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| | number = ML062770090 | | | number = ML062770090 |
| | issue date = 10/03/2006 | | | issue date = 10/03/2006 |
| | title = Cooper Nuclear Station, Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval (TAC No. MC9732) | | | title = Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
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| | docket = 05000298 | | | docket = 05000298 |
| | license number = DPR-046 | | | license number = DPR-046 |
| | contact person = Benney B J, NRR/DORL, 415-3764 | | | contact person = Benney B, NRR/DORL, 415-3764 |
| | case reference number = TAC MC9732 | | | case reference number = TAC MC9732 |
| | package number = ML062540020 | | | package number = ML062540020 |
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| =Text= | | =Text= |
| {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Pro-gram (SFDP) (continued) | | {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Pro-gram (SFDP) (continued) |
| For the purpose of this program, a loss of safety function may exist When a support system is inoperable, and: 1. A required system redundant to system(s) supported by the inoperable support system is also- inoperable; or 2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or 3. A required system redundant to support system(s) for the supported systems b. 1 and b.2 above is also inoperable. | | For the purpose of this program, a loss of safety function may exist When a support system is inoperable, and: |
| The SFDP identifies where a loss of safety function exists.. If a loss of safety function is determined to exist by this program, the appropriate. | | : 1. A required system redundant to system(s) supported by the inoperable support system is also- inoperable; or |
| Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.5.5.12 Primary Containment Leakage Rate Testing Program a. A program shall establish the leakage rate testing.of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by.approved exemptions. | | : 2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exceptions: | | : 3. A required system redundant to support system(s) for the supported systems b. 1 and b.2 above is also inoperable. |
| : 1. Exemption from Appendix'J to 10CFR Part 50 to allow reverse direction local leak rate testing of four containment isolation valves at Cooper Nuclear Station (TAC NO. M89765) (July 22, 1994).2. Exemptidn frQm Appendix .J to 1 OCFR Part 50 to allow MSIV testing at 29 psig and expansion bellows testing at 5 psig between the piles (Sept. 16, 1977).3. Exception to NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Section 9.2.3: The first Type A test performed after the December 7,1998 Type A test shall be performed no later than December 7, 2013. .b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 58.0 psig. The containment design pressure is 56.0 psig.(continued) | | The SFDP identifies where a loss of safety function exists.. If a loss of safety function is determined to exist by this program, the appropriate. Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. |
| Cooper 5.0-16 Amendment No. 224 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued) | | 5.5.12 Primary Containment Leakage Rate Testing Program |
| C. The maximum allowable containment leakage rate, L., at P., shall be 0.635% of containment air weight per day.d. Leakage Rate acceptance criteria are: 1. Containment leakage rate acceptance criterion is 5 1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are, <0.60 L. for the Type B and C tests and 0.75 L, for Type A tests.2. Air lock testing acceptance criteria are: a. Overall air lock leakage rate is -12 scfh when tested at 2 P 8.b. Overall air lock leakage rate is g 0.23 scfh when tested at 3.0 psig.e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage'Rate Testing Program.* f. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.Cooper 5.0-17 Amendment No. 224}} | | : a. A program shall establish the leakage rate testing.of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by. |
| | approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exceptions: |
| | : 1. Exemption from Appendix'J to 10CFR Part 50 to allow reverse direction local leak rate testing of four containment isolation valves at Cooper Nuclear Station (TAC NO. M89765) (July 22, 1994). |
| | : 2. Exemptidn frQm Appendix .J to 10CFR Part 50 to allow MSIV testing at 29 psig and expansion bellows testing at 5 psig between the piles (Sept. 16, 1977). |
| | : 3. Exception to NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Section 9.2.3: The first Type A test performed after the December 7,1998 Type A test shall be performed no later than December 7, 2013. . |
| | : b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 58.0 psig. The containment design pressure is 56.0 psig. |
| | (continued) |
| | Cooper 5.0-16 Amendment No. 224 |
| | |
| | Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued) |
| | C. The maximum allowable containment leakage rate, L., at P., shall be 0.635% of containment air weight per day. |
| | : d. Leakage Rate acceptance criteria are: |
| | : 1. Containment leakage rate acceptance criterion is 5 1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are, <0.60 L. for the Type B and C tests and 0.75 L, for Type A tests. |
| | : 2. Air lock testing acceptance criteria are: |
| | : a. Overall air lock leakage rate is - 12 scfh when tested at 2 P8. |
| | : b. Overall air lock leakage rate is g 0.23 scfh when tested at 3.0 psig. |
| | : e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage'Rate Testing Program. |
| | *f. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. |
| | Cooper 5.0-17 Amendment No. 224}} |
|
