Letter Sequence Request |
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TAC:ME7110, Control Room Habitability, Administratively Control Containment Penetrations, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
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MONTHYEARML11222A1232011-07-25025 July 2011 License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Request ML11252A5212011-08-30030 August 2011 License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Request ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 Project stage: Request ML11252A6542011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating Technical Specifications Bases Pages, Attachment 3 Project stage: Request ML11252A6562011-08-30030 August 2011 License Amendment Request 244, Radiological Accident Analysis and Discussion of Associated Technical Specification Changes, Attachment 4 Project stage: Request ML11252A6572011-08-30030 August 2011 License Amendment Request 244, Evaluation of New Proposed Manual Actions, Attachment 5 Project stage: Request ML11252A6582011-08-30030 August 2011 License Amendment Request 244, Data Files, Kewaunee Power Station Meterological Data 2002-2006 X/Q Calculation Support, Enclosure 1 Project stage: Request ML11252A6512011-08-30030 August 2011 License Amendment Request 244, Discussion of Change, Safety Evaluation, Significant Hazards Determination and Environmental Considerations, Attachment 1 Project stage: Request ML11290A1482011-10-17017 October 2011 NRR E-mail Capture - ME7110 - Chi-over-Q Amendment Application - Non-acceptance with Opportunity to Supplement Project stage: Other ML11298A2652011-10-25025 October 2011 NRR E-mail Capture - FW: ME7110 - Kewaunee Chi-over-Q - Acceptance Review RAL Items - Conference Calls of October 20, 25, 2011 Project stage: Acceptance Review ML11304A1462011-10-27027 October 2011 NRR E-mail Capture - FW: ME7110 - Kewaunee Chi-over-Q - Acceptance Review RAL Items - Conference Calls of October 20, 25, 26, 2011 Project stage: Acceptance Review ML11318A2052011-11-0808 November 2011 Response to Request for Additional Information: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML11325A0782011-11-18018 November 2011 NRR E-mail Capture - ME7110 - Kewaunee - LIC-109 Acceptance Review Results for Chi-over-Q License Amendment Request Project stage: Acceptance Review ML11339A0012011-12-0101 December 2011 NRR E-mail Capture - ME7110 Kewaunee Amendment Request Re_ Chi-over-Q - Eicb Request for Additional Information (RAI) Project stage: RAI ML12023A0472012-01-0909 January 2012 NRR E-mail Capture - ME7110 Kewaunee Amendment Request Re_ Chi-over-Q - Ahpb Request for Additional Information (RAI) Project stage: RAI ML12023A0572012-01-13013 January 2012 NRR E-mail Capture - ME7110 Kewaunee Amendment Request Re_ Chi-over-Q - Ahpb Request for Additional Information (RAI) - Firm RAI Items Project stage: RAI ML12031A1382012-01-25025 January 2012 Response to Request for Additional Information on License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12033A0102012-01-30030 January 2012 NRR E-mail Capture - ME7110 Kewaunee Amendment Request Chi-over-Q - Rsxb Request for Additional Information (RAI) Project stage: RAI ML12068A1422012-02-27027 February 2012 Response to Request for Additional Information: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12066A0082012-03-0202 March 2012 NRR E-mail Capture - ME7110 Kewaunee Amendment Request- Chi-over-Q - Aadb Request for Additional Project stage: Other ML12068A4202012-03-0606 March 2012 E-mail Capture - ME7110 Record of Clarification Conference Call for ME7110 Kewaunee Amendment Request Re_ Chi-over-Q - Aadb Request for Additional Information (RAI) Project stage: RAI ML12080A2232012-03-12012 March 2012 Response to Request for Additional Information: License Amendment Request 244. Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12107A1442012-04-13013 April 2012 NRR E-mail Capture - ME7110 Kewaunee - Request for Additional Information (RAI) Aadb and Scvb 2012-04-12 Project stage: RAI ML12124A2832012-04-30030 April 2012 Response to Request for Additional Information: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12138A0072012-05-15015 May 2012 NRR E-mail Capture - ME7110 Scvb Draft RAI Set Adoption of TSTF-51 & TSTF- 448, as Part of Chi-over-Q Action Project stage: Draft RAI ML12137A0032012-05-15015 May 2012 NRR E-mail Capture - ME7110 Agenda for Draft RAI Clarification Call Re Wednesday 3-4 PM ET - Eicb Input Project stage: Draft RAI ML12164A3742012-06-0606 June 2012 Response to Request for Additional Information: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12166A0062012-06-13013 June 2012 NRR E-mail Capture - ME7110 - Kewaunee - Chi-Over-Q - Record of Conference Call - Wednesday, June 13, 2012 3:00 PM Project stage: Other ML12193A6832012-06-19019 June 2012 NRR E-mail Capture - ME7110- Kewaunee LAR 244: Executive Summary of LRA Emergent Issue - Further Information - Generic Implications for Otherv Plants Project stage: Other ML12193A6842012-07-11011 July 2012 NRR E-mail Capture - Record of ME7110 - Kewaunee - Chi-Over-Q - Progress Review (Dated Wed 7/11/2012 3:00 PM - 4:00 PM from Outlook Invitation) Project stage: Other ML12219A2222012-08-0303 August 2012 Response to Request for Additional Information: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12226A5062012-08-0909 August 2012 Response to Request for Additional Information: License Amendment Request 244. Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Response to RAI ML12236A2062012-08-22022 August 2012 NRR E-mail Capture - FW: ME7110- Kewaunee LAR 244: Executive Summary of LRA Emergent Issue - Further Information - Generic Implications for Other Plants Project stage: Other ML12248A1492012-08-29029 August 2012 Submittal of Revision to Locked Rotor Radiological Accident Analysis: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications Project stage: Request ML12285A1572012-10-10010 October 2012 NRR E-mail Capture - ME7110 - Kewaunee - Chi-over-Q - Request for Additional Information (RAI) Project stage: RAI 2012-02-27
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Category:Report
MONTHYEARML20035C7592020-01-16016 January 2020 Redacted - Kewaunee, Request for Exemption from Certain Code of Federal Regulation Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML14126A0052014-04-29029 April 2014 Supplement 4 and Response to Request for Additional Information Regarding License Amendment Request 256, Permanently Defueled License and Technical Specifications ML14118A3822014-04-25025 April 2014 Revision to Post-Shutdown Decommissioning Activities Report ML13066A7802013-02-27027 February 2013 Non-Proprietary - Evaluation of Report Describing the Nature of an Estimated Effect on, Peak Cladding Temperature Resulting from a Significant Emergency Core Cooling System Evaluation Model Error ML12354A4962012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12181A2002012-06-21021 June 2012 Post Accident Monitoring Report ML11277A2402011-09-21021 September 2011 TAC ME7250 - Public - 7 Pages - Kewaunee Power Station License Amendment Request 250: Adoption of NFPA-805 Performance-based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML11255A1342011-08-31031 August 2011 Core Operating Limits Report Cycle 31 Revision 2 ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 ML11252A6572011-08-30030 August 2011 License Amendment Request 244, Evaluation of New Proposed Manual Actions, Attachment 5 ML11252A6582011-08-30030 August 2011 License Amendment Request 244, Data Files, Kewaunee Power Station Meterological Data 2002-2006 X/Q Calculation Support, Enclosure 1 ML11252A6512011-08-30030 August 2011 License Amendment Request 244, Discussion of Change, Safety Evaluation, Significant Hazards Determination and Environmental Considerations, Attachment 1 ML1108100712011-03-10010 March 2011 Core Operating Limits Report Cycle 31, Revision 0 ML1032104962010-11-0909 November 2010 Technical Report No. EE-0116 Revision 8, Allowable Values for North Anna Improved Technical Specifications Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications, Section 2.3 and 3.7 and Allowable Values for Ke ML1027001622010-09-23023 September 2010 Response to Request for Additional Information for the Review of the License Renewal Application ML1025714462010-09-0707 September 2010 Holistic Overview of GSI-191 Resolution for Kewaunee Power Station ML1023904192010-08-31031 August 2010 DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. ML1016102862010-05-11011 May 2010 Report No. 0900090.401, Rev. 0, 60-Year EAF Analyses Summary Report, Kewaunee Power Station Charging Nozzle & RCS Hot Leg Surge Nozzle. ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1027303972010-03-30030 March 2010 Allowable Values for North Anna Improved Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications (Cts), Sections 2.3 and 3.7, and Allowable Values for Kewaunee Power Station Improv ML1025714482010-02-0404 February 2010 Enclosure C-1 (RAI 8) Latent Debris Calculation C11928, Revision 0 ML0930701642009-10-15015 October 2009 Technical Report No. EE-0116, Revision 5 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0919705162009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure F, Archaeological and Cultural Resources ML0919705292009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure E, Non-Radiological Waste ML0919705152009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosure D, Hydrology Through ML0919705092009-07-0606 July 2009 Response to Request to Docket Information Related to the Environmental Site Audit, Enclosures D, Appendix a ML1011101282009-06-30030 June 2009 Enclosure 5 - WCAP-16643-NP, Revision 2, Kewaunee Power Station Heatup and Cooldown Limit Curves for Normal Operation ML0826903872008-09-19019 September 2008 Enclosure 1, License Amendment Request 239, Supplement 1 - Request for Review and Approval of Seismic Analysis Methodology for Auxiliary Building Crane ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0816204382008-06-0202 June 2008 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML0809802292008-04-0404 April 2008 Stations - Request for Approval of Appendix C of Fleet Report DOM-NAF-2 Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code ML0807001732008-03-0505 March 2008 U.S. Dept of Homeland Security/Final Report of the December 4, 2007, Radiological Emergency Preparedness Full Participation Plume Pathway Exercise for the Kewaunee Power Station/Report