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| | number = ML063190535 | | | number = ML063190535 |
| | issue date = 11/15/2006 | | | issue date = 11/15/2006 |
| | title = Wolf Creek - Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program | | | title = Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
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| {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 5.5.8 Reactor Coolant Pump Flywheel Inspection Program (continued) radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year Intervals. | | {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program (continued) radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year Intervals. |
| Inservice Testing Pro-ram This program proVides controls for Inservice testing of ASME Code Class 1, 2, and 3 components. | | 5.5.8 Inservice Testing Pro-ram This program proVides controls for Inservice testing of ASME Code Class 1, 2, and 3 components. The program shall Include the following: |
| The program shall Include the following: | | : a. Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows: |
| : a. Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows: I ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months every 6 months*every 6 months Every 9 months Yearly or annually Biennially or every 2 years At least once per 7 days At least once per 31 days At least once per 921days At least once per 276 days At least once per 766 days At least once per 376 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to theabove required Frequencies and other normal and accelerated Frequencies specified as 2 years or less In the Inservice Testing Program for performing inservice testing activities; | | I ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 921days every 6 months* |
| : c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and d., Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.I I-(continued) | | every 6 months At least once per 276 days Every 9 months At least once per 766 days Yearly or annually At least once per 376 days Biennially or every At least once per 731 days 2 years |
| Wolf Creek -Unit I 5.0-10 Amendment No. 42,153, 172 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) | | : b. The provisions of SR 3.0.2 are applicable to theabove required Frequencies and other normal and accelerated Frequencies specified as 2 years or less In the Inservice Testing Program for performing inservice testing activities; I |
| : i. Limitations on the annual and quarterly doses to a member of the public from iodine-1 31., iodine-1 33, tritium, and all radionuclides In particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle .sources, conforming to 40 CFR 190.k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
| | : c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and d., Nothing in the ASME OM Code shall be construed to supersede the I requirements of any TS. |
| | -(continued) |
| | Wolf Creek - Unit I 5.0-10 Amendment No. 42,153, 172 |
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| ====5.5.5 Component====
| | Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) |
| | | : i. Limitations on the annual and quarterly doses to a member of the public from iodine-1 31., iodine-1 33, tritium, and all radionuclides In particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; |
| Cyclic or Transient Limit This program provides controls to track the USAR, Section 3.9(N), cyclic and transient occurrences to ensure that components are maintained within the design limits.5.5.6 Containment Tendon Surveillance Program This program provides controls for monitoring tendon performance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural Integrity. | | : j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle .sources, conforming to 40 CFR 190. |
| The program shall Include baseline measurements prior to Initial plant operation as well as periodic testing thereafter. | | : k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency. |
| The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance critetia, shall be In accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.The provisions of SR 3.0.3 are applicaible to the Tendon Surveillance Program Inspection frequencies. | | 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 3.9(N), cyclic and transient occurrences to ensure that components are maintained within the design limits. |
| | | 5.5.6 Containment Tendon Surveillance Program This program provides controls for monitoring tendon performance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural Integrity. The program shall Include baseline measurements prior to Initial plant operation as well as periodic testing thereafter. The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance critetia, shall be In accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC. |
| ====5.5.7 Reactor====
| | The provisions of SR 3.0.3 are applicaible to the Tendon Surveillance Program Inspection frequencies. |
| Coolant Pump Flywheel Inspection Program This program shall provide for the inspebdton of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the Inner bore of the flywheel to the circle one-half of the outer (continued) | | 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspebdton of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. |
| Wolf Creek -Unit I 5.0-9 Amendment No. 423, 153}} | | In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the Inner bore of the flywheel to the circle one-half of the outer (continued) |
| | Wolf Creek - Unit I 5.0-9 Amendment No. 423, 4*52, 153}} |
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TAC:MC9726, Changes to Reflect Revision of 10 CFR 50.55A (Approved, Closed) |
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Category:Technical Specification
MONTHYEARML24227A5562024-08-14014 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. ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23068A1232023-03-0909 March 2023 Changes to Technical Specification Bases – Revisions 91 and 92 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22067A0302022-03-0808 March 2022 Changes to Technical Specification Bases - Revisions 86, 87, 88, 89, and 90 ML21070A0582021-03-11011 March 2021 Changes to Technical Specification Bases - Revisions 82, 83, 84, and 85 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20070L9822020-03-0202 March 2020 Changes to Technical Specification Bases - Revisions 80 and 81 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ML19078A1302019-03-11011 March 2019 Changes to Technical Specification Bases - Revisions 78 and 79 WO 19-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-03-11011 March 2019 Supplement to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18075A0242018-03-0808 March 2018 Changes to Technical Specification Bases - Revisions 76 and 77 WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ML17073A0932017-03-0909 March 2017 Changes to Technical Specification Bases - Revisions 74 and 75 ML17054C2212017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes ML17054C2202017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes ML16076A3572016-03-10010 March 2016 Changes to Technical Specification Bases - Revisions 67 Through 73 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 ML15077A0662015-03-11011 March 2015 Changes to Technical Specification Bases, Revisions 61 Through 66 WO 14-0092, Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2014-12-15015 December 2014 Submittal of Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ET 13-0028, Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report.2013-09-23023 September 2013 Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report. 