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| If the cause of inoperability exists on the other DG, it would be declared inoperable upon discovery and Condition F of LCO 3.8.1 would be entered. Additionally, page 7 of 12 of the license amendment request (LAR) submittal, Section 3.6, Evaluation, states in part: In GL [Generic Letter] 93-05 [Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation | | If the cause of inoperability exists on the other DG, it would be declared inoperable upon discovery and Condition F of LCO 3.8.1 would be entered. Additionally, page 7 of 12 of the license amendment request (LAR) submittal, Section 3.6, Evaluation, states in part: In GL [Generic Letter] 93-05 [Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation |
| -Generic Letter 93-05"], the NRC [U.S. Nuclear Regulatory Commission] | | -Generic Letter 93-05"], the NRC [U.S. Nuclear Regulatory Commission] |
| staff stated that, in performing the study documented in NUREG-1366 | | staff stated that, in performing the study documented in NUREG-1366 |
| ["Improvements to Technical Specifications | | ["Improvements to Technical Specifications |
| -3 Surveillance Requirements," dated December 1992], the safety can be improved, equipment degradation | | -3 Surveillance Requirements," dated December 1992], the safety can be improved, equipment degradation |
| [de]creased, and unnecessary burden on personnel eliminated by reducing the frequency of certain testing required in the TS during power operation. | | [de]creased, and unnecessary burden on personnel eliminated by reducing the frequency of certain testing required in the TS during power operation. |
| The changes eliminate testing that is likely to cause transients or excessive wear of equipment." Question 3 Based on WCGS TS 3.8 Bases and the excerpt taken from the LAR, please explain why performance of a common cause failure determination on the OPERABLE DG, currently allowed by the WCGS TS as an alternative to performance of TS SR 3.8.1.2, does not provide a reasonable alternative to verify OPERABILITY of the opposite train DG and, therefore, the intent of GL 93-05. | | The changes eliminate testing that is likely to cause transients or excessive wear of equipment." Question 3 Based on WCGS TS 3.8 Bases and the excerpt taken from the LAR, please explain why performance of a common cause failure determination on the OPERABLE DG, currently allowed by the WCGS TS as an alternative to performance of TS SR 3.8.1.2, does not provide a reasonable alternative to verify OPERABILITY of the opposite train DG and, therefore, the intent of GL 93-05. |
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MONTHYEARML0935800682009-12-23023 December 2009 Acceptance Review E-mail License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating. Project stage: Acceptance Review ML1006105042010-03-12012 March 2010 Request for Additional Information, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating, for Note, Required Actions and Completion Times Project stage: RAI WO 10-0013, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating2010-04-0606 April 2010 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating Project stage: Response to RAI WO 10-0053, Letter Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating.2010-08-10010 August 2010 Letter Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating. Project stage: Withdrawal ML1022502062010-08-20020 August 2010 Notice of Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating, for Note, Required Actions and Completion Times Project stage: Withdrawal ML1022501962010-08-20020 August 2010 Letter, Notice of Withdrawal of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating, for Note, Required Actions and Completion Times Project stage: Withdrawal 2010-04-06
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Category:Letter
MONTHYEAR05000482/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 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 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 ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) 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 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 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 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 ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations 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 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 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 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)) 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 March 12, 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 -REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST FOR REVISION TO TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES -OPERATING" (TAC NO. ME2675)
Dear Mr. Sunseri:
By letter dated November 20, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093310430), Wolf Creek Nuclear Operating Corporation (WCNOC, the license) requested approval to revise Technical Specification (TS) 3.8.1, "AC [Alternating Current] Sources -Operating." The licensee is proposing to add a note to Required Actions B.3.1 and B.3.2 to indicate that the TS 3.8.1 Required Actions B.3.1 and B.3.2 are satisfied if the diesel generator (DG) becomes inoperable due to an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing. The licensee has also proposed to revise the Completion Time for Required Actions B.3.1 and B.3.2 to specify a Completion Time based on the time from discovery of an issue requiring common cause failure determination.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that additional information is needed in order to complete the review. A draft copy of the request for additional information (RAI) was forwarded to Ms. Diane Hooper of your staff on February 3, 2010, via e-mail. Mr. Steve Wideman of your staff confirmed on February 16, 2010, that WCNOC staff understands the request and no further clarifications are needed. Mr. Wideman also agreed to provide the final RAI response within 30 days from the date of this letter.