ML0731706782007-05-19019 May 2007 SCS-00684, Rev. Draft-2, Design Report, ASME Bp&V Section III, Class 3, SS-45S8-18622-NSR Ball Valve, SS-45XS8-18623-NSR Ball Valve, Enclosure 2 ML0710603922007-04-16016 April 2007 Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps.) ML0710201612007-03-29029 March 2007 Generator Tube Inspection Report ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0633906662006-12-0505 December 2006 Closure of Kewaunee Improvement Initiatives to Corrective Action Program ML0632504212006-11-14014 November 2006 Attachment 3, Submittal of Irradiated Reactor Vessel Surveillance Capsule Test Results for Capsule T Per 10 CFR 50 Appendix H ML0632504182006-10-31031 October 2006 Master Curve Assessment of Kewaunee Power Station Reactor Pressure Vessel Weld Metal, WCAP-16609-NP, Revision 0 ML0632504152006-10-31031 October 2006 Analysis of Capsule T from the Dominion Energy Kewaunee Power Station Reactor Vessel Radiation Surveillance Program, WCAP-16641-NP, Revision 0 ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0616604372006-06-20020 June 2006 Technical Report (TAC MC7897) on Third 10-Year Inservice Inspection Interval Request for Relief for Nuclear Management Company, LLC ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0603804892006-02-0606 February 2006 Closed Gc TAC Report (10/01/2005 - 12/31/2005) ML0536100952005-12-16016 December 2005 Appendix C - Fault Tree Analysis - Attachment 1 - Human Error Probabilities; Attachment 1:A - Human Error Probabilities ML0536100922005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 1, Revision 1 ML0536101002005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 2, Revision 1 ML0524403512005-08-25025 August 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report 2020-01-16
[Table view] Category:Technical
MONTHYEARML20035C7592020-01-16016 January 2020 Redacted - Kewaunee, Request for Exemption from Certain Code of Federal Regulation Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System ML11277A2402011-09-21021 September 2011 TAC ME7250 - Public - 7 Pages - Kewaunee Power Station License Amendment Request 250: Adoption of NFPA-805 Performance-based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML11252A6512011-08-30030 August 2011 License Amendment Request 244, Discussion of Change, Safety Evaluation, Significant Hazards Determination and Environmental Considerations, Attachment 1 ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 ML11252A6582011-08-30030 August 2011 License Amendment Request 244, Data Files, Kewaunee Power Station Meterological Data 2002-2006 X/Q Calculation Support, Enclosure 1 ML1032104962010-11-0909 November 2010 Technical Report No. EE-0116 Revision 8, Allowable Values for North Anna Improved Technical Specifications Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications, Section 2.3 and 3.7 and Allowable Values for Ke ML1023904192010-08-31031 August 2010 DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. ML1016102862010-05-11011 May 2010 Report No. 0900090.401, Rev. 0, 60-Year EAF Analyses Summary Report, Kewaunee Power Station Charging Nozzle & RCS Hot Leg Surge Nozzle. ML1027303972010-03-30030 March 2010 Allowable Values for North Anna Improved Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1, Setting Limits for Surry Custom Technical Specifications (Cts), Sections 2.3 and 3.7, and Allowable Values for Kewaunee Power Station Improv ML1025714482010-02-0404 February 2010 Enclosure C-1 (RAI 8) Latent Debris Calculation C11928, Revision 0 ML0930701642009-10-15015 October 2009 Technical Report No. EE-0116, Revision 5 ML1011101282009-06-30030 June 2009 Enclosure 5 - WCAP-16643-NP, Revision 2, Kewaunee Power Station Heatup and Cooldown Limit Curves for Normal Operation ML0826903872008-09-19019 September 2008 Enclosure 1, License Amendment Request 239, Supplement 1 - Request for Review and Approval of Seismic Analysis Methodology for Auxiliary Building Crane ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0809802292008-04-0404 April 2008 Stations - Request for Approval of Appendix C of Fleet Report DOM-NAF-2 Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code ML0731706782007-05-19019 May 2007 SCS-00684, Rev. Draft-2, Design Report, ASME Bp&V Section III, Class 3, SS-45S8-18622-NSR Ball Valve, SS-45XS8-18623-NSR Ball Valve, Enclosure 2 ML0710603922007-04-16016 April 2007 Request for Approval of Topical Report DOM-NAF-5, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (Kps.) ML0632504212006-11-14014 November 2006 Attachment 3, Submittal of Irradiated Reactor Vessel Surveillance Capsule Test Results for Capsule T Per 10 CFR 50 Appendix H ML0632504182006-10-31031 October 2006 Master Curve Assessment of Kewaunee Power Station Reactor Pressure Vessel Weld Metal, WCAP-16609-NP, Revision 0 ML0632504152006-10-31031 October 2006 Analysis of Capsule T from the Dominion Energy Kewaunee Power Station Reactor Vessel Radiation Surveillance Program, WCAP-16641-NP, Revision 0 ML0616604372006-06-20020 June 2006 Technical Report (TAC MC7897) on Third 10-Year Inservice Inspection Interval Request for Relief for Nuclear Management Company, LLC ML0536100952005-12-16016 December 2005 Appendix C - Fault Tree Analysis - Attachment 1 - Human Error