ML062770090: Difference between revisions

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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
Line 9: Line 9:
| 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}}

Latest revision as of 13:32, 23 November 2019

Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval
ML062770090
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/03/2006
From:
NRC/NRR/ADRO/DORL/LPLIV
To:
Benney B, NRR/DORL, 415-3764
Shared Package
ML062540020 List:
References
TAC MC9732
Download: ML062770090 (2)


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