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, b lAs k:S, Balwant K. Singal, Senior Project Manager 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 TECHNICAL SPECIFICATIONS 3.8.1, "AC SOURCES OPERATING" WOLF CREEK GENERATING STATION WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 The Wolf Creek Generating Station (WCGS) Technical Specification (TS), 1.3, "Completion Times," DESCRIPTION, states the following:
The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO [Limiting Condition for Operation].
Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.
Question 1a Given the eXisting Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, please explain how the proposed revision to the Completion Time for Required Actions B.3.1 and B.3.2 of TS 3.8.1 is compliant with WCGS TS LCO 3.0.2, and consistent with the TS 1.3, Completion Time, time of discovery description.
Question 1b Please explain the unique WCGS design requiring the proposed Completion Time change for performance of LCO 3.8.1, Condition B, Required Actions B.3.1 and B.3.2. The WCGS TS 1.1, "Definitions," defines OPERABLE--OPERABILITY as follows: A system, subsystem, train, component, or device shall be OPERABLE have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, normal or emergency electrical power, cooling and seal water, and other auxiliary equipment that are required for the subsystem, train, component, or device to perform its specified function(s) are also capable of performing their related Enclosure
-2 The objective of LCO 3.8.1, Required Actions B.3.1 and B.3.2 is to ensure that a failure of a diesel generator (DG) does not affect the opposite train DG capability to perform its specified safety function(s) (Le., verify OPERABILITY of the opposite train DG). Question 2a Please explain how the term OPERABILITY, as defined by WCGS TS 1.1, will be determined for the OPERABLE DG with the proposed note stating: "Not applicable if result of support system, independently testable component, or preplanned preventative maintenance or testing." Question 2b Please explain how it can be ensured that a failure of a DG support system or independently testable component does not affect the OPERABILITY of the opposite train DG if the Required Actions of 3.8.1, Condition B, Required Actions B.3.1 or B.3.2 are not performed as currently required.
Question 2c Please state what specific DG support instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment, that are required for the DG perform its specified safety function(s), will be covered by the proposed exception to TS 3.8.1 Condition B, Required Actions B.3.1 and B.3.2. Question 2d Please identify all "issues" affecting DG OPERABILITY that would not require a common cause failure determination and, for each issue, explain how TS OPERABILITY is met as defined above. 3. The WCGS TS Bases 3.8.1, Condition B, Required Actions B.3.1 and B.3.2 state: Required Action 8.3.1 provides an allowance to avoid unnecessary testing of OPERABLE DG. If it can be determined that the cause of the inoperable DG does not exist on the OPERABLE DG, SR [Surveillance Requirement]
3.8.1.2 does not have to be performed.
If the cause of inoperability exists on the other DG, it would be declared inoperable upon discovery and Condition F of LCO 3.8.1 would be entered. Additionally, page 7 of 12 of the license amendment request (LAR) submittal, Section 3.6, Evaluation, states in part: In GL [Generic Letter] 93-05 [Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
-Generic Letter 93-05"], the NRC [U.S. Nuclear Regulatory Commission]
staff stated that, in performing the study documented in NUREG-1366
["Improvements to Technical Specifications
-3 Surveillance Requirements," dated December 1992], the safety can be improved, equipment degradation
[de]creased, and unnecessary burden on personnel eliminated by reducing the frequency of certain testing required in the TS during power operation.
The changes eliminate testing that is likely to cause transients or excessive wear of equipment." Question 3 Based on WCGS TS 3.8 Bases and the excerpt taken from the LAR, please explain why performance of a common cause failure determination on the OPERABLE DG, currently allowed by the WCGS TS as an alternative to performance of TS SR 3.8.1.2, does not provide a reasonable alternative to verify OPERABILITY of the opposite train DG and, therefore, the intent of GL 93-05.
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, IRA! Balwant K. Singal, Senior Project Manager 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 DISTRI BUTION: PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDeEeeb Resource RidsNrrDirsltsb Resource RidsNrrDorlLpl4 Resource RidsNrrPMWolfCreek Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GWaig, NRRIDIRS/ITSB KMiller, NRRIDE/EEEB ADAMS Accession No.: ML 100610504 Memo dated 2/22/10 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRIITSB/BC NRR/LPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt RElliotl*
MMarkley BSingal DATE 3/11/10 3/9110 2/22/10 3/12/10 3/12/10 OFFICIAL RECORD