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Category:Technical Specifications
MONTHYEARNLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) NLS2024027, Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021 Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program ML20314A2352020-12-0202 December 2020 Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process ML19238A0072019-10-30030 October 2019 Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML16021A3222016-01-12012 January 2016 Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML15216A2592015-08-27027 August 2015 Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water ML15168A1712015-07-14014 July 2015 Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications ML15135A0052015-05-29029 May 2015 Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS) NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML14055A0232014-04-29029 April 2014 Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML13191A1052013-09-12012 September 2013 Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report ML13085A0962013-03-29029 March 2013 Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML1136302582012-01-31031 January 2012 Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011 Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0906207232009-02-26026 February 2009 Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment ML0815402852008-06-30030 June 2008 Technical Specifications, Measurement Uncertainty Recapture Power Uprate ML0812202892008-05-12012 May 2008 Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448 NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008 Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007 Corrected Technical Specification Pages NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007 License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML0630405382006-10-31031 October 2006 Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J ML0629602942006-10-23023 October 2006 Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities ML0627700902006-10-0303 October 2006 Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0625003012006-09-0606 September 2006 Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335 ML0624900372006-09-0505 September 2006 Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566 NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation ML0612403772006-05-0303 May 2006 Correction to Amendment No. 218, Technical Specification Page 3.1-12 ML0612304692006-05-0202 May 2006 Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves ML0611802442006-04-27027 April 2006 Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation ML0611001622006-04-18018 April 2006 Corrected Technical Specification Page 3.9-1 Re Refueling Operations NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006 Corrected Technical Specification Page from Amendment No. 218 ML0609004412006-03-30030 March 2006 Technical Specification Pages, Change Request for Various Sections ML0628404572006-03-10010 March 2006 Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006 License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006 Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006 License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval ML0602002922006-01-16016 January 2006 Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences 2024-05-09
[Table view] |
Text
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Pro-gram (SFDP) (continued)
For the purpose of this program, a loss of safety function may exist When a support system is inoperable, and:
- 1. A required system redundant to system(s) supported by the inoperable support system is also- inoperable; or
- 2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or
- 3. A required system redundant to support system(s) for the supported systems b. 1 and b.2 above is also inoperable.
The SFDP identifies where a loss of safety function exists.. If a loss of safety function is determined to exist by this program, the appropriate. Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
5.5.12 Primary Containment Leakage Rate Testing Program
- a. A program shall establish the leakage rate testing.of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by.
approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exceptions:
- 1. Exemption from Appendix'J to 10CFR Part 50 to allow reverse direction local leak rate testing of four containment isolation valves at Cooper Nuclear Station (TAC NO. M89765) (July 22, 1994).
- 2. Exemptidn frQm Appendix .J to 10CFR Part 50 to allow MSIV testing at 29 psig and expansion bellows testing at 5 psig between the piles (Sept. 16, 1977).
- 3. Exception to NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Section 9.2.3: The first Type A test performed after the December 7,1998 Type A test shall be performed no later than December 7, 2013. .
- b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 58.0 psig. The containment design pressure is 56.0 psig.
(continued)
Cooper 5.0-16 Amendment No. 224
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
C. The maximum allowable containment leakage rate, L., at P., shall be 0.635% of containment air weight per day.
- d. Leakage Rate acceptance criteria are:
- 1. Containment leakage rate acceptance criterion is 5 1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are, <0.60 L. for the Type B and C tests and 0.75 L, for Type A tests.
- 2. Air lock testing acceptance criteria are:
- a. Overall air lock leakage rate is - 12 scfh when tested at 2 P8.
- b. Overall air lock leakage rate is g 0.23 scfh when tested at 3.0 psig.
- e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage'Rate Testing Program.
Cooper 5.0-17 Amendment No. 224