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MONTHYEARML0936410672009-12-16016 December 2009 License Amendment Request for Use of Fire-Resistive Electrical Cable Project stage: Request ML1011006282010-05-0606 May 2010 Request for Additional Information, License Amendment Request, Revise Updated Safety Analysis Report to Modify Fire Protection Program for Use of Fire-Resistive Electrical Cable Project stage: RAI ML1025604982010-09-30030 September 2010 Issuance of Amendment No. 189, Revise Updated Safety Analysis Report to Modify Fire Protection Program for Use of Fire-Resistive Electrical Cable Project stage: Approval 2010-05-06
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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 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) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third 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 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 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 ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements 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 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 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 IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 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) 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22249A2552022-06-29029 June 2022 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012 ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21253A0902021-09-23023 September 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21132A1032021-05-12012 May 2021 Document Request List, Paperwork Reduction Act Statement ML20302A4782020-10-28028 October 2020 OPC R1 Request for Information ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20195A2712020-07-13013 July 2020 Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19346E6052019-11-0404 November 2019 Target Set Request for Information for Week of November 4, 2019 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML18282A6402018-10-0909 October 2018 NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses ML18207A4332018-07-24024 July 2018 NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101 ML18116A6132018-04-25025 April 2018 Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17170A3152017-06-19019 June 2017 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17052A0282017-02-15015 February 2017 NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs ML16319A4282016-11-14014 November 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15 ML16300A2662016-10-21021 October 2016 Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage IR 05000482/20160022016-08-0303 August 2016 NRC Integrated Inspection Report 05000482/2016002 ML16110A3722016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16020A1392016-01-15015 January 2016 Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information ML15135A4862015-05-14014 May 2015 Wc 2015007 17T RFI ML15082A0052015-03-27027 March 2015 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15079A0762015-03-23023 March 2015 Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML15040A6252015-02-10010 February 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14323A5742014-12-0404 December 2014 Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR ML14230A7572014-08-21021 August 2014 Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML14206A0122014-08-0101 August 2014 Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14197A3362014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval ML14148A3872014-06-0202 June 2014 Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 6, 2010 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 WOLF CREEK GENERATING STATION -LICENSE AMENDMENT REQUEST FOR USE OF FIRE-RESISTIVE ELECTRICAL CABLE (TAC NO. ME2966)
Dear Mr. Sunseri:
By letter dated December 16, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093641 067), Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request (LAR) to make changes to the approved fire protection program as described in the Wolf Creek Generating Station (WCGS) Updated Safety Analysis Report (USAR). Specifically, a deviation from certain technical commitments to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix R.Section III.G.2, as described in Appendix 9.5E of the WCGS USAR, is requested regarding the use of fire-resistive cable at WCGS for certain power and control cables associated with two motor-operated valves on the Train B Component Cooling Water System. Based on its review, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete its evaluation of the LAR. The enclosure to this letter provides the staff request for additional information (RAI) that was sent to Ms. Diane Hooper of WCNOC via e-mail on March 26 and 31, 2010, and discussed with WCNOC staff on April 20, 2010. It was agreed that WCNOC will provide its RAI response within 30 days from the date of issuance of this letter. The NRC staff considers that timely responses to RAls help ensure sufficient time is available for the staff to complete its review and contribute toward the NRC's goal of efficient and effective use of staff resources.
M. Sunseri -2 If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Sincerely, Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 Enclosure As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR USE OF FIRE-RESISTIVE ELECTRICAL CABLES WOLF CREEK GENERATING STATION DOCKET NO. 50-482 By letter dated December 16,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093641 067), Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request (LAR) to make changes to the approved fire protection program as described in the Wolf Creek Generating Station (WCGS) Updated Safety Analysis Report (USAR). Specifically, a deviation from certain technical commitments to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix R,Section III.G.2, as described in Appendix 9.5E of the WCGS USAR, is requested regarding the use of fire-resistive cable at WCGS for certain power and control cables associated with two motor-operated valves on the Train B Component Cooling Water System. Based on its review, the U.S. Nuclear Regulatory Commission (NRC) has determined that the following additional information is required to complete its evaluation of the LAR. Fire Protection Branch The licensee states in its application that the proposed change"...will not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire." If the proposed installation would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire, please explain why the change would not fall under WCGS License Condition 2.C(5)(b). Please provide a detailed summary of the analysis that demonstrates that the installed configurations will be bounded by the tested configurations with respect to electrical properties (voltage, current, conductor size, number of conductors, etc.) of the installed cables. The summary provided should include a discussion of key assumptions, methods, results, and conclusions. In its application dated December 16, 2009, the licensee states that, WCNOC is proposing to route the new fire-resistive cable from the valves to the motor control center, which would include installation of the cable in Fire Areas A-16 and A-21.
