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| {{#Wiki_filter:W0..LF CREEKNUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014Vice President Engineering ET 14-0037U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555 | | {{#Wiki_filter:W0..LF CREEK NUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014 Vice President Engineering ET 14-0037 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 |
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| ==Reference:== | | ==Reference:== |
| : 1) Letter ET 13-0035, dated November 21, 2013, from J. P Broschak, WCNOC, to USNRC | | : 1) Letter ET 13-0035, dated November 21, 2013, from J. P Broschak, WCNOC, to USNRC |
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| ==Subject:== | | ==Subject:== |
| | | Docket No. 50-482: Supplemental Information Regarding License Amendment Request for Revision to the Wolf Creek Generating Station Fire Protection Program Related to Alternative Shutdown Capability Gentlemen: |
| Docket No. 50-482: Supplemental Information Regarding LicenseAmendment Request for Revision to the Wolf Creek Generating StationFire Protection Program Related to Alternative Shutdown Capability Gentlemen: | | Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the approved fire protection program as described in the Updated Safety Analysis Report (USAR). Attachment I to Reference 1 (page 10 of 64), Section 3.4, "Defense-In-Depth Evaluation," describes the defense-in-depth fire protection features utilized to meet the concept of defense-in-depth described in 10 CFR 50, Appendix R. Section 3.4 states, in part: Defense-in-depth fire protection features established for meeting the above objectives for the control room includes the following: |
| Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application torevise the approved fire protection program as described in the Updated Safety Analysis Report(USAR). Attachment I to Reference 1 (page 10 of 64), Section 3.4, "Defense-In-Depth Evaluation," | | : 8. Cables carrying voltages greater than 120 VAC/125 VDC are not run in the control room. Cables in the control room are limited to those that terminate in the control room for instrumentation and control circuits as well as lighting and other ancillary uses.During a review of external operating experience, Institute of Nuclear Power Operations Event Report (IER) 14-33, "Direct Current Circuits Challenge Appendix R Fire Analysis," it was identified that there are cables carrying voltages of 250 VDC in the control room. These cables are associated with hand switches and indication circuits for the Turbine Generator direct current (DC) Emergency Lube Oil Pump and the Emergency DC Seal Oil Pump. These cables are IEEE-383,"Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations," qualified which indicates that they will not readily ignite and propagate a fire. The presence of the 250 VDC cables in the control room does not adversely impact the conclusion that the fire protection defense-in-depth features within the control room provide reasonable assurance that a severe fire that causes the evacuation of the control room is unlikely.P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET ET 14-0037 Page 2 of 3 Item 8, in Section 3.4, is revised to state: 8. Cables in the control room are limited to those that terminate in the control room for instrumentation and control circuits as well as lighting and other ancillary uses.The additional information does not expand the scope of the application and does not impact the no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.This letter contains no commitments. |
| describes the defense-in-depth fire protection features utilized to meet the conceptof defense-in-depth described in 10 CFR 50, Appendix R. Section 3.4 states, in part:Defense-in-depth fire protection features established for meeting the above objectives forthe control room includes the following: | | If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.Sincerely, Jai e H. McCoy JHM/rlt cc: T. A. Conley (KDHE)M. L. Dapas (NRC)C. F. Lyon (NRC)N. F. O'Keefe (NRC)Senior Resident Inspector (NRC) |
| : 8. Cables carrying voltages greater than 120 VAC/125 VDC are not run in thecontrol room. Cables in the control room are limited to those that terminate in thecontrol room for instrumentation and control circuits as well as lighting and otherancillary uses.During a review of external operating experience, Institute of Nuclear Power Operations EventReport (IER) 14-33, "Direct Current Circuits Challenge Appendix R Fire Analysis," | | ET 14-0037 Page 3 of 3 STATE OF KANSAS))ss COUNTY OF COFFEY )Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.By __ _ _Jaime .iMcCoy Vice President Engineering SUBSCRIBED and sworn to before me this 0 day of becerr be(-,2014.NA14bh)SNctzry Pu~ligz -State of KansasI Expiration Date* .! w}} |
| it wasidentified that there are cables carrying voltages of 250 VDC in the control room. These cablesare associated with hand switches and indication circuits for the Turbine Generator directcurrent (DC) Emergency Lube Oil Pump and the Emergency DC Seal Oil Pump. These cablesare IEEE-383,"Standard for Type Test of Class 1E Electric Cables, Field Splices, andConnections for Nuclear Power Generating Stations," | |
| qualified which indicates that they will notreadily ignite and propagate a fire. The presence of the 250 VDC cables in the control roomdoes not adversely impact the conclusion that the fire protection defense-in-depth featureswithin the control room provide reasonable assurance that a severe fire that causes theevacuation of the control room is unlikely. | |
