ML16341G444

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Forwards Insp Repts 50-275/91-40 & 50-323/91-40 on 911119- 1231.Weaknesses in Preparation & Implementation of Operability Evaluation Involving post-accident Monitoring Instrumentation,Noted
ML16341G444
Person / Time
Site: Diablo Canyon  
Issue date: 01/31/1992
From: Richards S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Rueger G
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML16341G445 List:
References
NUDOCS 9202180131
Download: ML16341G444 (6)


See also: IR 05000275/1991040

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UNITED STATES

NUCLEAR REGULATORYCOMMISSION

REGION V

1450 MARIALANE

WALNUTCREEK, CAUFORNIA94596-5368

dAN.

Docket Nos. 50-275

and 50-323

Pacific

Gas

and Electric Company

77 Scale Street,

Room 1451

San Francisco,

California 94106

Attention:

Mr. G.

M. Rueger,

Senior Vice President

and General

Manager,

Nuclear

Power Generation

Business

Unit

Gentlemen:

Subject:

NRC Inspection of Diablo Canyon Units

1 and

2

This refers to the routine inspection

conducted

by H. gong

and M. Miller

during the period of November

19 through

December .31,

1991.

This inspection

examined your activities

as authorized

by NRC License

Nos.

DPR-80

and DPR-82.

At the conclusion of the inspection,

discussions

of their findings were held

with you and other members of your staff.

Areas

examined during this inspection

are described

in the enclosed

inspection

report.

Within these

areas,

the inspection consisted of selective

examinations

of procedures

and representative

records,

interviews with

personnel,

and observations

by the inspectors.

No violations of NRC requirements

were identified

as

a result of this

inspection.

However, this inspection

noted weaknesses

in the preparation

and

implementation of an operability evaluation involving post-accident

monitoring

instrumentation,

which had

been reviewed

by the Plant Staff Review Committee

and approved

by the acting plant manager.

Factual errors

were made

and

corrective actions stated

in the evaluation

were not in all cases fully

implemented.

This demonstr ates

a need for engineering

personnel

to more fully

~ understand

the plant configur ation

and for corrective actions to be fully

coordinated

and verified.

We note that you have initiated certain actions

which should prevent these errors from recurring.

In addition, your attention is directed to paragraph

6.a,

which discusses

the

continuing problem associated

with the steam

admission

valve to the Unit

1

turbine-driven auxiliary feedwater

pump (FCV-95).

We are concerned with the

lack of identification of a root cause of the intermittent failures of

FCV-95.

We note that you are continuing to monitor the valve

and will be

i'nstrumenting the

same valve in Unit 2.

In accordance

with 10 CFR 2.790(a),

a copy of this letter

and the enclosure

will be placed in the

NRC Public Document

Room.

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Mr. G. M. Rueger

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Should you have

any questions

concerning this inspection,

we will be pleased

to discuss

them with you.

Sincerely,

S. A. Richards,

Chief

Reactor Projects

Branch

Enclosure:

Inspection Report Nos. 50-275/91-40

and 50-323/91-40

cc w/enclosure:

J.

A. Sexton,

PG5E

R. F. Locke,

PG5E

J.

D. Townsend,

PGLE (Diablo Canyon)

D. A. Taggart,

PGSE (Diablo Canyon)

T. L. Grebel,

PGEE (Diablo Ca;;on)

B. Thomas,

News Services,

PGEE

R. Hendrix, County Administrator

State of California

Sandra Silver

bcc w/enclosure:

Project Inspector

Resident

Inspector

Docket File

J. Martin

B. Faulkenberry

G.

Cook

bcc w/o enclosure:

M. Smith

J.

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J. Bianchi

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