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MONTHYEARML24072A0062024-03-12012 March 2024 Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Revised Safety Evaluation for Wolf Creek Generating Station Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting Project stage: Approval ML24085A2732024-03-21021 March 2024 Comments for March 25, 2024 Meeting on Portable Lighting Revised SE Project stage: Meeting ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides Project stage: Meeting ML24088A3122024-04-0101 April 2024 Summary of March 25, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Revised Safety Evaluation for Wolf Creek Generating Station Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting Project stage: Approval ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements Project stage: Approval 2024-03-25
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML24085A2732024-03-21021 March 2024 Comments for March 25, 2024 Meeting on Portable Lighting Revised SE ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML21179A0892021-07-13013 July 2021 Background Information July 13, 2021, Pre-Submittal Public Teleconference ML20308A7332020-11-18018 November 2020 Slides for GSI-191 Pre-Submittal Public Teleconference November 18, 2020 ML18299A0492018-10-30030 October 2018 Accident Analyses Methodology Transition LAR Public Meeting ML16271A4822016-09-27027 September 2016 Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation ML16236A0952016-08-25025 August 2016 And Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML16095A0852016-04-12012 April 2016 Large Scale Head Loss Test Specification 4/12/16 ML16095A0802016-04-12012 April 2016 Large Scale Penetration Test Specification 4/12/16 ML16095A0922016-03-31031 March 2016 Large Scale Penetration and Head Loss Test Plan 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1016204902010-06-16016 June 2010 Notice of Construction Reactor Oversight Process Category 2 Public Meeting Handout: Wolf Creek 2, Notice of Violation and Proposed Imposition of Civil Penalty, Dated 11/21/1984 ML1013404892010-05-14014 May 2010 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009 ML0933702032009-12-0303 December 2009 Summary of Public Meeting for Wolf Creek Generating Station ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response RAIs ML0913300232009-05-13013 May 2009 Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform ML0912600692009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop ML0902102422009-01-15015 January 2009 Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station ML0834700222008-12-11011 December 2008 Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee ML0820305982008-07-18018 July 2008 License Renewal Process Overview M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0820009912008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0817706682008-06-25025 June 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek ML0803706102008-01-11011 January 2008 Westinghouse Electric Company LLC, LTR-CDME-08-2, Rev. 1 NP-Attachment, Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B* ML0729204682007-10-29029 October 2007 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities ML0721501532007-08-0202 August 2007 NRC Staff Handout for August 2, 2007, Meeting with Wolf Creek Nuclear Operating Corporation ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation ML0718606902007-06-19019 June 2007 06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) ML0716203882007-06-0101 June 2007 Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc ML0733409182007-05-31031 May 2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal ML0713703642007-05-17017 May 2007 Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensees Application for the Main Steam and Feedwater Isolation System (Msfis) Modification ML0713506532007-05-0808 May 2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project) ML0713506462007-05-0808 May 2007 Industry Slides, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential PWSCC, from Status Meeting on Implications of Wolf Creek Dissimilar Metal Weld Inspections ML0713506512007-05-0808 May 2007 Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections ML0713603732007-05-0101 May 2007 Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc ML0713603962007-05-0101 May 2007 Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2 2024-06-28
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML20310A2232020-11-19019 November 2020 Slides for ERO Staffing pre-submittal Public Teleconference November 19, 2020 (L-2020-LRM-0104) ML16236A0952016-08-25025 August 2016 And Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16236A0972016-08-25025 August 2016 Operating Corporation - August 25, 2016, Core Design and Safety System Analysis Methodology Transition License Amendment Request Revised ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13219A1932013-08-0707 August 2013 Licensee Slides (Final), 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML13121A4892013-05-0101 May 2013 End of Cycle Meeting Summary 4-18-13 ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1013404892010-05-14014 May 2010 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009 ML0933702032009-12-0303 December 2009 Summary of Public Meeting for Wolf Creek Generating Station ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response RAIs ML0913300232009-05-13013 May 2009 Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform ML0912600762009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop Application of ISG-4 During Wolf Creek and Oconee Reviews ML0912600692009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop ML0902102422009-01-15015 January 2009 Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station ML0834700222008-12-11011 December 2008 Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee ML0820305982008-07-18018 July 2008 License Renewal Process Overview ML0820009912008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0817706682008-06-25025 June 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek ML0813606472008-06-10010 June 2008 Summary of