ML17334B722
| ML17334B722 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 04/10/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17334B723 | List: |
| References | |
| 50-315-98-05, 50-315-98-5, 50-316-98-05, 50-316-98-5, EA-98-150, EA-98-151, EA-98-152, NUDOCS 9804170060 | |
| Download: ML17334B722 (8) | |
See also: IR 05000315/1998005
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9804170060
DOC.DATE: 98/04/10
NOTARIZED: NO
DOCKET ¹
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
GROBE,J.A.
Region
3
(Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
FITZPATRICK,E.
(formerly Indiana
& Michigan Ele
SUBJECT:
Forwards insp repts
50-315/98-05
& 50-316/98-05
on 980121-
0227
& 0319.Violations noted.Insp
reviewed activities
related to surveillance testing, corrective action
& maint of
design basis for ice condenser.
DISTRIBUTION CODE'EOIF
COPIES
RECEIVED'LTRI ENCL
i
SIZE'
7
TITLE: General
(50 Dkt) -Insp Rept/Notice of Violation Response
NOTES:
37
C
E
INTERNAL:
RECIPIENT
ID CODE/NAME
PD3-3
AEOD/SPD/RAB
DEDRO
NRR/DRCH/HHFB
NRR/DRPM/PERB
OE DIR
RGN3
FILE
01
COPIES
LTTR ENCL
1
1
1
1
1
1
1
1
1
1
1
1
1
1
RECIPIENT
ID CODE/NAME
STANG,J
L
NRR/DRPM/PECB
NUDOCS-ABSTRACT
OGC/HDS2
COPIES
LTTR ENCL
1
1
1
1
1
1
1
1
1
1
1
1
0
2
EXTERNAL: LITCO BRYCE,J H
NRC PDR
1
1
1
1
NOAC
NUDOCS FULLTEXT
1
1
1
1
D
16AMO WOM
NRC FLOPPY
NOTE TO ALL "RZDS" 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
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April 10,
1998
Mr. E. E. Fitzpatrick
Executive Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
SUBJECT:
NRC INSPECTION REPORT NO. 50-315/98005(DRS); 50-316/98005(DRS)
Dear Mr. Fitzpatrick:
On February 27, 1998, the NRC completed an on-site inspection at your D. C. Cook 1 and 2
reactor facilities. A final exit to update your staff on the regulatory characterization of issues
identified in this inspection was conducted by telephone on March 19, 1998. The purpose of
this inspection was to review your activities related to surveillance testing, corrective action and
maintenance of the design basis for the ice condenser.
The enclosed report presents the
results of this inspection.
Based on the results of this inspection, 29 apparent violations were identified and are being
considered for escalated enforcement action in accordance with the "General Statement of
Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600.
These apparent violations are grouped into three areas; surveillance testing, corrective action
and maintenance of the design basis as discussed
below.
Eight apparent violations of 10 CFR 50 Appendix B (three Criterion V, four Criterion XI, and one
Criterion Vll)and two apparent violations of technical specifications were identiTied pertaining to
inadequate surveillance testing of the ice condenser.
Specifically, these violations related to,
inadequate instructions, inadequate acceptance
limits, inadequate control of contractors, failure
to implement technical specification requirements and entry into an unanalyzed condition.
Additionally, an apparent violation 10 CFR 50 Appendix B, Criterion V was identiTied for failure
to followthe procedure change process for completed surveillance tests.
Collectively, these
apparent violations represent a programmatic breakdown in surveillance testing of the ice
condenser.
Seven apparent violations of 10 CFR 50 Appendix B, Criterion XVIwere identified pertaining to
your staffs failure to promptly identify conditions adverse to quality or take appropriate
cor'rective actions.
Inspectors'ntervention
was necessary to prompt your staff to identify:
blocked flow passages,
missing ice segments,
dented/buckled basket webbing, unweighable
ice baskets, and nonencapsulated
insulation within the ice condenser.
Further,
inspectors'ntervention
was necessary
to prompt your staff: to implement corrective actions for missing ice
'7804i70060
98041.0
ADOCK 050003i5
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E. Fitzpatrick
basket sheet metal screws, to take corrective actions for preventing the recurrence of loose
U-bolt nuts and separated
ice baskets, and to take appropriate corrective actions for the ice
baskets with defective hold down bar welds.
Collectively, these apparent violations represent a
breakdown in your corrective action program for the ice condenser.
Seven apparent violations of 10 CFR 50.71(e) were identified pertaining to your staff's failure to
update and maintain the Final Safety Analysis Report Appendices J and M, which contain the
detailed description and design basis for the ice condenser.
Additionally, four apparent
violations of 10 CFR 50 Appendix B, Criterion IIIwere identified pertaining to a failure to follow
the established design control process for ice basket modifications. Collectively, these
apparent violations represent a programmatic breakdown in the maintenance of the design
basis for the ice condenser.
NRC intervention was needed to call attention to these programmatic problems.
Further, the
weaknesses
in each of these program areas has directly or indirectly contributed to a poor state
of materiel condition for each ice condenser,
such that the ability of the ice condenser to
perform its design function during past plant operation is in question.
Allowingthe ice
condensers
to degrade to this condition demonstrates
that your staff did not pay appropriate
attention to maintaining the reliability and availability of a key safety system.
No Notice of Violation is presently being issued for these apparent violations.
In addition, be
advised that the number and characterization of the apparent violations described in the
enclosed inspection report may change as a result of further NRC review.
An open predecisional enforcement conference to discuss these apparent violations will be
scheduled
in the near future. The decision to hold a predecisional enforcement conference
does not mean that the NRC has determined that violations occurred or that enforcement action
willbe taken.
This conference will be held to obtain information to enable the NRC to make an
enforcement decision, such as a common understanding of the facts, root causes,
missed
opportunities to identify the apparent violations sooner, corrective actions, significance of the
issues, and the need for lasting and effective corrective action.
In addition, this is an
opportunity for you to provide any information concerning your perspectives
on:
1) the severity
of the violations, 2) the application of the factors that the NRC considers when it determines the
amount of a civil penalty that may be assessed
in accordance with Section VI.B.2 of the
Enforcement Policy, and 3) any other application of the Enforcement Policy to this case,
including the exercise of discretion in accordance with Section Vll.
You will be advised by separate correspondence
of the results of our deliberations on this
matter.
No response
regarding these apparent violations is required at this time.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be placed in the NRC Public Document Room.
h
',1
E. Fitzpatrick
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
original /s/ J. A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-315, 50-316
Enclosure:
Inspection Report No. 50-315/98005(DRS);
50-316/98005(DRS)
cc w/encl:
John Sampson,
Site Vice
President
A. A. Blind, Vice President
Nuclear Engineering
Douglas Cooper, Plant Manager
Richard Whale, Michigan Public
Service Commission
Michigan Department of
Environmental Quality
Emergency Management
Division, Ml Department
of State Police
~DI jiijtiqn:
Docket File w/encl
PUBLIC IE-01 w/encl
Project Manager, NRR w/encl
Rill Enf. Coordinator w/encl
IEO w/encl (E-mail)
TSS w/encl
DRP w/encl
A. B. Beach w/encl
J. L. Caldwell w/encl
Rill PRR w/encl
DRS (2) w/encl
DOCDESK (E-mail)
GREENS
J. Lieberman, OE
J. Goldberg, OGC
B. Boger, NRR
DOCUMENT NAME: G:ttDRSiDCC98005.DRS
To recehre a co
of thla document, Indicate In the born 'c'
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OFFICE
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DATE
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