ML17331B404
| ML17331B404 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/27/1994 |
| From: | Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17331B405 | List: |
| References | |
| NUDOCS 9406070069 | |
| Download: ML17331B404 (4) | |
See also: IR 05000315/1994007
Text
ACCELERATED DOCUMENT DISTRIBUTIONSYSTEM
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9406070069
DOC.DATE: 94/05/27
NOTARIZED:
NO
DOCKET
FACIL:50-315 Donald
C.
Cook Nuclear Power Plant, Unit 1, Indiana
M
05000315
50-316 Donald
C.
Cook Nuclear Power Plant, Unit 2, Indiana
M
05000316
~
AUTH.NAME
AUTHOR AFFILIATION
RING,M.A.
Region
3 (Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
FITZPATRICK,E.
Co.
(formerly Indiana
& Michigan Ele
D
SUBJECT:
Forwards Insp Repts 50-315/94-07
& 50-316/94-07
on 940411-22
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED:LTR
ENCL
SIZE:
TITLE: General
(50 Dkt)-Insp Rept/Notice of Via%ation Response
/
NOTES'ECIPIENT
ID CODE/NAME
PD3-1
COPIES
RECIPIENT
LTTR ENCL
ID CODE/NAME
1
1
HICKMAN,J
COPIES
LTTR ENCL
1
1
A
D
INTERNAL: AEOD/DEIB
AEOD/DSP/TPAB
DEDRO
NRR/DRCH/HHFB
NRR/DRSS/PEPB
NUDOCS-ABSTRACT
OGC/HDS2
RES/HFB
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
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AEOD/DSP/ROAB
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NRR/DRIL/RPEB
NRR/PMAS/ILPB1
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HEDOCUMENT CONTROL DESK,
ROOM P1-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION
LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
21
ENCL
21
D
May 27,
1994
Docket No. 50-315
Docket No. 50-316
Company
ATTN:
Mr. E.
E. Fitzpatrick
Vice President
1 Riverside
Plaza
Columbus,
OH
43216
Dear Mr. Fitzpatrick:
This refers to the routine safety inspection
conducted
by Messrs.
C. Gill and
K. Salehi of this office from April 11 through 22,
1994.
The inspection
included
a review of activities at the
D.
C.
Cook Nuclear Plant, Units
1
and
2, authorized
by
NRC Operating
Licenses
No.
and
At the
conclusion of the inspection,
the findings were discussed
with you and those
members of your staff identified in the enclosed
report.
Areas
examined during the inspection
are identified in the report.
Within
these
areas,
the inspection consisted
of a selective
examination of procedures
and representative
records,
observations
of activities in progress,
and
interviews with personnel.
The purpose of the inspection
was to determine
whether engineering activities authorized
by the license
were conducted
safely
and in accordance
with NRC requirements.
During this inspection,
we noted weaknesses
regarding
communications,
engineering
assessments,
and inattention to detail.
These
weaknesses
resulted
in significant plant problems,
including failures to follow your own
procedures,
improper
CCW system operation
due to acceptance
by operations
personnel'f
unsubstantiated
engineering
judgements,
and
an inefficient and
cumbersome
modification of the diesel starting air compressors.
These
issues
collectively point out the need for additional
management
attention.
Based
on the results of this inspection,
certain of your activities appeared
to be in violation of NRC requirements
as specified in the enclosed
Notice of
Violation (Notice).
The violation was for failure to perform
a required
safety evaluation of a proposed
change
in the facility, as described
in the
Updated Safety Analysis Report
(USAR), to ascertain
whether the proposed
change
involved
an unreviewed safety question.
The violation is of concern
because
the
USAR upper-limit design temperature
of 95'F for'he Component
Cooling Water
(CCW) supply was authorized
by the Operations
Department
Superintendent
to be increased
to 105'F for Unit
1 without a required safety
evaluation
and without
a revision to the
CCW operating
procedure,
which
specified the
same
95OF limitation.
Subsequently,
the
CCW supply temperature
increased
to 110oF because
of operation inattention during
induced
by intermittent boric acid evaporator operation
on January
27 and 28,
1994.
Contributing factors to exceeding
the
CCW specified supply temperature
included
inadequate
communications
between
the
CCW system engineer
and the
940607006'7
940527
ADQCK 05000315
Q
Company
May 27,
1994
operations
department,
and the failure of the operations
department
to reset
the
CCW supply (heat
exchanger outlet) temperature
alarm setpoint
from 95'F to
105'F.
We request that you address
the safety significance of the event,
the
above concerns
and contributing factors,
and the conclusions of your ongoing
root cause
team investigation
in your response.
You are required to respond to this letter and you should follow the
instructions specified in the enclosed
Notice when preparing your response.
In your response,
you should document
the specific actions
taken
and
any
additional
actions
you plan to prevent recurrence.
After reviewing your
response
to this Notice, including your proposed corrective actions
and the
results of future inspections,
the
NRC will determine whether further
NRC
enforcement
action is necessary
to ensure
compliance with NRC regulatory
requirements.
In accordance
with 10 CFR 2.790 of the Commission's
regulations,
a copy of
this letter,
the enclosures,
and your response
to this letter will be placed
in the
NRC Public Document
Room.
The responses
directed
by this letter and the accompanying
Notices
are not
subject to the clearance
procedures
of the Office of Management
and Budget
as
required
by the Paperwork
Reduction Act of 1980,
PL 96-511.
We will gladly discuss
any questions
you have concerning this inspection.
Sincerely,
/s/ B. Burgess
Hark A. Ring, Chief
Operations
Branch
Enclosures;
1.
2.
Inspection
Reports
No. 50-315/94007(DRS);
No. 50-316/94007(DRS)
cc w/enclosures:
A. A. Blind, Plant Manager
OC/LFDCB
Resident
Inspector, RIII
James
R. Padgett,
Michigan Public
Service'Commission
EIS Coordinator,
USEPA
Region
5 Office
Michigan department of Public Health
D.
C. Cook,
LPH,
S. Stein,
bcc:
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