[Attachment I, page 3 of 13] Does this indicate that the Meggitt cable is to be installed in all three (A-16, A-21, and A-27) fire areas? If so, please elaborate on the planned installation of Meggitt cable in fire areas A-16 and A-21. Enclosure
-Do fire areas A-16 and A-21 require the same fire rating for the Meggitt cables that are proposed to be installed as the fire rating that is required in fire area A-27? If the fire resistance of the Meggitt cable is not required in the additional fire areas, please describe why the Meggitt is being installed in the additional areas. If the Meggitt is not to be installed in the additional fire areas, please clearly describe what will be installed in each of the three fire areas. In several places in its application, the licensee describes the use of Meggitt cable for 1-hour fire-rated applications.
Examples include: This testing demonstrated that the cable is capable of providing an equivalent level of protection as would be provided by a 3-hour and 1-hour rated fire barrier as described by Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix R,Section III.G.2. [Attachment I, page 5 of 13] The WCGS design specifies that fire-resistive cables required to only withstand a 1-hour fire are to be routed with the most practical routes along walls and ceilings.
Fire detectors and automatic fire suppression systems are installed in the 1-hour fire areas, which mitigate the possibility of damage from equipment or material failing and falling onto the fire-resistive cable. [Attachment I, page 6 of 13] The 600 volt fire-resistive control and power cables are type tested to 1925°F to verify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire ratings, and to verify environmental qualifications in accordance with NRC Generic Letter 86-10, Supplement
- 1. [Attachment II, page 10 of 17] Fire-resistive cable, which has been successfully tested per the requirements of U.S. Nuclear Regulatory Commission (NRC) Generic Letter 86-10, Supplement 1, may be used in lieu of the rated fire barrier requirement in III.G.2.a and c. [Attachment II, page 17 of 17] However, the majority of the application describes a specific 3-hour fire-rated installation. Does the licensee also intend to install the Meggitt cable in lieu of 1-hour rated barriers, or in other 3-hour rated applications? If so, please describe these additional applications in detail. If not, the application should be amended to remove references to other installations.
-3On page 8.3-29 of its application, related to the proposed modification to the WCGS USAR, the licensee states: Openings in solid floors for vertical runs of cables are sealed with fire resistant material with the exception of 600 volt fire-resistive control and power cables which are routed independent of raceways.
[Attachment II to the application, page 12 of 17] Please describe in detail the relationship between this change and the requested licensing action. If there is no relationship, please retract this change from the application or explain why it is appropriate. If this change is related to the application, please provide a detailed summary of the plant-specific analyses that demonstrates the acceptability of unsealed openings in fire area boundaries, and other rated barriers, related to Meggitt cables, as described above. The summary provided should include a discussion of key assumptions, methods, results, and conclusions. In the Regulatory Evaluation section of the application, the licensee states: Paragraph (e) states "Nuclear power plants licensed to operate after January 1, 1979, shall...satisfy Criterion 3 of Appendix A to this part in accordance with the provisions of their licenses." [Attachment I, page 11 of 13] Paragraph 50.48(e) of 10 CFR is no longer in force, and was removed nearly 10 years ago (65 FR 38190, June 20,2000). Please revise the Regulatory Evaluation to ensure that only currently in-force regulations are referenced, or provide an explanation for the use of obsolete references.
