ML17333A765
| ML17333A765 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/04/1997 |
| From: | Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17333A766 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 9702070466 | |
| Download: ML17333A765 (6) | |
See also: IR 05000315/1996013
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
'CCESSION NBR:9702070466
DOC.DATE: 97/02/04
NOTARIZED: NO
DOCKET
FACIL:50-315 Donald C.
Caok 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
GRANT,G.E.
Region
3 (Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION *
FITZPATRICK,E.
American Electric Power Co., Inc.
SUBJECT:
Forwards
insp rept 50-315/96-13
& 50-316/96-13
on 961213
&
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED:LTR
ENCL
SIZE:
TITLE: General
(50 Dkt)'-Insp Rept/Notice of Vio ation
R sponse
NOTES:
RECIPIENT
ID CODE/NAME
PD3-3
INTERNAL: AEOD/SPD/RAB
DEDRO
NRR/DISAP/PIPB
NRR/DRPM/PECB
NUDOCS-ABSTRACT
OGC/HDS2
XTERNAL: LITCO BRYCEgJ
H
NRC PDR
COPIES
LTTR ENCL
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
RECIPIENT
ID CODE/NAME
HICKMANgJ
AEOD~
FIL
NTER
HFB
NRR/DRPM/PERB
OE DIR
RGN3
FILE
01
NOAC
COPIES
LTTR ENCL
1
1
1
1
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0
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0
E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS
OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL
DESK
(DCD)
ON EXTENSION 415-2083
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR.
17
ENCL
17
T
February 4,
1997
EA 97-20
Mr. E. E. Fitzpatrick
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
SYSTEM OPERATIONAL PERFORMANCE INSPECTION (SOPI) REPORT
NOS. 50-315/96013(DRS);
50-316/96013(DRS),
NOTICE OF DEVIATION,
Dear Mr. Fitzpatrick:
On December 13, 1996, the NRC completed a system operational performance inspection
(SOPI) at your Donald C. Cook facility. The enclosed report presents the results of that
inspection.
.
Based on the inspection results, certain of your activities appeared to be in violation of
NRC requirements,
as specified in the enclosed Notice of Violation (Notice). The violations
are of concern because
timely corrective actions for identified problems, adherence
to
station procedures,
adequate
procedures,
and appropriate testing acceptance
criteria, are
all important aspects of safe plant operation.
In particular, we are concerned about
problems identified regarding our design performance review of the centrifugal charging
pumps.
You are required to respond to this letter and 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 take 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.
Also, based on the results of this inspection, certain of your activities, set forth in the
enclosure to this letter, appear to be a deviation from commitments which you have made
in previous correspondence
with the Commission regarding the use of NUREG-0737
assumptions
in the design basis accident radiological analysis.
A written response
is
requested.
In addition, the inspectors identified several examples where technical specification
interpretations could not be technically justified. Although the consequences
cf the
inadequate interpretations were not significant, we are concerned about the effectiveness
of the technical specification interpretation review process and the possibility that
9702070466
970204
ADOCK 050003i5
8
E. E. Fitzpatrick
February 4, 1997
additional technical specification interpretation problems may exist.
As a result, and as
discussed at the December 13, 1996 exit meeting, you committed to provide the results
of your review of your remaining technical specification interpretations.
You are requested
to provide these results within 30 days of receipt of this letter.
Also, at the end of the inspection, the inspectors were provided with calculations which
were subsequently
reviewed.
As a result of that review, additional questions were
developed as discussed
in Attachments A and B of this report.
You are requested to
provide, within 60 days of receipt of this letter, a written response
to these questions.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter,
its enclosures,
and your response will be placed in the NRC Public Document Room (PDR).
To the extent possible, your response
should not include any personal privacy, proprietary,
or safeguards
information so that it can be placed in the PDR without redaction.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
/s/ G. E. Grant
Geoffrey E. Grant, Director
Division of Reactor Safety
Docket Nos.:
50-315, 50-316
License Nos.:
Enclosures
1.
Notice of Deviation
2.
3.
Inspection Report
No. 50-315/96013(DRS);
No. 50-316/96013(DRS)
S
Ata he
Di
rib in
DOCUMENT NAME: G:iDRSiDCC96013.DRS
SEE ATTACHED CONCURRENCES
To receive e copy of this document, indicate in the box 'C'
Copy w/o attach/encl 'E
Copy w/attach/encl 'N
~ No copy
OFFICE
NAME
DATE
RIII:DRS
Duncan Butler
01/
97
RIII:DRP
RI II:DRS
Garder Rin
Ol/
/97
Miller
Ol/
/97
OFFICIAL RECORD
COPY
RI I I:DRS
Leach
02/
4T
E. E. Fitzpatrick
Also, at the end of the inspection, the inspectors were provided with calculations which
were subsequently
reviewed.
As a result of that review, additional questions were
developed for which additional information is required as discussed
in Attachments A and
B of this report.
You are requested to provide, within 60 days of receipt of this letter, a
written response to these requests.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter,
its enclosures,
and your response will be placed in the NRC Public Document Room (PDR).
To the extent possible, your response
should not include any personal privacy, proprietary,
or safeguards
information so that it can be placed in the PDR without redaction.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
Geoffrey E. Grant, Director
Division of Reactor Safety
Docket Nos.:
50-315, 50-316
License Nos.:
Enclosures:
1.
2.
Inspection Report
No. 50-315/96013(DRS);
No. 50-316/96013(DRS)
cc w/encls:
A. A. Blind, Site Vice President
John Sampson,
Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of Public Health
SEE ATTACHED CONCURRENCES
DOCUMENT NAME: G:ttDRSttDCC96013.DRS
To receive a copy of this document, indicate in the box "C" ~ Copy w/o attach/encl "E" ~ Copy w/attach/encl "N" ~ No
copy
CFF ICE
I I I:CRS
RI I I'l
I I;CRP
Rl I I:CRS
ncan/But
CATE
01/ i
/97
Gard
/Rin
01 /
/97
~ther
01 /
/97
Leach/Grant
01/
/97
E. E. Fitzpatrick
February 4,
1997
cc w/encls:
A. A. Blind, Site Vice President
John Sampson,
Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of Public Health
~Dis ri
ion:
Docket File w/encl
IPUBL'ICtIE-01 w/encl
OC/LFDCB w/encl
DRP w/encl
DRS w/encl
Rill PRR w/encl
SRI, D. C. Cook w/encl
LPM, NRR w/encl
A. B. Beach, Rill w/encl
W. L. Axelson, Rill w/encl
Enf. Coordinator, Rill w/encl
CAA1 w/encl
J. Lieberman, OE w/encl
J. Goldberg, OGC w/encl
R. Zimmerman, NRR w/encl