ML062710014

Tech Spec Pages for Amendment 261 Limits on Main Steam Isolation Valve Leakage

ML062710014
Person / Time
Site:	Browns Ferry
Issue date:	09/27/2006
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Shared Package
ML062210461	List: ML062210458 ML062710014
References
TAC MC3813
Download: ML062710014 (2)

Text

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and"10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter i:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2) Technical Specifications The Technical .Specifications contained in Appendices A and B, as revised through Amendment No. 261 , are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance'Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.

Renewed License No. DPR-33 Amendment No. 261

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SIR 3.6.1.3.5 Verify the isolation time of each power In accordance operated, automatic PCIV, except for MSIVs, with the Inservice is within limits. Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is > 3 In accordance seconds and < 5 seconds. with the Inservice Testing Program SIR 3.6.1.3.7 Verify each automatic PCIV actuates to the 18 months isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV 18 months actuates to the isolation position on a simulated instrument line break signal.

SIR 3.6.1.3.9 Remove and test the explosive squib from 18 months on a each shear isolation valve of the TIP System. STAGGERED TEST BASIS SIR 3.6.1.3.10 Verify leakage rate through each MSIV is In accordance

_<100 scfh and that the combined leakage with the Primary rate for all four main steam lines is < 150 scfh Containment when tested at > 25 psig. Leakage Rate Testing Program SR 3.6.1.3.11 Verify combined leakage through water tested In accordance lines that penetrate primary containment are with the Primary within the limits specified in the Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program BF14-UNIT 1 3.6-16 Amendment No.-234. 261