ML20198R704

Amend 174 to License DPR-35,adding Footnote to TS 3.7.A.5, Primary Containment. Footnote Provides one-time Exception to Reverse Flow Testing Requirement for Containment Isolation Check Valve 30-CK-432

ML20198R704
Person / Time
Site:	Pilgrim
Issue date:	10/30/1997
From:	Eaton R NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198R708	List: ML20198R704 ML20198R790
References
NUDOCS 9711130366
Download: ML20198R704 (4)

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UNITED STATES f}

NUCLEAR REGULATORY COMMIS810N

'f WASHINGTON, D.C. seteH001

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BOSTON EDIS0N COMPANY DOCKET NO._50 293 PILGRIM NUCLEAR POWER STATION 1

i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. DPR-35 1.

The Nuclear Regulatory Comission (the Comission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) dated October 24, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations:

B.

The facility will operate in conformity with the application, the arovisions of the Act, and the rules and regulations of the Comission:

C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations:

D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and sefety of the public: and E,

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment.

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3.

This license amendment is effective as of its date of issuance and i

shall be implemented by November 2,1997.

FOR THE NUCLEAR REGULATORY COMMISSION i

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Foe Ronald B. Eaton, Actin ctor ProjectDirectorateI-DivisionofReactorProjects-I/11 Office of Nuclear Reactor Regulation t

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Attachment:

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Changes to the Technical i

Specifications i

Date of Issuance: October 30, 1997 l

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ATTACAMENT TO LICENSE AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50 293 Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

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3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

A.

Primary Containtnent (Cont)

A.

Primary Containment (Cont) j

5. All containment isolation check

4. Combined main steamlines: 46 valves are operable or at least scfh @ 23 psig, one containment isolation valve in each line having an where P.

45 psig inoperable valve is secured in L

1.0% by weight of the contained the isolated position.**

air e 45 psig for 24 hrs.

Primary Containment inpfation Valves Primary Containment Isolation Valves

2. b.1. The primary containment 2.

b.

In the event any automatic isolation valves surveillance shall Primary Containment Isolation be performed as follows:

Valve becomes inoperable, at least one containment isolation

a. At least once per operating valve in each line having an cycle the operable primary inoperable valve shall be containment isolation valves deactivated in the isolated that are power operated and condition. (This requirement may automatically initiated shall be satisfied by deactivating the be tested for simulated inoperable valve in the isolated automatic initiation and condition. Deactivation means to closure times.

electrically or pneumatically

b. Test primary containment disarm, or otherwise secure the Isolation valves:

valve.)*

1. Verify power operated primary containment isolation valve operability as specified in 3.13

2. Verify main steam

• Isolation valves closed to satisfy these requirements isolation valve operability may be reopened on an intermittent basis under ORC as specified in 3.13.

approved administrative controls.

" Check valve 30 CK 432 will be considered operable until reverse flow testing is performed no later than the 1998 maintenance outage.

Amendment No. 413,13S, die,1S0.167, i74 3/4.7-5

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