In addition, please ensure that the descriptions of regulation sections are accurate (e.g., the description of the 10 CFR III.G.2. requirements). In its application, the licensee references a precedent, but does not relate the precedent to its different licensing basis for WCGS: Amendment No. 123 to Shearon Harris Nuclear Power Plant, Unit 1 Facility Operating License No. NPF-62 approved the use of fire-resistive electrical cables in lieu of alternatives specified in Section C5.b.2 of Branch Technical Position Chemical Engineering Branch 9.5-1 for certain volume control tank outlet valves. Please revise the discussion to clearly relate the requirements that the precedent is satisfying to those in the WCGS licensing basis that are of concern in the current application.
-In its application, the licensee proposed an addition to the WCGS Fire Hazard Analysis (FHA), page 17 of 274: Safety-related cable in the general plant area is qualified to Institute of Electrical and Electronics Engineers (IEEE) 383-1974.
All single conductors inside control panels meet the flame resistance requirements of Insulated Power Cable Engineers Association (IPCEA) S-19-81 or S-61-402, or Military Specification MIL-W-810044B3." [Attachment III, page 5 of 27] Please describe in detail the relationship between this change and the requested licensing action. If there is no relationship, please retract this change from the application, or explain why it is appropriate.
Electrical Engineering Branch On page 3 of the LAR, the licensee stated: The cables are purchased as safety related, seismically-qualified, environmentally-qualified, Class 1 E cables, which meet the 3-hour fire endurance rating when tested per the requirements of Supplement 1 to Generic Letter 86-10, "Implementation of Fire Protection Requirements," (Reference 6.1). For the proposed application, the cables are not used in a harsh environment and therefore, are not required to be environmentally qualified.
However, as noted on page 5 of Attachment II to the LAR, the licensee proposed adding the new fire-resistive cables to Table 3.11 (B)-3 (Sheet 68) of Section 3.11 of WCGS's USAR. Specifically, these cables are described as being required to function during a high energy line break accident (as denoted by the letter 'A' in the Category column). Please explain the apparent discrepancy. This question is only applicable if the new fire-resistive cables are required to meet NRC's environmental qualification requirements.
On page 5 of the LAR, the licensee stated: The cables are type Si2400 manufactured by Meggitt Safety Systems, Inc. This cable has demonstrated that it is capable of operating continuously for three hours during the most severe design basis fire, and it satisfies the other design considerations such as environmental qualification, seismic, and electrical characteristics. Please provide a summary of your environmental qualification technical analysis.
In your response, provide details that demonstrate that the new fire-resistive cables will perform their design function under postulated design bases events
-5 (i.e., loss-of-coolant accident, high energy line break, and main steam line break). Also, please provide the environmental qualification profiles for each . area that these cables will be located to show that the new fire-resistive cables will be bounded by the original assumptions.
- b. Please describe whether the conventional cables that the new fire-resistive cables will be connected to are environmentally qualified.
- c. Please describe the impact of connecting (i.e., splicing) the new fire-resistive cables to the existing conventional cables (i.e., the impact on both the new resistive cables and the conventional cables) on the environmental qualification of each type of cable. d. Please describe whether the splices and supports are environmentally qualified.
- e. Please describe how the new fire-resistive cables will be protected from water and chemical sprays.
M. Sunseri -2 If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Docket No. 50-482 Enclosure As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV rlf RidsAcrsAcnw_MailCTR Resource RidsNrrDeEeeb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrDraAfpb Resource RidsNrrPMWolfCreek Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CMoulton, NRR/DRAJAFPB MMcConnell, NRR/DE/EEEB LGibson, NRR/DORLlLPL4 ADAMS Accession No.: ML101100628 Sincerely, IRAJ Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- Memo dated 4/22/10 **Memo dated 3/31/10 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlDE/EEEB/BC NRRlDRAlAFPB/BC NRRlLPL4/BC NRRlLPL4/PM NAME BSingal JBurkhardt GWilson**
AKlein* MMarkley CFLyon for BSingal DATE 4/22/10 4/21/10 3/31/10 4/22/10 5/4110 5/6/10