ML16341G122
| ML16341G122 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/31/1991 |
| From: | Richards S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML16341G123 | List: |
| References | |
| NUDOCS 9106180104 | |
| Download: ML16341G122 (4) | |
See also: IR 05000275/1991010
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION V
1450 MARIALANE,SUITE 210
WALNUTCREEK, CALIFORNIA94595
Docket Nos.
50-275
and 50-323
Pacific
Gas
and Electric Company
77 Beale Street,
Room 1451
San Francisco,
California 94106
MAY 3
>
egg!
Attention:
. Nr. J.
D. Shiffer, Senior Vice President
and General
Manager
Nuclear
Power Generation
Subject:
NRC Inspection of Diablo Canyon Units
1 and
2
During the period of March
17 through April 27,
1991, Ilr. P. Narbut and Mr. K.
Johnston of this office conducted
a routine inspection of activities
authorized for the Diablo Canyon
Power Plant.
At the conclusion of the
inspection,
Nr. Johnston
discussed
the findings with members of your staff
identified in the enclosed
report.
leII
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,
two items in this report are worthy of management
attention.
The installation of check valves in the
RHR system in a vertical position
which rendered
them nonfunctional
(paragraph 4.f), and the installation of a
motor for the auxiliary feedwater
system,
which did not have the appropriate
environmental qualification documentation
(paragraph 4.e), indicate potential
weaknesses
in communications
between
design engineering
and the plant staff..
Your attention is also directed to paragraph
4.g concerning
a recent
problem
in the determination of operability of the auxiliary feedwater
system
when
associated
ventilation systems
were out of service.
The lack of requirements
to involve management
personnel
and to clearly document operability rationale
in cases
where operability is not readily apparent
was previously raised at
the end of 1990 regarding
valve
FCV-95 and still remains to be resolved.
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 pleased
to discuss
them with you.
Sincerely,
'71 061 801 04 910531
ADDCK 050002'75
G
S.
A. Richards,
Chief
Reactor Projects
Branch
Enclosure:
Inspection
Report Nos. 50-275/91-10
and 50-323/91-10
I
\\'
cc w/enclosure:
J.
A. Sexton,
PGE;E
J.
D. Townsend,
Vice President/Plant
Manager,
PGIIE
R.
F. Locke, Esq., Attorney
D. A. Taggert, Director, equality Support,
PGSE
B. Thomas,
News Services,
PGIIE
T. L. Grebel,
Regulatory
Compliance Supervisor,
PGKE
State of California
Sandra Silver
QAY 3
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