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| | number = ML14006A218 | | | number = ML14006A218 |
| | issue date = 01/13/2014 | | | issue date = 01/13/2014 |
| | title = Wolf Creek - Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test (TAC No. ME9603) | | | title = Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Sunseri M W | | | addressee name = Sunseri M |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
| | docket = 05000482 | | | docket = 05000482 |
| | license number = NPF-042 | | | license number = NPF-042 |
| | contact person = Lyon C F | | | contact person = Lyon C |
| | case reference number = TAC ME9603 | | | case reference number = TAC ME9603 |
| | document type = Letter, Technical Specifications | | | document type = Letter, Technical Specifications |
| | page count = 5 | | | page count = 5 |
| | project = TAC:ME9603 | | | project = TAC:ME9603 |
| | stage = | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Matthew W. Sunseri UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 13, 2014 President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 SUBJECT: WOLF CREEK GENERATING STATION-CORRECTION TO TECHNICAL SPECIFICATION PAGE ISSUED FOR AMENDMENT NO. 206, REVISE TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES-OPERATING" (TAC NO. ME9603) Dear Mr. Sunseri: By letter dated December 2, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13282A147), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 206 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment increased the voltage limit for the emergency diesel generator full load rejection test specified by Technical Specification (TS) 3.8.1, "AC [Alternating Current] Sources-Operating," Surveillance Requirement 3.8.1.1 0. On December 31, 2013, your staff identified that the newTS page 3.8-9 issued with Amendment No. 206 did not include changes to the page issued with Amendment No. 204. Please find enclosed a replacement TS page 3.8-9 for Amendment No. 206. This correction does not change any of the NRC staffs conclusions in the safety evaluation associated with the amendment. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 13, 2014 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 |
| M. Sunseri -2-The remainder of the letter and the enclosure were correct. I apologize for any inconvenience due to the error. If you have any questions, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov. Docket No. 50-482 Enclosure: Revised TS page 3.8-9 cc w/encl: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENCLOSURE REVISED TECHNICAL SPECIFICATION PAGE 3.8-9 FOR AMENDMENT NO. 206 ISSUED DECEMBER 2, 2013 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) SR 3.8.1.7 SR 3.8.1.8 SR 3.8.1.9 SR 3.8.1.10 Wolf Creek -Unit 1 SURVEILLANCE --------------------------------N 0 T E ----------------------------------All DG starts may be preceded by an engine prelube period. Verify each DG starts from standby condition and achieves: a. In :S; 12 seconds, voltage 3950 V and frequency 59.4 Hz; and b. Steady state voltage 3950 V and :S; 4320 V, and 59.4 Hz and :S; 60.6 Hz. Not Used. Not Used. FREQUENCY 184 days Verify each DG operating at a power factor :S; 0.9 and 18 months 0.8 does not trip and voltage is maintained :S; 4992 V and frequency is maintained :S; 65.4 Hz during and following a load rejection 5650 kW and :S; 6201 kW. (continued) 3.8-9 Amendment No. 123, 154, 161, 163, ;w.4,206 M. Sunseri -2 -The remainder of the letter and the enclosure were correct. I apologize for any inconvenience due to the error. If you have any questions, please contact me at 301-415-2296 or via e-mail at fred .lyon@nrc.gov. Docket No. 50-482 Enclosure: Revised TS page 3.8-9 cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV-1 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMWolfCreek Resource RidsRgn4MaiiCenter Resource ADAMS Accession No* ML 14006A218 .. Sincerely, IRA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DORLILPL4-1 /BC NRR/DORL!LPL4-1/PM NAME Flyon JBurkhardt* MMarkley Flyon DATE 1/13/14 1/10/14 1/13/14 1/13/14 OFFICIAL RECORD COPY | | |
| }} | | ==SUBJECT:== |
| | WOLF CREEK GENERATING STATION- CORRECTION TO TECHNICAL SPECIFICATION PAGE ISSUED FOR AMENDMENT NO. 206, REVISE TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES- OPERATING" (TAC NO. ME9603) |
| | |
| | ==Dear Mr. Sunseri:== |
| | |
| | By letter dated December 2, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13282A147), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 206 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment increased the voltage limit for the emergency diesel generator full load rejection test specified by Technical Specification (TS) 3.8.1, "AC [Alternating Current] Sources- Operating," Surveillance Requirement 3.8.1.1 0. |
