ML20081J032

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Amend 160 to License DPR-35 Re Changes to TS to Revise Allowable Leak Rate MSIVs
ML20081J032
Person / Time
Site: Pilgrim
Issue date: 03/22/1995
From: Marsh L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20081J035 List:
References
NUDOCS 9503270073
Download: ML20081J032 (4)


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UNITED STATES s

y NUCLEAR REGULATORY COMMISSION l

e-WASHINGTON, D.C. 20666 4 001 g

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BOSTON EDISON COMPANY j

DOCKET NO. 50-293 l

PILGRIM NUCLEAR POWER STATION l

AMENDMENT TO FACILITY OPERATING LICENSE

't Amendment No.-160 l

License No. DPR ;

1.

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

'i A.

The application for amendment filed by the Boston Edison Company (the j

licensee) dated November 22, 1994, complies with the standards and-requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations; i

B.

The facility will. operate in conformity with the application, the

l provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that.'the activities authorized by j

this amendment-can be conducted without endangering the health and

.j safety of the public, and (ii) that such activities will be conducted' i

in compliance with the Commission's regulations; j

D.

The issuance of this amendment will not be. inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this. amendment is in accordance with 10 CFR Part 51 I

of the Commission's regulations and all applicable requirements have l

been satisfied.

2.

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

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i 9503270073 950322

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PDR ADOCK 05000293 P

PDR

. 3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY C00911SSION L

. I.k h

p ledyard D. Marsh, Director (L

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 22, 1995 p

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ATTACHMENT TO LICENSE AMENDMENT NO. 160 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3/4.7-5 3/4.7-5 1

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LIMITINC CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont).

~l 4.7 CONTAINMENT SYSTEMS (Cont)

I A.

Primary Containment (Cont)

A.

Primary Containment (Cont)

5. All containment isolation
4. Combined main steam i

check valves are operable lines: 46 scfh @ 23 or at least one psig.

containment isolation i

valve in each line having where x 45 psis-an' inoperable valve is Le

.75.L.

secured in the isolated-L.

1.04 by weight of

position, the contained air

@ 45 psig for:

24 hrs.

Primary Containment Isolation Valves I

2. b. In the event any automatic Pri==rv Containment Isolation Valves Primary Containment
2. b. 1 The primary containment Isolation Valve becomes isolation valves inoperable, at least one surveillance shall be containment ~ isolation valve performed as follows:

in each line having an inoperable valve shall be

a. At least once per deactivated in the isolated operating cycle ttm l

condition.

(This operable primary i

requirement may be satisfied containment isolation i

by deactivating the valves that are power t

inoperable valve in the operated and isolated condition.

automatically initiated Deactivation means to shall be tested for electrically or simulated automatic pneumatically disarm, or initiation and closure otherwise secure the times.

valve.)*

b. Test primary containment i

isolation valves:

1. Verify power operated

]

primary containment i

isolation valve operability as specified in 3.13.

Isolation valves closed to satisfy

2. Verify main steam these requirements may be reopened isolation valve on an intermittent basis under ORC operability as approved administrative controls.

specified in 3.13.

113 -136,-149.160 Amendment No.

t 3/4.7-5

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