ML060110479: Difference between revisions

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| number = ML060110479
| number = ML060110479
| issue date = 12/16/2005
| issue date = 12/16/2005
| title = Cooper Nuclear Station, Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation
| title = Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation
| author name =  
| author name =  
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
Line 9: Line 9:
| docket = 05000298
| docket = 05000298
| license number = DPR-046
| license number = DPR-046
| contact person = Benney B J, NRR/DLPM, 415-3764
| contact person = Benney B, NRR/DLPM, 415-3764
| case reference number = TAC MC5031
| case reference number = TAC MC5031
| package number = ML060110601
| package number = ML060110601

Revision as of 00:48, 14 July 2019

Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation
ML060110479
Person / Time
Site: Cooper Entergy icon.png
Issue date: 12/16/2005
From:
Office of Nuclear Reactor Regulation
To:
Benney B, NRR/DLPM, 415-3764
Shared Package
ML060110601 List:
References
TAC MC5031
Download: ML060110479 (2)


Text

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)Secondary Containment Isolation Instrumentation APPUCABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1.2.3. 2 SR 3.3.6.2.1

>-42 Inches Level -Low Low (Level 2) (a) SR 3.3.62.2 SR 3.3.62.3 SR 3.3.62.4 2. Drywell Pressure -High 1.2.3 2 SR 3.3.6.2.2 1.84 psIg SR 3.3.623 SR 3.3.62.4 3. Reactor Building Ventilation 1.2.3. 2 SR 3.3.6.2.1 49 mRihr Exhaust Plenum (a),(b) SR 3.3.6.2.2 Radiation

-High SR 3.3.62.3 SR 3.3.6.2.4 I I I (a) During operations with a potential for draining the reactor vessel.(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary contatnmenL Amendment 212 3.3-57 CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)Control Room Emergency Filter System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1.2.3, 2 SR 3.3.7.1.1

>-42 Inches Level -Low Low (Level 2) (a) SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 2. Drywell Pressure -High 1,2.3 2 SR 3.3.7.12 <1.84 psig SR 3.3.7.1.3 SR 3.3.7.1.4 3. ReactorBuIldingVentilation 1.2,3. 2 SR 3.3.7.1.1 549 mR/hr Exhaust Plenum (a).(b) SR 3.3.7.1.2 Radiation

-High SR 3.3.7.1.3 SR 3.3.7.1A (a) During operaUons wth a potenal for drainng the reactor vessel.(b) During CORE ALTERATIONS and durlng movement of hradiated fuel assembfles In the secondary containment I I I Amendment 212 3.3-63