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 ML13079A0602013-03-0808 March 2013 Changes to Technical Specification Bases - Revisions 55 and 56 ML12080A2162012-03-12012 March 2012 Changes to Technical Specification Bases - Revisions 50 Through 54 WO 11-0086, Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating2011-11-30030 November 2011 Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 ML1007801282010-03-11011 March 2010 Changes to Technical Specification Bases - Revisions 41 Through 44 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 ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report WO 09-0022, Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases2009-09-0303 September 2009 Request for Approval of Changes to the Technical Specification 3.8.1, AC Sources - Operating, Bases ML0907506242009-03-11011 March 2009 Submittal of Changes to Technical Specification Bases - Revisions 36 Through 40 WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A2008-08-18018 August 2008 Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A 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. ML0811201492008-04-29029 April 2008 Corrected Technical Specification Pages, Amendment No. 177 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves, to Add Main Feedwater Regulating Valves and MFRV Bypass Valves ML0807805602008-03-0707 March 2008 Changes to Technical Specification Bases - Revisions 32 Through 35 ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707402282007-03-0909 March 2007 Changes to Technical Specification Bases - Revisions 24 Through 31 ML0631905352006-11-15015 November 2006 Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program 2024-08-14
[Table view] Category:Amendment
MONTHYEARML24213A3352024-07-31031 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. ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ...2018-01-15015 January 2018 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of ... ML16076A3572016-03-10010 March 2016 Changes to Technical Specification Bases - Revisions 67 Through 73 WO 11-0086, Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating2011-11-30030 November 2011 Application to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A2008-08-18018 August 2008 Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A ML0811201492008-04-29029 April 2008 Corrected Technical Specification Pages, Amendment No. 177 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves, to Add Main Feedwater Regulating Valves and MFRV Bypass Valves ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2008-01-15015 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0631905352006-11-15015 November 2006 Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program ML0627804522006-10-0505 October 2006 Technical Specification Pages - Issuance of Amendment Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0624201502006-08-29029 August 2006 Techncial Specification, Addition of Surveillance Requirement 3.3.1.16 to TS Table 3.3.1.16 WO 06-0023, Revision to Technical Specification 3.5.2, ECCS - Operating.2006-06-0202 June 2006 Revision to Technical Specification 3.5.2, ECCS - Operating. ET 05-0001, Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program2005-04-18018 April 2005 Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program ML0507702972005-03-16016 March 2005 Tech Spec Page for Amendment 160 Revised Seal Injection Flow Rates ML0503301602005-01-31031 January 2005 Technical Specifications, Amendment 156 Plant Protection Test Times, Completion Times and Surveillance Test Intervals ML0503502612005-01-31031 January 2005 Tech Spec Pages for Amendment 158, Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports. WO 04-0050, Revision to Technical Specification (TS) 3.8.1, AC Sources-Operating, Diesel Generator Start Time Surveillance Requirements2004-12-13013 December 2004 Revision to Technical Specification (TS) 3.8.1, AC Sources-Operating, Diesel Generator Start Time Surveillance Requirements WO 04-0031, Revision to Technical Specification (TS) 5.3, Unit Staff Qualifications, and Corrections to Various TSs2004-10-0707 October 2004 Revision to Technical Specification (TS) 5.3, Unit Staff Qualifications, and Corrections to Various TSs WO 04-0027, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process2004-07-23023 July 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process WO 04-0035, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process2004-07-23023 July 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process WO 03-0057, Revision to Technical Specifications Regarding Extensions of AC Electrical Power Distribution Completion Time2003-10-30030 October 2003 Revision to Technical Specifications Regarding Extensions of AC Electrical Power Distribution Completion Time ML0221200382002-07-29029 July 2002 Technical Specifications for Amendment 123, Limited Removal of Suspension of Positive Reactivity Additions 2024-07-31
[Table view] |
Text
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program (continued) radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year Intervals.
5.5.8 Inservice Testing Pro-ram This program proVides controls for Inservice testing of ASME Code Class 1, 2, and 3 components. The program shall Include the following:
- a. Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:
I ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 921days every 6 months*
every 6 months At least once per 276 days Every 9 months At least once per 766 days Yearly or annually At least once per 376 days Biennially or every At least once per 731 days 2 years
- b. The provisions of SR 3.0.2 are applicable to theabove required Frequencies and other normal and accelerated Frequencies specified as 2 years or less In the Inservice Testing Program for performing inservice testing activities; I
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and d., Nothing in the ASME OM Code shall be construed to supersede the I requirements of any TS.
-(continued)
Wolf Creek - Unit I 5.0-10 Amendment No. 42,153, 172
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
- i. Limitations on the annual and quarterly doses to a member of the public from iodine-1 31., iodine-1 33, tritium, and all radionuclides In particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;
- j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle .sources, conforming to 40 CFR 190.
- k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 3.9(N), cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6 Containment Tendon Surveillance Program This program provides controls for monitoring tendon performance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural Integrity. The program shall Include baseline measurements prior to Initial plant operation as well as periodic testing thereafter. The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance critetia, shall be In accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.
The provisions of SR 3.0.3 are applicaible to the Tendon Surveillance Program Inspection frequencies.
5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspebdton of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the Inner bore of the flywheel to the circle one-half of the outer (continued)
Wolf Creek - Unit I 5.0-9 Amendment No. 423, 4*52, 153