ML17334B167
| ML17334B167 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/28/1987 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17334B168 | List: |
| References | |
| NUDOCS 8801070070 | |
| Download: ML17334B167 (3) | |
See also: IR 05000315/1987026
Text
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Docket Nos.
50-315
50-316
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
QEt,'- 2 8 1981
American Electric Power Service Corporation
Company
ATTN:
Mr.,John
E. Dolan
Vice President
1 Riverside'laza
Columbus,
OH
43216
Gentlemen:
SUBJECT:
NRC INSPECTION AT DONALD C.
COOK, UNITS
1 AND 2
INSPECTION
REPORT
NOS. 50-315/87-26'0-316/87-26
This special
inspection,
conducted
by Messrs.
R. Correia,
N. Choules,
T. Cooper,
K. Hooks,
S.
Reynolds
and A. Toth of this office on October
19
through 30, 1987, focused
on the ability of your quality verification
organizations
to identify, solve,
and prevent safety-significant technical
deficiencies
in functional areas
encompassing
plant systems
and operations.
The inspection also assessed
line management's
effectiveness
in dealing with
identified deficiencies
promptly and completely.
At the conclusion of the
inspection,
our findings in these
areas
were discussed
with Messrs.
M.
Alexich, W. Smith, Jr.
and other members of your staff.
The results of the inspection indicate that the guality Assurance
Department
and the Safety
and Assessment
organization that includes guality Control, are
evolving into effective performance-oriented
organizations.
The Safety
and
Assessment
organization is assertive
in pursuing
and trending safety-
significant issues,
most notably in the operations
area.
The inspectors
noted
guality Assurance's visibility in the control
rooms
and encourage
even
more
monitoring of control
room activities.
We recommend that guality Assurance
take
a more active role during their reviews of control
room activities,
such
as noting activated annunciators
and alarms
and conferring with control
room
personnel
concerning the plant status.
The
NRC considers
the recurring operability problems that have existed for
several
years with both units'ressurizer
spray valves to be of significance.
Root cause
determinations
and corrective actions
appear to have taken
a
lengthy period of time considering that proper operation of these
valves is
necessary
to control reactor coolant pressure
and to prevent challenges
to the
pressurizer
heaters
and power operated relief valves.
We did note your recent
actions to resolve this issue,
and
we are interested
as to whether this
program is successful
and its potential application at other facilities with
similar valve problems.
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The
NRC is also concerned with the improper maintenance
and storaae of
materials
and equipment for modifications of systems
and components.
One of
the two storaae
areas
examined
by the inspectors
did not have proper
temperature
and humidity controls and, in both, there
was
no preventive
maintenance for anv stored equipment,
includina safety-related
valves
and
electrical devices.
The lack of prescribed
preventive maintenance
and the
uncontrolled environment that installed
and uninstalled safety-related
equipment
may have
been subjected
to are considered
to be sianificant
weaknesses
in your maintenance
and storaoe
proarams.
We encouraae
you to improve those
areas of concern identified in the enclosed
report and to promote the involvement of all plant oraanizations
and personnel
in the assurance
of quality.
The existence of sianificant problems reflects
on the performance
and commitments of all plant personnel,
particularly
manaaement.
The assurance
of quality rests primarily with the line
oraanization
which produces
the work product and secondarily with the quality
verification oraanizations
which verify that quality was achieved.
To that
end, the
NRC expects quality verification oraanizations
to be performance-
oriented
and capable of identifyina, reportina,
and resolvina issues of
safety-sianificance.
In accordance
with 10 CFR 2.790(a),
a copy of this letter and the enclosures
will be placed in the
NRC Public Document
Room.
We will aladly discuss
any questions
you have concernina this inspection.
Sincerely,Q~
De
M. Crutch ield, Director
Division of Reactor Projects III/IV/V
Office of Nuclear Reactor Reaulation
Enclosure:
Inspection
Report Nos. 50-315/87-26,
50-316/87-26
cc:
w/enclosures
W.
G. Smith, Jr., Plant Manaaer