Public Meeting on Safety Evaluation Report with Open Items Regarding the Wolf Creek Generating Station License Renewal Review ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0720601382007-07-17017 July 2007 Slides from Meeting Between NRC Staff and Wolf Creek Panel Enclosures 2 to 3, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation ML0718606902007-06-19019 June 2007 06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) ML0716203882007-06-0101 June 2007 Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc ML0733409182007-05-31031 May 2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal ML0713703642007-05-17017 May 2007 Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensees Application for the Main Steam and Feedwater Isolation System (Msfis) Modification ML0713506512007-05-0808 May 2007 Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections ML0713506532007-05-0808 May 2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project) ML0713603962007-05-0101 May 2007 Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2 ML0713603732007-05-0101 May 2007 Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc ML0701601892006-12-19019 December 2006 Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping ML0635603582006-11-30030 November 2006 Industry Presentation Slides: MRP-139 Analysis Basis ML0635603462006-11-30030 November 2006 November 30, 2006 NRC Presentation Slides: Wolf Creek Flaw Evaluation ML0632100772006-11-16016 November 2006 NRC Presentation: NRC Perspective on Wolf Creek Inspection Results ML0632100802006-11-16016 November 2006 Industry Presentations: Nov. 16, 2006 Public Meeting ML0622804372006-08-16016 August 2006 Handouts from Wolf Creek Nuclear Operating Corporation and from Union Electric Company for Meeting with NRC on the Main Steam Isolation Valve (MSIV) Operability Determination 2024-06-28
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Wolf Creek Generating Station,Unit 1 Revisions to Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements Public Meeting March 25, 2024
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements Meeting Purpose
- To Present the NRCs Revisions to the Safety Evaluation Related to Amendment 237, Request For Deviation from Fire Protection Requirements (ML23165A250)
- Licensee Submitted Request for Correction Letter October 19, 2023 (ML23292A357)
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comments 1.0 and 2.0: The SE only addresses the acceptability for portable lighting for fires outside the control room. The SE calls out specific fire areas. The SE did not include and address all procedures. The LAR does not request specific fire areas to be included for portable lighting consideration but requests specific implementing procedures that require OMAs.
NRC Response: The SE identifies the fire areas that were described by the licensee in Sections 1, 2, and 8 of its analysis titled Post-Fire Safe Shutdown Operator Manual Actions. The SE was revised to state the following:
Table 1 of this SE identifies the 10 CFR Part 50 Appendix R, Section III.G.2 fire areas identified by the licensee in its analysis that require operator manual actions to achieve safe shutdown.
Appendix R to 10 CFR Part 50, Section III.G.2 fire areas are areas where cables or equipment of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located in the same fire area outside of primary containment. The operator manual actions are actions conducted outside the affected fire area that are needed to ensure that safe shutdown can be accomplished for a fire in the affected area.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
NRC Response to Comments 1.0 and 2.0 (continued):
The SE does not identify any procedures. The NRC does not approve plant procedures, rather it reviews/approves proposed changes that may require plant procedure changes. The SE was revised to state the following:
The licensee requested to use hard hat mounted portable lights as an alternative for fixed emergency lighting units with limited exceptions (as described above), where operator manual actions are performed to achieve and maintain post-fire safe shutdown, and to be the primary illumination means for utilizing related implementing procedures, safe shutdown equipment, and the respective access and egress routes to the equipment in support of post-fire shutdown or a non-fire event resulting in the loss of all AC power.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 3.0: The licensee indicated that the following paragraph was incorrect:
In plant areas, where installation of 8-hour battery backup supplied lighting is not achievable, the hard hat mounted portable lights accomplish the purpose of achieving adequate emergency lighting because they will ensure that adequate lighting is available to aid the operator for an extended period of time during plant fire emergencies.
NRC Response: The SE was revised as follows:
The underlying purpose of 10 CFR Part 50, Appendix R, Section Ill.J, is to ensure that adequate lighting is available to aid the operator for an extended period of time during plant fire emergencies. In plant areas, where installation or maintenance of 8-hour battery backup supplied lighting is not achievable or feasible, the hard hat mounted portable lights accomplish the purpose of achieving adequate emergency lighting because they will ensure that adequate lighting is available to aid the operator for an extended period of time during plant fire emergencies.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 4.0: A discussion regarding the remaining 8-hour fixed emergency lighting units that will remain in place, but be downgraded to 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Life Safety is not include in the SE.
NRC Response: In Section 3.0 of the SE, the NRC states the following:
The licensee further indicated that for life safety access, egress, and for firefighting activities, 1.5-hour fixed lights will be available for supplementary lighting to the portable lights.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 5.0: The license indicated that they did not commit to 10 CFR 50, Appendix R.