| | On December 31, 2013, your staff identified that the newTS page 3.8-9 issued with Amendment No. 206 did not include changes to the page issued with Amendment No. 204. |
| | Please find enclosed a replacement TS page 3.8-9 for Amendment No. 206. This correction does not change any of the NRC staffs conclusions in the safety evaluation associated with the amendment. |
| | |
| | M. Sunseri The remainder of the letter and the enclosure were correct. I apologize for any inconvenience due to the error. If you have any questions, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov. |
| | Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 |
| | |
| | ==Enclosure:== |
| | |
| | Revised TS page 3.8-9 cc w/encl: Distribution via Listserv |
| | |
| | ENCLOSURE REVISED TECHNICAL SPECIFICATION PAGE 3.8-9 FOR AMENDMENT NO. 206 ISSUED DECEMBER 2, 2013 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 |
| | |
| | AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) |
| | SURVEILLANCE FREQUENCY SR 3.8.1.7 --------------------------------N0 T E---------------------------------- |
| | All DG starts may be preceded by an engine prelube period. |
| | Verify each DG starts from standby condition and 184 days achieves: |
| | : a. In :S; 12 seconds, voltage ~ 3950 V and frequency |
| | ~ 59.4 Hz; and |
| | : b. Steady state voltage ~ 3950 V and :S; 4320 V, and frequency~ 59.4 Hz and :S; 60.6 Hz. |
| | SR 3.8.1.8 Not Used. |
| | SR 3.8.1.9 Not Used. |
| | SR 3.8.1.10 Verify each DG operating at a power factor :S; 0.9 and 18 months |
| | ~ 0.8 does not trip and voltage is maintained :S; 4992 V and frequency is maintained :S; 65.4 Hz during and following a load rejection of~ 5650 kW and :S; 6201 kW. |
| | (continued) |
| | Wolf Creek - Unit 1 3.8-9 Amendment No. 123, 154, 161, 163, |
| | ;w.4,206 |
| | |
| | * .. ML14006A218 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DORLILPL4-1 /BC NRR/DORL!LPL4-1/PM NAME Flyon JBurkhardt* MMarkley Flyon DATE 1/13/14 1/10/14 1/13/14 1/13/14}} |
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MONTHYEARET 12-0018, License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement2012-09-19019 September 2012 License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement Project stage: Request ML12286A0452012-10-11011 October 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test Project stage: Acceptance Review ML13149A1602013-05-31031 May 2013 Request for Additional Information, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test Project stage: RAI ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test Project stage: Approval ML14006A2182014-01-13013 January 2014 Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test Project stage: Other 2013-12-02
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Category:Letter
MONTHYEARML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 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 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 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 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 ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report 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 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 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 2024-09-06
[Table view] Category:Technical Specifications
MONTHYEARML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 – Post Accident Monitoring (PAM) Report ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18093A9142018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Chapter 16, Technical Requirements Manual (Relocated Technical Specifications) ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation WO 15-0045, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2015-07-27027 July 2015 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML14006A2182014-01-13013 January 2014 Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test WO 13-0089, Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-12-17017 December 2013 Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 WO 10-0066, Correction of Typographical Error in Technical Specification 5.7.22010-10-21021 October 2010 Correction of Typographical Error in Technical Specification 5.7.2 ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-12010-04-13013 April 2010 Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 WO 10-0010, Updated Safety Analysis Report, Revision 232010-03-11011 March 2010 Updated Safety Analysis Report, Revision 23 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).2008-07-10010 