ML17333A788
| ML17333A788 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/19/1997 |
| From: | Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17333A790 | List: |
| References | |
| NUDOCS 9703030284 | |
| Download: ML17333A788 (11) | |
See also: IR 05000315/1996015
Text
CATEGORY 2
I
REGULATORY'INFORMATION DISTRIBUTION SYSTEM (RIDS)
.I ACCESSION NBR:9703030284
DOC.DATE: 97/02/19
NOTARIZED: NO
FACIL:50-315 Donald C.
Cook Nuclear
Power Plant, Unit 1, Indiana
M
"50-316 Donald
C.
Cook Nuclear
Power Plant, Unit 2, Indiana
M
UTH.NAME
AUTHOR AFFILIATION
LDWELL,J.L.
Region
3 (Post
820201)
ECIP.NAME
RECIPIENT AFFILIATION
FITZPATRICK,E.
American Electric Power Co., Inc.
SUBJECT:
Forwards insp repts
50-315/96-15,50-316/96-15
& notice of
violation.
DOCKET
05000315
05000316
DISTRIBUTION CODE:
IEOZT
COPIES
RECEIVED:LTRj ENCL J
BISE:
+2
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:
RECIPIENT
ID CODE/NAME
PD3-3
COPIES
LTTR ENCL
1
1
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HICKMAN,J
COPIES
LTTR ENCL
1
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INTERNAL: AEOD/SPD/RAB
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NOTE TO ALL "RIDS" RECIPIENTS:
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LTTR
18
ENCL
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February 19, 1997
Mr. E. E. Fitzpatrick
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC INSPECTION REPORT NO. 50-315/316-96015(DRP)
Dear Mr. Fitzpatrick:
On January 5, 1997, the NRC completed an inspection at your D. C. Cook
1 and 2 reactor
facilities. The enclosed report presents the results of that inspection.
During the 6-week periodcovered by this inspection report, the inspectors observed that
the plant was operated in a safe manner, personnel followed procedures,
and engineering
evaluations were promptly performed.
Based on the results of this inspection, the NRC has determined that two violations of NRC
requirements occurred.
The violations are cited in the enclosed Notice of Violation (Notice)
and the circumstances
surrounding them are described in detail in the subject inspection
report.
The first violation was of concern because there were a number of examples of a
failure to comply with technical specifications regarding the completion of a breaker
alignment surveillance check.
Although the actual safety consequence
was minor, their
was regulatory significance based on the inconsistent performance by D.C. Cook staff
regarding when to conduct the surveillance.
The second violation was of concern because
it involved the use of an engineering memorandum to approve the selection of nonsafety-
related piping for use on a safety-related system.
Although we did not identify additional
examples of this violation, we are concerned that any method exists that would bypass
the normal engineering processes for dedication of nonsafety-related
parts for application
in safety-related systems.
In addition to the above violations, the NRC identified a concern regarding test personnel
misreading a spring scale during a backdraft damper surveillance.
This concern indicated
that test personnel may not have sufficient training to properly read test equipment.
This
conclusion was supported by a review of previous backdraft damper surveillances that
identified additional examples of improper spring scale use by other test personnel.
Please
provide, in addition to your response to the above violations, your corrective actions in
response to this concern.
9703030284
9702i9
ADQCK 050003i5
8
IIIIIIIIHlllltIHIIlIIIBIBIIIEIIIEIIHllll
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E. E. Fitzpatrick
-2-
You are required to respond to this letter and should followthe instructions specified in the
enclosed Notice when preparing your response.
The NRC willuse your response,
in part,
to determine whether further enforcement action is necessary to ensure compliance with
regulatory requirements.
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) ~
Sincerely,
Docket Nos.: 50-315, 50-316
/s/John
A. Grobe for
James
L. Caldwell, Director
Division of Reactor Projects
Enclosure:
2. Inspection Report
-31 5/31 6-9601 5(DRP)
No. 50
cc w/encl:
A. A. Blind, Site Vice President
John Sampson,
Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of
Public Health
Docket File w/encl
DRP w/encl
PUBLIC IE-01 w/encl
Rill PRR w/encl
OC/LFDCB w/encl
SRI D. C. Cook w/encl
A. B. Beach, w/encl
Rill Enf. Coordinator, w/encl
W. L. Axelson, w/encl
CAA1 w/encl (E-mail)
DRS (3) w/encl
TSS w/encl
(See attached concurrence)
Document:
R:iinsprptshpowershcookhdcc96015.drp
To receive a copy of this document, indicate in the box "C" = Copy without attach/encl
"E" = Copy with attach/encl
"N" = No copy
OFFICE
RI I I
Rill
Rill
NAME
Maynen
Burge
Idwell
DATE
02/I 1/97
024'97
02 %97
OFFICIAL RECORD COPY
E. E. Fitzpatrick
-2-
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).
