ML081510650

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Technical Specifications, Issuance of Amendment Regarding One-Time 5-Year Extension to Type a Test Interval
ML081510650
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/30/2008
From:
NRC/NRR/ADRO/DORL/LPLII-1
To:
Lingam, Siva NRR/DORL 415-1564
Shared Package
ML081510532 List:
References
TAC MD7478
Download: ML081510650 (17)


Text

(3) Pursuant to.the Act and 10 CFR Parts 30.40. and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor stalup, sealed sources for reactor Instrumentaflon and radiatlion montoring equpment calibration, and as fission detectors inamounts as required; (4) Pursuant to the Act end 10 CFR Parts 30, 40, end 70, VEPCO to receive, possess, end use In amounts as required any byproduct, source, or special nudear material, without restriction to chemical or physical form, for sample analysis or instwment calibration or associated with, radioactive appantus or components; and (5) Pursuant to the Act end 10CFR Parts 30, 40, and 70, VEPGO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the faclily.

C. This renewed license shall be deemed to contain and Is subject to the condirloms specifled In the Comminslon's regulations as set forth In 10 GCR Chapter I end is subject to all applicable provisions of the Act and to the rules, regultagons, and orders of the oomlssfon now or hereafter Ineffect; and Is subject to nos additional condiltons specified or Incorporated below:

(1) Maximum Power Level VEPCO Is authorized to operate the facility at steady stale reactor ce power leves not In excess of 2893 megawatts (thermal).

(2) Teihnical SpecJI;callons The Technical Specdlications contained In Appendix A,as revised through Amendment No. 233 are hereby hkoorporated In the renewed license.

The 11censee shan operate the faclIty Inaccordance with the Techrical Speclficatifons.

(3) Additional Conditione The matters specified Inthe foltowing condiUons shal be completed to the etlusfaclion of the Commission within the stated time periods following the Issuance of lhe condi'lon or wlthin the opemulonal restrictions Indicated. The removal of thesd conditions shall be made by en amendment to the renewed license supported by e favorable evaluation by the Commission:

a. IfVEPCO plans to remove or 1o make slgnIlIcant changes In the normal operation of equipment that contros the amouni of radloactlvy In effluents from the North Anna Power Btation, the Renewed Ucense No NPF-7 Amendment No. 233

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (SFDP) (continued) analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or
b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or
c. A required system redundant to the support system(s) for the supported systems (a) and (b) 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. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.15 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 exception:

NEI 94-01-1995, Section 9.2.3: The first Unit 2 Type A test performed after the October 9, 1999 Type A test shall be performed no later than October 9, 2014.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 42.7 psig. The containment design pressure is 45 psig.
c. The maximum allowable containment leakage rate, La, at Pat shall be 0.1% of containment air weight per day.

(continued)

North Anna Units 1 and 2 5.5-14 Amendment No. 233