July 2008 Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). ML0808400052008-04-0404 April 2008 Tech Pages for Amendment 178, Revision to Technical Specification 5.5.9 on the Steam Generator Program ML0803701212008-04-0303 April 2008 Tech Spec Pages for Amendment No. 177, Revise TS 3.3.2, ESFAS and TS 3.7.3, Main Feedwater Isolation Valves by Addition of Main Feedwater Regulating Valves and Associated Bypass Valves ML0729700282008-03-0303 March 2008 Tech Spec Pages for Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1 ML0720603282007-08-28028 August 2007 Tech Spec Pages for Amendment 174 Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program ML0705500202007-04-17017 April 2007 Tech Spec Pages for License Amendment No. 173 Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement2007-03-14014 March 2007 Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement ET 06-0053, Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-15015 December 2006 Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0631202612006-11-0707 November 2006 Tech Spec Pages for Amendment 171 Regarding Addition of Actuator Trains to Main Steam and Feedwater Isolation Valves Technical Specifications ML0630502562006-10-31031 October 2006 Technical Specifications, Revision to Reactor Coolant System Specific Activity ML0627201792006-09-28028 September 2006 Tech Spec Pages for Amendment 167 Regarding Extended Containment Isolation Valve Completion Times ML0627000632006-09-26026 September 2006 Tech Spec Pages for Amendment 166 Regarding Changes to the Reactor Coolant System (RCS) Leakage Detection Instrumentation Methodology ET 06-0026, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.2006-06-30030 June 2006 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program. ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-06-26026 June 2006 Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ML0612804712006-05-0808 May 2006 Tech Spec Pages for Amendment 164, Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0611702372006-04-26026 April 2006 Technical Specifications, Extended Diesel Generator Completion Times ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program2006-02-21021 February 2006 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program 2024-02-27
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 13, 2014 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION- CORRECTION TO TECHNICAL SPECIFICATION PAGE ISSUED FOR AMENDMENT NO. 206, REVISE TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES- OPERATING" (TAC NO. ME9603)
Dear Mr. Sunseri:
By letter dated December 2, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13282A147), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 206 to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment increased the voltage limit for the emergency diesel generator full load rejection test specified by Technical Specification (TS) 3.8.1, "AC [Alternating Current] Sources- Operating," Surveillance Requirement 3.8.1.1 0.
On December 31, 2013, your staff identified that the newTS page 3.8-9 issued with Amendment No. 206 did not include changes to the page issued with Amendment No. 204.
Please find enclosed a replacement TS page 3.8-9 for Amendment No. 206. This correction does not change any of the NRC staffs conclusions in the safety evaluation associated with the amendment.
M. Sunseri The remainder of the letter and the enclosure were correct. I apologize for any inconvenience due to the error. If you have any questions, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Revised TS page 3.8-9 cc w/encl: Distribution via Listserv
ENCLOSURE REVISED TECHNICAL SPECIFICATION PAGE 3.8-9 FOR AMENDMENT NO. 206 ISSUED DECEMBER 2, 2013 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.7 --------------------------------N0 T E----------------------------------
All DG starts may be preceded by an engine prelube period.
Verify each DG starts from standby condition and 184 days achieves:
- a. In :S; 12 seconds, voltage ~ 3950 V and frequency
~ 59.4 Hz; and
- b. Steady state voltage ~ 3950 V and :S; 4320 V, and frequency~ 59.4 Hz and :S; 60.6 Hz.
SR 3.8.1.8 Not Used.
SR 3.8.1.9 Not Used.
SR 3.8.1.10 Verify each DG operating at a power factor :S; 0.9 and 18 months
~ 0.8 does not trip and voltage is maintained :S; 4992 V and frequency is maintained :S; 65.4 Hz during and following a load rejection of~ 5650 kW and :S; 6201 kW.
(continued)
Wolf Creek - Unit 1 3.8-9 Amendment No. 123, 154, 161, 163,
- w.4,206
- .. ML14006A218 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DORLILPL4-1 /BC NRR/DORL!LPL4-1/PM NAME Flyon JBurkhardt* MMarkley Flyon DATE 1/13/14 1/10/14 1/13/14 1/13/14