| P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831An Equal Opportunity Employer M/F/HC/VET ET 14-0037Page 2 of 3Item 8, in Section 3.4, is revised to state:8. Cables in the control room are limited to those that terminate in the control roomfor instrumentation and control circuits as well as lighting and other ancillary uses.The additional information does not expand the scope of the application and does not impactthe no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," | |
| a copy ofthis submittal is being provided to the designated Kansas State official. | |
| This letter contains no commitments. | |
| If you have any questions concerning this matter, pleasecontact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041. | |
| Sincerely, Jai e H. McCoyJHM/rltcc: T. A. Conley (KDHE)M. L. Dapas (NRC)C. F. Lyon (NRC)N. F. O'Keefe (NRC)Senior Resident Inspector (NRC) | |
| ET 14-0037Page 3 of 3STATE OF KANSAS))ssCOUNTY OF COFFEY )Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf ofsaid Corporation with full power and authority to do so; and that the facts therein stated are trueand correct to the best of his knowledge, information and belief.By __ _ _Jaime .iMcCoyVice President Engineering SUBSCRIBED and sworn to before me this 0 day of becerr be(-,2014.NA14bh)SNctzry Pu~ligz -State of KansasIExpiration Date* .! w}} | |
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Category:Letter
MONTHYEARML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, “Preparation and Scheduling of Operator Licensing Examinations” ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24036A0092024-02-14014 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0075 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24036A1852024-02-0505 February 2024 Correction to 2022 Annual Radioactive Effluent Release Report - Report 46 ML24032A1742024-02-0202 February 2024 Withdrawal of Requested Licensing Action Exemption from Specific Provisions in 10 CFR 73.55 ML24025A0992024-01-25025 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 2024-09-04
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W0..LF CREEK NUCLEAR OPERATING CORPORATION Jaime H. McCoy December 8, 2014 Vice President Engineering ET 14-0037 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 13-0035, dated November 21, 2013, from J. P Broschak, WCNOC, to USNRC
Subject:
Docket No. 50-482: Supplemental Information Regarding License Amendment Request for Revision to the Wolf Creek Generating Station Fire Protection Program Related to Alternative Shutdown Capability Gentlemen:
Reference 1 provided the Wolf Creek Nuclear Operating Corporation (WCNOC) application to revise the approved fire protection program as described in the Updated Safety Analysis Report (USAR). Attachment I to Reference 1 (page 10 of 64), Section 3.4, "Defense-In-Depth Evaluation," describes the defense-in-depth fire protection features utilized to meet the concept of defense-in-depth described in 10 CFR 50, Appendix R. Section 3.4 states, in part: Defense-in-depth fire protection features established for meeting the above objectives for the control room includes the following:
- 8. Cables carrying voltages greater than 120 VAC/125 VDC are not run in the control room. Cables in the control room are limited to those that terminate in the control room for instrumentation and control circuits as well as lighting and other ancillary uses.During a review of external operating experience, Institute of Nuclear Power Operations Event Report (IER) 14-33, "Direct Current Circuits Challenge Appendix R Fire Analysis," it was identified that there are cables carrying voltages of 250 VDC in the control room. These cables are associated with hand switches and indication circuits for the Turbine Generator direct current (DC) Emergency Lube Oil Pump and the Emergency DC Seal Oil Pump. These cables are IEEE-383,"Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations," qualified which indicates that they will not readily ignite and propagate a fire. The presence of the 250 VDC cables in the control room does not adversely impact the conclusion that the fire protection defense-in-depth features within the control room provide reasonable assurance that a severe fire that causes the evacuation of the control room is unlikely.P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET ET 14-0037 Page 2 of 3 Item 8, in Section 3.4, is revised to state: 8. Cables in the control room are limited to those that terminate in the control room for instrumentation and control circuits as well as lighting and other ancillary uses.The additional information does not expand the scope of the application and does not impact the no significant hazards consideration determination presented in Reference 1.In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.This letter contains no commitments.
If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.Sincerely, Jai e H. McCoy JHM/rlt cc: T. A. Conley (KDHE)M. L. Dapas (NRC)C. F. Lyon (NRC)N. F. O'Keefe (NRC)Senior Resident Inspector (NRC)
ET 14-0037 Page 3 of 3 STATE OF KANSAS))ss COUNTY OF COFFEY )Jaime H. McCoy, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.By __ _ _Jaime .iMcCoy Vice President Engineering SUBSCRIBED and sworn to before me this 0 day of becerr be(-,2014.NA14bh)SNctzry Pu~ligz -State of KansasI Expiration Date* .! w