ML17296A443

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Amends 790626 Response to IE Bulletin 79-09.Reactor Trip Switchgear Includes Two GE AKR-30 Circuit Breakers W/Same Failure Problem as Type AK-2.Action Recommended for Type AK-2 Will Be Used for Type AKR-30
ML17296A443
Person / Time
Site: Browns Ferry, Palo Verde  Tennessee Valley Authority icon.png
Issue date: 08/30/1979
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-13762-JMA, NUDOCS 7910020597
Download: ML17296A443 (4)


Text

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AB)ZONANUCLEAR POPPER PROJECT Post Office Box 21666 Phi

'x, Arizona 85036 Docket Nos. 50-528, 50-529, 50-530 August 30, 1979 ANPP-13762 - JMA/TFg Mr. R.

H. Engelken, Director U.S. Nuclear Regulatory Commission Region V

202 Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94596

Subject:

-NRC IE Bulletin No. 79-09 dated April 17, 1979 File:

D.4.06.1; 79-005-026 6

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V

Reference:

(A)

ANPP-13372 - JMA/TFg dated June 26, 1979

Dear Mr. Engelken:

This letter amends our response, Reference (A), to your IE Bulletin No. 79-09, which discussed failures of GE type AK-2 circuit breakers in safety related systems.

As stated in Reference (A), the GE type AK-2 circuit breaker is not used in the Palo Verde Nuclear Generating Station.

Further investi-gation has revealed, however, that the PVNGS reactor trip switchgear includes two GE type AKR-30 circuit breakers.

General Electric has verified that the type AKR-30 circuit breaker hag the same under voltage trip device failure problem as the type AK-2.

Even though Bulletin No. 79-09 doesn't state applicability to the entire family of GE type AK breakers, proper action recommended by Bulletin No. 79-09 will be implemented for the GE type AKR-30 circuit breakers.

As recommended, a preventive maintenance program will be developed, to assure design performance of the GE type AKR-30 circuit breakers.

This program kill include a preventive maintenance schedule which will'

Mr. R.

H. Engelken, Director August 30, 1979 ANPP-13762 - JMA/TFQ Page 2

1 h

implement the recommended corrective actions described in the GE Service Alert letter attached to Bulletin No. 79-09.

The main-tenance will be performed by qualified personnel.

This program will be developed and implemented prior to initial fuel load for each unit.

If you have any questions, please advise.

Very 'truly your,

(

C GC U n~(

E.

E.

Van Brunt, Jr.

APS Vice President, Nuclear Projects ANPP Project Director EEVBJr/TFQ/av Attachment cc:

R. L.

Robb J.

M. Allen D.

B. Karner J.

A. Roedel F.

W. Hartley W. H. Wilson C.

E.

Ferguson A. C.

Rogers L.

W. Price NRC Office of Inspection and Enforcement Division of Reactor Inspection Programs Washington, D.C.

20555