Probabilities; Attachment 1:A - Human Error Probabilities ML0536101002005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 2, Revision 1 ML0536100922005-12-0101 December 2005 Safety Significance Evaluation of Kewaunee Power Station Turbine Building Internal Floods - Volume 1, Revision 1 ML0510803792005-05-27027 May 2005 Relief, Third and Fourth 10-Year Inservice Inspection Interval Program Requests for Relief ML0508105002005-03-0808 March 2005 Enclosure 2, NMCKWO02-RPT-01-05, Kewaunee Nuclear Power Plant Hatch Closure Task Assessment. ML0503502252005-02-18018 February 2005 Relief, Forth 10-Year Inservice Inspection Interval Program Requests for Relief ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0428903732004-09-30030 September 2004 Response to Request for Additional Information Related to Technical Letter Report on Fourth 10-Year Interval In-Service Inspection Request for Nuclear Management Co., LLC ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 ML0306901592003-02-27027 February 2003 Part 2, Kewaunee, NMC Responses to NRC Request for Additional Information Concerning License Amendment Request 187 ML0305202692003-02-15015 February 2003 Follow-up Report, Reference Event #39516 ML0922306202003-01-13013 January 2003 SIR-00-045, Revision 2, Leak-Before-Break Evaluation 6-Inch to 12-Inch Safety Injection and Residual Heat Removal Piping Attached to the RCS (Kewaunee Nuclear Plant), Enclosure D ML0302405652003-01-13013 January 2003 License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate, Attachments 1 - 4 ML0302204542003-01-13013 January 2003 License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate, Attachment 8 ML0302204302003-01-13013 January 2003 License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate, Attachments 5, 10 - 12 NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2020-01-16
[Table view] Category:Technical Specification
MONTHYEARML16097A4172016-03-29029 March 2016 Technical Specifications Bases Changes and Technical Requirements Manual Changes ML14106A4502014-04-0303 April 2014 Technical Specifications Bases Changes and Technical Requirements Manual Changes ML14009A3932014-01-0707 January 2014 Supplement 2: License Amendment Request 256, Permanently Defueled License and Technical Specifications ML13108A1832013-04-0505 April 2013 Technical Specifications Bases Changes and Technical Requirements Manual Changes ML12109A2302012-04-10010 April 2012 Technical Specifications Bases Changes and Technical Requirements Manual Changes ML11252A6562011-08-30030 August 2011 License Amendment Request 244, Radiological Accident Analysis and Discussion of Associated Technical Specification Changes, Attachment 4 ML11252A6542011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating Technical Specifications Bases Pages, Attachment 3 ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 ML1011206552010-04-14014 April 2010 Technical Specifications Bases Changes and Technical Requirements Manual Changes ML1011101232010-04-13013 April 2010 License Amendment Request 246: Revision to Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection Limitations ML0910607252009-04-0707 April 2009 Submittal of Technical Specifications Bases Changes and Technical Requirements Manual Changes ML0902602992009-01-23023 January 2009 License Amendment Request 247: Emergency Diesel Generator Fuel Oil Technical Specification Changes ML0823200832008-08-14014 August 2008 License Amendment Request 229, Change Technical Specifications to Require Testing Containment Purge and Vent Isolation Valves When the Reactor Is Above Cold Shutdown ML0810700722008-04-0808 April 2008 Transmittal of Technical Specifications Bases Changes and Technical Requirements Manual Changes ML0726201442007-09-14014 September 2007 License Amendment Request 210 - Technical Specification Modifications Regarding Control Room Envelope Habitability ML0712101852007-04-26026 April 2007 Supplement to License Amendment Request 230, Emergency Diesel Generator Short-Time Load Testing. ML0701200882007-01-10010 January 2007 License Amendment Request 230 Emergency Diesel Generator Short-Time Load Testing ML0624201332006-08-29029 August 2006 Tech Specs, Correction Amendment 188 ML0615601442006-06-0202 June 2006 Response to NRC Request for Additional Information Re License Amendment Request 218: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0604504872006-02-0606 February 2006 License Amendment Request - 219, One-Time Extension of Surveillance Requirements ML0602505242006-01-12012 January 2006 License Amendment Request 218 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0517200282005-06-20020 June 2005 (TS) Issuance of Amendment Auxiliary Feedwater System ML0505302282005-02-10010 February 2005 Response to NRC Request for Additional Information License Amendment Request 203 to the Kewaunee Nuclear Power Plant Technical Specifications, Rod Position Indication. ML0435800062004-12-22022 December 2004 Tech Specs - Issuance of Amendment Deletion of Requirements for Submittal of Occupational Radiation Exposure Reports, Reports of Challenges to and Failures of the Pressurizer Power Operated Relief Valves and Safety ML0427300902004-09-24024 September 2004 Technical Specification Pages for Amendment No. 