NRC Response: The SE was revised as follows:
Wolf Creek was licensed to operate on June 4, 1985, and thus, is not subject to Appendix R to 10 CFR Part 50. However, the requirements of Appendix R to 10 CFR Part 50, Section III.J to provide emergency lighting to assure that safe shutdown capability is maintained during and after a fire, are referenced in appendix 9.5E, 10 CFR Part 50 Appendix R Comparison, of the Wolf Creek USAR. Appendix R to 10 CFR Part 50, Section III.J, states that, Emergency lighting units with at least an 8-hour battery power supply shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes thereto. The objective of this requirement is that in the event of a fire, adequate lighting will be available to assure that the plant can be safely shut down.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 6.0: The license indicated that the following paragraph was incorrect:
The fixed emergency lighting system is powered from vital buses. Upon loss of the normal power supply to the vital buses, the emergency diesel generators will provide power to the vital buses. Thus, the emergency lighting system will be continuously energized to the fire areas listed in table 2 of this SE.
NRC Response: The SE was revised as follows:
The fixed emergency lighting system is powered from normal lighting circuits that are fed from the non-Class 1E auxiliary system. Upon loss of the normal AC power, the lights will be powered by the back-up batteries. The licensee has provided a reliability and feasibility analysis, which shows that all of the required manual actions can be performed well before the 8-hour batteries become incapable of performing their required function. Thus, the fixed emergency light fixtures in the locations listed in table 2 of this SE will be continuously energized for a sufficient time period to enable the plant to safely shutdown.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 7.0: The licensee indicated that the basis the NRC stated for the RAI was incorrect.
NRC Response: The SE was revised as follows:
Based on its review of information in the LAR, the NRC staff transmitted a request for additional information (RAI) to the licensee on December 27, 2022 (ML22361A005). The NRC staffs RAI requested that the licensee discuss the impact of using only portable (hard hat mounted) lights to light travel pathways to and from areas where operator manual actions are performed. Furthermore, the NRC staffs RAI requested information regarding the status of updating the feasibility and reliability review for each fire area where operator manual actions are conducted since it did not appear to the NRC staff that this review had been updated to reflect the use of portable hard hat mounted lights in lieu of fixed emergency light fixtures.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 8.0: The licensee indicated that using the term in certain fire areas was not correct.
NRC Response: The SE was revised in several areas by deleting in certain fire areas and changing it to with limited exceptions and those limited exceptions were defined. In addition, the following paragraph was added to SE Section 1.0:
The areas where hard hat mounted lights will not be used for post-fire safe shutdown (i.e., the limited exceptions mentioned above) are areas of the plant where the fixed emergency light fixtures with 8-hour battery backup will be retained and credited for post-fire safe shutdown.
These areas include the control room, the auxiliary shutdown panel, the emergency diesel generator control panel, and the operations hard hat rack just outside the control room. For additional details, see table 2 of this SE.
Table 2 refers to the fixed emergency lighting units with 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery backup locations credited for safe shutdown as identified in LAR table E.2.5-1.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 9.0: The licensee indicated that the defense-in-depth discussion was not correct.
NRC Response: The SE was revised as follows:
Defense-in-depth elements are maintained (e.g., control of transient combustible materials),
through various means, including: the implementation of administrative procedures; automatic fire detection and fire suppression systems are provided as required by the fire hazard analysis; portable fire extinguishers and fire hose stations are provided throughout the plant for manual firefighting; and passive fire barrier features (walls, floors/ceilings, fire dampers, doors, penetration seals, fire wrap, and structural steel fireproofing) to separate redundant post-fire safe-shutdown components are installed in accordance with industry standards and fire tested assemblies. Therefore, a level of safety is being provided that results in the unlikely occurrence of fires; rapid detection, control, and extinguishment of fires that do occur, and the protection of SSCs important to safety.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Licensee Comment 10.0: The licensee indicated that the following paragraph was not correct:
The equipment needed for safe shutdown at Wolf Creek is maintained inside the main power block and several buildings onsite.
NRC Response: The SE was revised as follows:
The equipment needed for safe shutdown at Wolf Creek is maintained inside the main power block and the essential service water pump house. Fixed emergency lighting is provided inside these buildings for areas needed for operation of safe shutdown equipment, as well as for access and egress routes in accordance with 10 CFR Part 50, Appendix R, Section llI.J.
Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements
Comments/Questions Revisions to Wolf Creek Safety Evaluation Related to Amendment 237, Request for Deviation from Fire Protection Requirements