Sincerely,
- Docket Nos.: 50-315, 50-316
James
L. Caldwell, Director
Division of Reactor Projects
cc w/encl:
Enclosure:
2. Inspection Report
No. 50-315/316-96015(DRP)
A. A. Blind, Site Vice President
John Sampson,
Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of
Public Health
Docket File w/encl
PUBLIC IE-01 w/encl
OC/LFDCB w/encl
SRI D. C. Cook w/encl
Rill Enf. Coordinator, w/encl
CAA1 w/encl (E-mail)
TSS w/encl
DRP w/encl
Rill PRR w/encl
A. B. leach, w/encl
W. L. Axelson, w/encl
DRS (3) w/encl
Document:
R:hinsprpts>powers>cookhdcc96015.drp
To receive a copy of this document, indicate in the'box "C" = Copy without attach/encl
"E" = Copy with attach/encl
"N" = No copy
Rill
OFFICE
RIII
RIII
NAIVIE
Maynen
Bur
ss
Grobe/Caldwell
02/ /97
OFFICIAL RE
ORD
PY
DATE
02/l) /97
02/ 397
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UNITED STATES
NUCLEAR REGULATORYCOMMISSION
REGION III
801 WARRENVILLEROAD
USLE. ILLINOIS60532-'4351
February
19,
1997
Mr. E. E. Fitzpatrick
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC INSPECTION REPORT NO. 50-315/316-96015(DRP)
Dear Mr. Fitzpatrick:
On January 5, 1997, the NRC completed an inspection at your D. C. Cook
1 and 2 reactor
facilities. The enclosed report presents the results of that inspection.
During the 6-week period covered by this inspection report, the inspectors observed that
the plant was operated in a safe manner, personnel followed procedures,
and engineering
evaluations were promptly performed.
Based on the results of this inspection, the NRC has determined that two violations of NRC
requirements occurred.
The violations are cited in the enclosed Notice of Violation (Notice)
and the circumstances
surrounding them are described in detail in the subject inspection
report.
The first violation was of concern because there were a number of examples of a
failure to comply with technical specifications regarding the completion of a breaker
alignment surveillance check. Although the actual safety consequence
was minor, their
was regulatory significance based-on the inconsistent performance by D.C. Cook staff
regarding when to conduct the surveillance.
The second violation was of concern because
it involved the use of an engineering memorandum to approve the selection of nonsafety-
related piping for use on a safety-related system.
Although we did not identify additional
examples of this violation, we are concerned that any method exists that would bypass
the normal engineering processes for dedication of nonsafety-related
parts for application
in safety-related systems.
In addition to the above violations, the NRC identified a concern regarding test personnel
misreading a spring scale during a backdraft damper surveillance.
This concern indicated
that test personnel may not have sufficient training to properly read test equipment.
This
conclusion was supported by a review of previous backdraft damper surveillances that
identified additional examples of improper spring scale use by other test personnel.
Please
provide, in addition to your response to the above violations, your corrective actions in
response to this concern.
'I
f
ll
t
k
l
E. E. Fitzpatrick
-2-
You are required to respond to this letter and should follow the instructions specified in the
enclosed Notice when preparing your response.
The NRC will use your response,
in part,
to determine whether further enforcement action is necessary to ensure compliance with
regulatory requirements.
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).
Sincerely,
ames L. Caldwell, Director
Division of Reactor Projects
Docket Nos.: 50-315, 50-316
Enclosure:
2. Inspection Report
No. 50-31 5/31 6-9601 5(0RP)
cc w/encl:
A. A. Blind, Site Vice President
John Sampson,
Plant Manager
James
R. Padgett, Michigan Public
Service Commission
Michigan Department of
Public Health
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