177 Turbine Building Service Water Header Isolation (TS) S110810 ML0423904602004-08-18018 August 2004 Response to Request for Additional Information Related to License Amendment Request 197 to the Kewaunee Nuclear Power Plant Technical Specifications ML0421603022004-07-19019 July 2004 Bases Revision(S) to the Kewaunee Nuclear Power Plant Technical Specifications ML0416205032004-05-25025 May 2004 License Amendment Request 203 Re Technical Specifications on Rod Position Indication ML0413803552004-05-13013 May 2004 Amd No. 174, Tech Spec, Relocation of Requirements for Hydrogen Monitors ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0402901202004-01-16016 January 2004 License Amendment Request 201 to the Kewaunee Nuclear Power Plant Technical Specifications, Equipment Hatch and Control Room Post Accident Recirculation System. ML0335704692003-12-12012 December 2003 License Amendment Request 198, ILRT 5-Year Extension, NMC Response to NRC Request for Additional Information. ML0332505592003-11-20020 November 2003 Tech Spec Pages for Amendment No. 171, Revising the Reporting Requirements for the Discovery of Defective or Degraded Steam Generator Tubes ML0321706442003-07-25025 July 2003 Bases Revision(S) to the Kewaunee Nuclear Power Plant Technical Specifications ML0318206132003-06-20020 June 2003 License Amendment Request 198 to Kewaunee TS for One Time Extension of Containment Integrated Leak Rate Test Interval ML0316813912003-06-0909 June 2003 Bases Revisions to the Kewaunee Nuclear Power Plant Technical Specifications 4.4 and 4.12 ML0314205282003-05-15015 May 2003 Bases Revision(S) to the Kewaunee Nuclear Power Plant Technical Specifications ML0233803042002-11-22022 November 2002 License Amendment Request 189 to Kewaunee TS Regarding Modification of Diesel Generator Inspection Requirements ML0231104142002-10-29029 October 2002 Bases Revision to Kewaunee Nuclear Power Plant TS ML0214402322002-05-0707 May 2002 Proposed Amendment 180 Application for Technical Specification Change Re Missed Surveillance & Adoption of Technical Specifications Bases Control Program) Using Consolidated Line Item Improvement Process ML0208805202002-03-19019 March 2002 Bases Revision Technical Specifications 2.2, Safety Limit - Reactor Coolant System Pressure. ML0203103642002-01-0303 January 2002 Bases Revisions to the Kewaunee Power Plant Technical Specifications 2016-03-29
[Table view] Category:Amendment
MONTHYEARML11252A6562011-08-30030 August 2011 License Amendment Request 244, Radiological Accident Analysis and Discussion of Associated Technical Specification Changes, Attachment 4 ML11252A6532011-08-30030 August 2011 License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2 ML0823200832008-08-14014 August 2008 License Amendment Request 229, Change Technical Specifications to Require Testing Containment Purge and Vent Isolation Valves When the Reactor Is Above Cold Shutdown ML0726201442007-09-14014 September 2007 License Amendment Request 210 - Technical Specification Modifications Regarding Control Room Envelope Habitability ML0712101852007-04-26026 April 2007 Supplement to License Amendment Request 230, Emergency Diesel Generator Short-Time Load Testing. ML0624201332006-08-29029 August 2006 Tech Specs, Correction Amendment 188 ML0604504872006-02-0606 February 2006 License Amendment Request - 219, One-Time Extension of Surveillance Requirements ML0602505242006-01-12012 January 2006 License Amendment Request 218 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0517200282005-06-20020 June 2005 (TS) Issuance of Amendment Auxiliary Feedwater System ML0435800062004-12-22022 December 2004 Tech Specs - Issuance of Amendment Deletion of Requirements for Submittal of Occupational Radiation Exposure Reports, Reports of Challenges to and Failures of the Pressurizer Power Operated Relief Valves and Safety ML0427300902004-09-24024 September 2004 Technical Specification Pages for Amendment No. 177 Turbine Building Service Water Header Isolation (TS) S110810 ML0413803552004-05-13013 May 2004 Amd No. 174, Tech Spec, Relocation of Requirements for Hydrogen Monitors ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0402901202004-01-16016 January 2004 License Amendment Request 201 to the Kewaunee Nuclear Power Plant Technical Specifications, Equipment Hatch and Control Room Post Accident Recirculation System. ML0335704692003-12-12012 December 2003 License Amendment Request 198, ILRT 5-Year Extension, NMC Response to NRC Request for Additional Information. ML0332505592003-11-20020 November 2003 Tech Spec Pages for Amendment No. 171, Revising the Reporting Requirements for the Discovery of Defective or Degraded Steam Generator Tubes ML0318206132003-06-20020 June 2003 License Amendment Request 198 to Kewaunee TS for One Time Extension of Containment Integrated Leak Rate Test Interval ML0233803042002-11-22022 November 2002 License Amendment Request 189 to Kewaunee TS Regarding Modification of Diesel Generator Inspection Requirements 2011-08-30
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Serial No. 11-025A ATTACHMENT 2 LICENSE AMENDMENT REQUEST 244:
PROPOSED REVISION TO RADIOLOGICAL CONSEQUENCES ANALYSIS AND CONTROL ROOM HABITABILITY TECHNICAL SPECIFICATIONS MARKED-UP OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Insert 1: Proposed Change to the Kewaunee Operating License (XX) Upon implementation of Amendment No. [ ] adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS SR 3.7.10.4, in accordance with TS 5.5.17.c.1, and the assessment of CRE habitability as required by Specification TS 5.5.17.c.2, shall be considered met. Following implementation:
(a) The first performance of TS 3.7.10.4, in accordance with Specification TS 5.5.17.c.1, shall be within the specified Frequency of 6 years, plus the 18-month allowance of TS SR 3.0.2, as measured from December 15, 2004, the date of the most recent successful tracer gas test, as stated in the April 1, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification TS 5.5.17.c.2, shall be within 3 years, plus the 9-month allowance of TS SR 3.0.2, as measured from December 15, 2004, the date of the most recent successful tracer gas test, as stated in the April 1, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
Definitions 1.1 1.1 Definitions CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.
CORE OPERATING LIMITS The COLR is the unit specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle.
These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.3.
Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present.
The determination of DOSE EQUIVALENT I-131 shall be performed using ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."
DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil."
Committed Dose Equivalent (CDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclides Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion".
Kewaunee Power Station 1.1-2 Amendment No. 207 02/02/2011
Containment Purge and Vent Isolation Instrumentation 3.3.6 recently ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Place and maintain Immediately Only applicable during containment purge and vent movement of irradiated valves in closed position.
fuel assemblies within containment. OR C.2 Enter applicable Conditions Immediately One or more Functions and Required Actions of with one or more LCO 3.9.6, "Containment automatic actuation Penetrations," for trains inoperable. containment purge and vent isolation valves made OR inoperable by isolation instrumentation.
Two or more radiation monitoring channels inoperable.
OR Required Action and associated Completion Time for Condition A not met.
Kewaunee Power Station 3.3.6-2 Amendment No. 207 02/02/2011
Containment Purge and Vent Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Purge and Vent Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS
- 1. Automatic Actuation Logic and Actuation 1,2,3,4, (a) 2 trains SR 3.3.6.2 Relays
- 2. Containment Radiation
- a. Gaseous 1,2,3,4, (a) 2 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4
- b. Particulate 1,2,3,4, (a) 1 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4
- 3. Containment Isolation - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"
Function 3.a, for all initiation functions and requirements.
- 4. Containment Spray - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"
Function 2.a, for all initiation functions and requirement.
- 5. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all functions and requirements.
(a) During movement of irradiated fuel assemblies within containment.
recently Kewaunee Power Station 3.3.6-4 Amendment No. 207 02/02/2011
CRPAR System Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Post Accident Recirculation (CRPAR) System Actuation Instrumentation LCO 3.3.7 The CRPAR System actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.3.7-1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Automatic Actuation A.1 Place associated CRPAR 7 days Logic and Actuation train in emergency mode.
Relay train inoperable.
B. Two Automatic Actuation B.1.1 Place one CRPAR train in Immediately Logic and Actuation emergency mode.
Relay trains inoperable.
AND OR B.1.2 Enter applicable Conditions Immediately Control Room Vent and Required Actions for Radiation Monitor one CRPAR train made inoperable. inoperable by inoperable CRPAR System actuation instrumentation.
OR B.2 Place both CRPAR trains in Immediately emergency mode.
Kewaunee Power Station 3.3.7-1 Amendment No. 207 02/02/2011
CRPAR System Actuation Instrumentation 3.3.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and D.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies.
Time for Condition A or B not met during recently movement of irradiated fuel assemblies. recently E. Required Action and E.1 Initiate action to restore one Immediately associated Completion CRPAR train to Time for Condition A OPERABLE status.
or B not met in MODE 5 or 6.
SURVEILLANCE REQUIREMENTS
NOTE-----------------------------------------------------------
Refer to Table 3.3.7-1 to determine which SRs apply for each CRPAR System Actuation Function.
SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.2 Perform COT in accordance with the Setpoint 92 days Control Program.
Kewaunee Power Station 3.3.7-2 Amendment No. 207 02/02/2011
CRPAR System Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.7.3 -------------------------------NOTE------------------------------
This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.
