ML20203F225
| ML20203F225 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/08/1997 |
| From: | Anderson C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| Shared Package | |
| ML20203F229 | List: |
| References | |
| 50-352-97-08, 50-352-97-8, 50-353-97-08, 50-353-97-8, NUDOCS 9712170313 | |
| Download: ML20203F225 (3) | |
See also: IR 05000352/1997008
Text
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December 8,1997
Mr. D. M. Smith, President
PECO Nuclear
Nuclear Group Headquarters
Correspondence Control Desk
P. O. Box 195
Wayne, PA 19087-0195
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-352/97 08, 50-353/97-08
Dear Mr. Smith:
This refers to the inspection conducted on September 16,1997, through November 17,
1997, at your Limerick Units 1 and 2 reactor facilities. The enclosed report presents the
results of this inspection.
During the nine week inspection period covered by this report, the conduct of activities at
Limerick Units 1 and 2 was generally characterized by safe and conservative operations
and decision making. Your operators' response was excellent to an unexpected control rod
drif t. On-line hydraulic control unit maintenance was completed without error or challenge
to safe plant operations. Activities in the Technical Support Center following a fire that
occurred in one of the eight site emergency diesel generators were performed well with
conservative decisions and thorough verifications made.
However, the NRC raised concerns regarding PECO Energy's initial assessments following
the failure of a control rod to scram at Unit 2.
PECO did not perform a prompt and
comprehensive assessment of generic and common mode concerns associated with aging
BUNA-N diaphragms, and did not initially verify whether an unanalyzed condition existed.
A number of conference calls occurred between your staff and NRC management resulting
in further testing and analysis.
There were a number of instances where your staff did not correctly implement procedures
and processes. For example, during previous configuration changes made to the residual
heat removal service water radiation monitoring system, engineering reviews of the system
configuration and drawings were inadequate to ensure that the emergency service water
system was properly monitored. Another example involved severalindividuals that failed
to properly annotate the reasons for not performing fire damper functional tests consistent
with the procedural requirements. Although these and other exainples were minor issues,
the NRC is concerned with the number of issues that occurred. Management attention is
warranted to ensure that a wider procedural compliance problem does not exist.
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Mr. D. M. Smith
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in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
its enclosure (s), and your response will be placed in the NRC Public Document Room
(PDR),
Sincerely,
Original Signed By:
Clifford J. Anderson, Chief
Project Branch No. 4
Division of Reactor Projects
Docket Nos.: 50 352, 50-353
License Nos: NPF-39, NPF 85
Enclosures:
NRC inspection Report 50-352/97-08,50-353/97-08
cc w/ encl:
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director - Licensing
W. MacFarland, Vice President - Limerick Generating Station
J. L. Kantner, Manager, Experience Assessment
Secretary, Nuclear Committee of the Board
Commonwealth of Pennsylvania
i
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Mr. D. M. Smith
3
Distribution w/ encl:
Region i Docket Room (with concurrences)
H. Miller, RA/W. Axelson, DRA (Irs)
P. Swetland, DRP
A. Linde, DRP
NRC Resident inspector
Nuclear Safety Information Center (NSIC)
PUBLIC
Distribution w/ encl: (Via E Mail)
W. Dean, OEDO
B. Buckley, NRR
J. Stolz, PDI 2, NRH
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
F. Talbot, NRR
DOCDESK
DOCUMENT NAME: G:\\ BRANCH 4\\ LIM 9708. INS
To receive a copy of thle document, Indicate in the boa:
- C* = Copy without attachment! enclosure
- [* = Copy with attachment / enclosure
- N* = No copy
0FFICE
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NAME
ABurritt r14
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DATE
12/05/97
12/ 3 /97
12/
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12/
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12/
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0FFICIAL RECORD COPY
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