ML16341G334

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Forwards Insp Rept 50-275/91-25 & 50-323/91-25 on 910729-0802 & 19-23.No Violations or Deviations Noted. Findings Indicate Weakness in Proper Identification & Evaluation of Safety Significant Problems
ML16341G334
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 10/18/1991
From: Kirsch D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Shiffer J
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML16341G335 List:
References
NUDOCS 9111040075
Download: ML16341G334 (6)


See also: IR 05000275/1991025

Text

UNITED STATES

NUCLEAR REGULATORY COMIVIISSION

REGION V

1450 MARIALANE, SUITE 210

WALNUTCREEK. CALIFORNIA94596 5368

OvT ] j

199)

Docket Nos.

50-275

and

50-.323

Pacific Gas

and Electric Company

'7 Beale Street,

Room 1451

San Francisco,

California 94106

Attention:

Nr. J.

D. Shiffer, Senior Vice President

Nuclear

Power Generation

Business

Unit

Gentlemen:

SUBJECT:

NRC- INSPECTION

OF DIABLO CANYON UNITS 1 AND 2

This refers to an unannounced

inspection

conducted. by Messrs.

M, Royack,

F.

Gee,

and

P.

Galon of this office during the weeks'f July 29 through August 2,

and August 19 through August 23,

1991, of activities authorized

by

NRC license

Nos.

DPR-80 and DPR-82,

and to the discussion

of our findings held with members

of your staff at the conclusion of the inspection.

The inspection

was reopened

on September

20 to review an operability evaluation for Unit 1 4kv/480 volt

transformers.

A followup exit was held by telephone

on October 8,

1991 to

discuss

the results of the operability

review.

Areas

exami'ned during this inspection

are described

in the enclosed

inspection

report.

Mithin these

areas,

the inspection consisted of selective

examinations

of procedures

and representative

records,

interviews with personnel,

and

observations

by the inspectors.

The findings discussed

in this report indicate

a weakness

in the proper

identification and evaluation of safety significant problems which require

an

operability evaluation

be performed.

In this regard,

the inspectors

identified

. two occasions

where earlier operability evaluations

would have

been beneficial

in determining the capability of equipment to perform their design safety

functions.

This weakness

appears

to have

a root cause

based

in poor,

coordination of day to day operating information between your site engineering

and your corporate

design engineering staffs,

and

a lack of appropriate

procedural

guidance for identifying and evaluating

probtems requiring

performance of operability evaluations.

Me understand that you have recognized this procedural

deficiency and will be

issuing

a procedure to address

the issue.

Me consider that engineering

coordination

and information transfer are

key factors in identifying and

resolving potentially safety significant issues

before they become

problems.

Accordingly,

we will continue to review your progress within this area during

future inspections.

cyf1 10 I0075

5000P75

g) )0ia

PDR

ADDCH 0

PDR

G

-2-

No violations or deviations

were identified during this inspection.

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.

Should you have

any questions

concerning this inspection,

we will be glad to

discuss

them with you.

Sincerely,

Dennis

F. Kirsch, Chief

Reactor

Safety Branch

Enclosure:

Inspection

Report

No. 50-275/91-25,

50-323/91-25

cc w/enclosure:

J.

A. Sexton,

PG8E,

J.

D. Townsend,

Vice President/Plant

Manager,

PG8E

R.

F.

Locke, Esq., Attorney

D.

A. Taggart, Director, equality.Support,

PGKE

B. Thomas,

News Services,

PG8 E

T.

L. Grebel,

Regulatory

Compliance Supervisor,

PG8E

State of California

B. Hendrix, County Administrator

Sandra Silver

bcc w/enclosure

Docket File

Resident Inspector

Project Inspector

G.

Cook

K. Perkins

R.

Zimmerman

B. Faulkenberry

J. Martin

bcc w/o enclosure:

J. 2ollicoffer

M. Smith

J.

Bianchi

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