3.3.7.1 ---------------------------------------------------------------------
Perform ACTUATION LOGIC TEST. 18 months SR 3.3.7.4 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.
Kewaunee Power Station 3.3.7-3 Amendment No. 207 02/02/2011
CRPAR System Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)
CRPAR System Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS 3.3.7.1
- 1. Automatic Actuation Logic and 1, 2, 3, 4, 5, 6, 2 trains SR 3.3.7.3 Actuation Relays (a) 2 Control Room Vent Radiation 1, 2, 3, 4, 5, 6, 1 SR 3.3.7.1 Monitor (a) SR 3.3.7.2 SR 3.3.7.4
- 3. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
2.
(a) During movement of irradiated fuel assemblies.
recently Kewaunee Power Station 3.3.7-4 Amendment No. 207 02/02/2011
RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT --------------------NOTE-------------------
I-131 not within limit. LCO 3.0.4.c is applicable.
A.1 Verify DOSE EQUIVALENT Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I-131 20 µCi/gm.
AND 10 A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT I-131 to within limit.
B. DOSE EQUIVALENT --------------------NOTE-------------------
XE-133 not within limit. LCO 3.0.4.c is applicable.
B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.
Kewaunee Power Station 3.4.16-1 Amendment No. 207 02/02/2011
RCS Specific Activity 3.4.16 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met.
C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR DOSE EQUIVALENT I-131 > 20 µCi/gm.
10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 7 days specific activity 595 µCi/gm.
16.4 SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT I-131 14 days specific activity 1.0 µCi/gm.
AND 0.1 Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Kewaunee Power Station 3.4.16-2 Amendment No. 207 02/02/2011
CRPAR System 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Post Accident Recirculation (CRPAR) System envelope (CRE)
LCO 3.7.10 Two CRPAR trains shall be OPERABLE.
NOTE--------------------------------------------
The control room boundary may be opened intermittently under administrative control.
NOTE--------------------------------------------
The CRE shall be isolated during movement of recently irradiated fuel assemblies APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
and recently ACTIONS for reasons other CONDITION REQUIRED ACTION COMPLETION TIME than Condition B A. One CRPAR train A.1 Restore CRPAR train to 7 days Insert 2 inoperable. OPERABLE status.
B. Two CRPAR trains B.1 Restore control room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to OPERABLE inoperable control room status.
boundary in MODE 1, 2, 3, or 4.
C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Kewaunee Power Station 3.7.10-1 Amendment No. 207 02/02/2011
CRPAR System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE CRPAR Immediately associated Completion train in emergency mode.
Time of Condition A not met in MODE 5 or 6, or OR recently during movement of irradiated fuel D.2 Suspend movement of Immediately assemblies. irradiated fuel assemblies.
recently E. Two CRPAR trains E.1 Suspend movement of Immediately inoperable in MODE 5 or irradiated fuel assemblies.
6, or during movement of irradiated fuel recently assemblies. recently F. Two CRPAR trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
Insert 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRPAR train for 15 minutes. 31 days SR 3.7.10.2 Perform required CRPAR filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with VFTP SR 3.7.10.3 Verify each CRPAR train actuates on an actual or 18 months simulated actuation signal.
SR 3.7.10.4 Perform required CRE unfiltered air inleakage In accordance with testing in accordance with CRE Habitability CRE Habitability Program Program Kewaunee Power Station 3.7.10-2 Amendment No. 207 02/02/2011
Insert 2:
B. One or more CRPAR B.1 Initiate action to implement Immediately trains inoperable due to an mitigating actions.
inoperable CRE boundary in Modes 1, 2, 3, or 4. AND B.2 Verify mitigating actions ensure 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary to OPERABLE status. 90 days Insert 3:
OR Required Actions and associated Completion Times of Condition B not met during movement of recently irradiated fuel assemblies.
CRAC Alternate Cooling System 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning (CRAC) Alternate Cooling System LCO 3.7.11 Two CRAC Alternate Cooling trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.
recently ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAC Alternate A.1 Restore CRAC Alternate 30 days Cooling train inoperable. Cooling train to OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Required Action and C.1 Place OPERABLE CRAC Immediately associated Completion Alternate Cooling train in Time of Condition A not operation.
met during movement of recently irradiated fuel OR assemblies.
C.2 Suspend movement of Immediately recently irradiated fuel assemblies.
D. Two CRAC Alternate D.1 Suspend movement of Immediately Cooling trains inoperable irradiated fuel assemblies.
during movement of irradiated fuel recently assemblies.
recently Kewaunee Power Station 3.7.11-1 Amendment No. 207 02/02/2011
Secondary Specific Activity 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Secondary Specific Activity LCO 3.7.16 The specific activity of the secondary coolant shall be 0.10 µCi/gm DOSE EQUIVALENT I-131.
