020 Financial Protection Levels WO 19-0059, Docket No. 50-482: Wolf Creek Nuclear Operating Corporation'S Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082019-12-23023 December 2019 Docket No. 50-482: Wolf Creek Nuclear Operating Corporation'S Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 WO 19-0033, License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System2019-08-29029 August 2019 License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System WO 19-0031, Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-08-0808 August 2019 Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 19-0011, Financial Protection Levels2019-03-27027 March 2019 Financial Protection Levels WO 19-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-03-11011 March 2019 Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0045, Submittal of Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Revision to the Emergency Plan2018-11-19019 November 2018 Submittal of Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Revision to the Emergency Plan WO 18-0047, Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Timeline for Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0036, Operating Corporation (WCNOC) - Notification of Readiness for Supplemental Inspection2018-08-15015 August 2018 Operating Corporation (WCNOC) - Notification of Readiness for Supplemental Inspection WO 18-0034, Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-08-0909 August 2018 Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0031, Inservice Inspection (ISI) Program Relief Request from the Requirements of American Society of Mechanical Engineers (ASME) Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12018-07-23023 July 2018 Inservice Inspection (ISI) Program Relief Request from the Requirements of American Society of Mechanical Engineers (ASME) Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 WO 18-0016, License Amendment Request for Revision to the Emergency Plan2018-05-0909 May 2018 License Amendment Request for Revision to the Emergency Plan WO 18-0014, Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-04-16016 April 2018 Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations WO 18-0015, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2018-04-0505 April 2018 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... WO 17-0093, License Amendment Request (LAR) for Revision to the Emergency Plan2017-12-19019 December 2017 License Amendment Request (LAR) for Revision to the Emergency Plan WO 17-0092, Request for Regulatory Conference (EA-17-149)2017-11-0808 November 2017 Request for Regulatory Conference (EA-17-149) WO 17-0065, Submittal of LER 17-S01-00 for Wolf Creek Nuclear Operating Corp., Regarding Contraband Introduced Into the Protected Area Boundary2017-10-10010 October 2017 Submittal of LER 17-S01-00 for Wolf Creek Nuclear Operating Corp., Regarding Contraband Introduced Into the Protected Area Boundary WO 17-0042, Operating Corporation Supplement to RAI Response Regarding Adopting New EAL Scheme2017-04-26026 April 2017 Operating Corporation Supplement to RAI Response Regarding Adopting New EAL Scheme WO 17-0041, Supplement to Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2017-04-20020 April 2017 Supplement to Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report WO 17-0033, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations.2017-04-17017 April 2017 Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations. WO 17-0023, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2017-03-27027 March 2017 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report WO 17-0026, Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses2017-03-22022 March 2017 Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses WO 17-0013, Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme2017-03-16016 March 2017 Response to Request for Additional Information Regarding License Amendment Request for Adopting Revised Emergency Action Level Scheme WO 17-0009, Revision 30 to Updated Safety Analysis Report2017-03-0909 March 2017 Revision 30 to Updated Safety Analysis Report WO 16-0068, Docket No. 50-482: Request for Regulatory Conference2016-12-21021 December 2016 Docket No. 50-482: Request for Regulatory Conference 2023-05-17
[Table view] |
Text
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)