ML16341G334
| ML16341G334 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| 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.
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
ADDCH 0
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
Region V/dkm <
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