0.05 APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> within limit.
AND A.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the specific activity of the secondary coolant 31 days is 0.10 µCi/gm DOSE EQUIVALENT I-131.
0.05 Kewaunee Power Station 3.7.16-1 Amendment No. 207 02/02/2011
AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
- a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and
- b. One diesel generator (DG) capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.
recently APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite -------------------NOTE--------------------
circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.
A.1 Declare affected required Immediately feature(s) with no offsite power available inoperable.
OR recently A.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND Kewaunee Power Station 3.8.2-1 Amendment No. 207 02/02/2011
AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.2.3 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.
recently B. One required DG B.1 Suspend movement of Immediately inoperable. irradiated fuel assemblies.
AND B.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND B.3 Initiate action to restore Immediately required DG to OPERABLE status.
Kewaunee Power Station 3.8.2-2 Amendment No. 207 02/02/2011
DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE to support one subsystem of the DC Electrical Power Distribution System required by LCO 3.8.10, "Distribution System - Shutdown."
recently APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC A.1 Suspend movement of Immediately electrical power irradiated fuel assemblies.
subsystem inoperable.
AND recently A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.3 Initiate action to restore Immediately required DC electrical power subsystem to OPERABLE status.
Kewaunee Power Station 3.8.5-1 Amendment No. 207 02/02/2011
Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 One inverter shall be OPERABLE to support the 120 VAC electrical distribution subsystem required by LCO 3.8.10, "Distribution Systems -
Shutdown."
recently APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 Suspend movement of Immediately inoperable. irradiated fuel assemblies.
AND recently A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND A.3 Initiate action to restore Immediately required inverter to OPERABLE status.
Kewaunee Power Station 3.8.8-1 Amendment No. 207 02/02/2011
Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
recently APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.
ACTIONS
NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC supported required instrument bus electrical feature(s) inoperable.
power distribution recently subsystems inoperable. OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.
AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.
AND Kewaunee Power Station 3.8.10-1 Amendment No. 207 02/02/2011
Containment Penetrations 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Containment Penetrations capable of being ;
LCO 3.9.6 The containment penetrations shall be in the following status:
- a. The equipment hatch is closed and held in place by four bolts;
- b. One door in each air lock is capable of being closed; and
- c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere is either:
- 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent; or
- 2. Capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.
APPLICABILITY: During movement of irradiated fuel assemblies within containment.
recently recently ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Suspend movement of Immediately containment irradiated fuel assemblies penetrations not in within containment.
required status.
NOTE------------------------------------------------------
Penetration flow paths providing direct access from the containment to outside atmosphere may be opened under administrative controls.
Kewaunee Power Station 3.9.6-1 Amendment No. 207 02/02/2011
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Setpoint Control Program (continued) 10 CFR 50.90 is required to change the listed value of the NTSP, AV, AFT, and ALT (as applicable) for each Function described in Paragraph a.
- c. The program shall establish methods to ensure that Functions described in Paragraph a. will function as required by verifying the as-left and as-found settings are consistent with the list of values established by Paragraph b. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.
- d. The program shall identify the Functions described in Paragraph a. that are automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A). The NTSP of these Functions are Limiting Safety System Settings. These Functions shall be demonstrated to be functioning as required by applying the following requirements during CHANNEL CALIBRATIONS, CHANNEL OPERATIONAL TESTS, and TRIP ACTUATING DEVICE OPERATIONAL TESTS that verify the NTSP.
- 1. The as-found value of the instrument channel trip setting shall be compared with the previous as-left value or the specified NTSP.
- 2. If the as-found value of the instrument channel trip setting differs from the previous as-left value or the specified NTSP by more than the pre-defined test acceptance criteria band (i.e., the specified AFT), then the instrument channel shall be evaluated before declaring the SR met and returning the instrument channel to service. This condition shall be entered in the plant corrective action program.
- 3. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.
- 4. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the NTSP at the completion of the surveillance test; otherwise, the channel is inoperable (setpoints may be more conservative than the NTSP provided that the as-found and as-left tolerances apply to the actual setpoint used to confirm channel performance).
- e. The program shall be specified in the Technical Requirements Manual.
5.5.17 (see Insert 4)
Kewaunee Power Station 5.5-15 Amendment No. 207 02/02/2011
Insert 4:
5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Post-Accident Recirculation (CRPAR) System and CRE boundary, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a. The definition of the CRE and the CRE boundary.
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for:
- 1. Determining the unfiltered air in-leakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and;
- 2. Assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Licensee controlled programs will be used to verify the integrity of the CRE boundary. Conditions that generate relevant information from those programs will be entered into the corrective action process and shall be trended and used as part of the 36-month assessment of the CRE boundary in accordance with TS 5.5.17.c.2.
- e. The quantitative limits on unfiltered air in-leakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and assessing the CRE boundary as required by TS 5.5.17.c. and TS 5.5.17.d., respectively.