ML20150C339
| ML20150C339 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/23/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20150C342 | List: |
| References | |
| NUDOCS 8807120446 | |
| Download: ML20150C339 (2) | |
See also: IR 05000324/1988011
Text
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Jim 2 31988
Docket Nos. 50-325, 50-324
Carolina Power and Light Company
ATTN: Mr. E. E. Utley
Senior Execu^ive Vice President
Power Supply u d Engineering
and Construction
P. O. Box 1551
Raleigh, NC 27602
Gentlemen:
SUBJECT: PRA-BASED OPERATIONAL SAFETY INSPECTION REPORT NOS. 50-325/88-11
AND 50-324/88-11
This refers to the special PRA-Based operational safety inspection conducted by
a team of NRC personnel led by F. Jape on February 29 - March 4,1988, and
March 14-18, 1988, at your Brunswick Steam Electric Plant.
At the conclusion
of the inspection, the findings were discussed with these members of your staff
identified in the enclosed inspection report.
Areas examined during the inspection were selected from the accident sequences
described in the Brunswick PRA.
The inspection focused on the availability of
critical components including implementation of plant procedures and nanagement
programs to assure operability.
In addition, the inspection examined the
ability of the plant staff to utilize procedures and equipment to recover from
certain postulated severe accidents.
While no violations or deviations were
identified, there were a number of inspection find'ngs of some safety
significance.
Some of the more important ones are discussed below. The results
of these examinations are described in the NRC inspection report which is
enclosed with this letter.
CP&L is commended for the self initiated development of the PRA and the actions
taken by the Onsite Nuclear Safety (0NS) group to resulve findings of high
importance to plant reliability.
The inspectors found that many of the
findings selected to inspect had been reviewed, and corrective actions
initiated by ONS and the plant staff.
Station blackout was identified as a dominant contributor to risk in the
Brunswick PRA and was selected as one of the areas for review by the NRC team.
The team found that the decisionmaking program for containment venting was not
clear and that venting would likely be impossible, during a blackout, due to
lack of accessibility to the vent valves because of their location and high
radiation levels.
We believe these issues art significant, and we understand
they will be addressed as part of the resolution of the Mark I problem
currently under review by NRR.
In addition
+ha lack of a clearly stated
program to ensure availability of keys to ' cured dreas when card readers are
disabled was identified.
An interim res.JJIion Was discussed and an agreement
was reached for this issue,
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JUN 2 31988
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Carolina Power and Light Company
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We encourage you to direct attention toward an early resolution of the above
matters.
We appreciate your cooperation with us especially since this effort was
conducted during an outage.
Your staff gave us their undivided attention
throughout the inspection period.
Should you have any questions concerning
.:lis letter, please contact us.
Sincerely,
j Sj
J. Nelson Grace
Regional Administrator
Enclosure:
NRC PRA-Based Operational Safety
Inspection Report
cc w/ encl:
P. W. Howe, Vice President
Brunswick Nuclear Project
C. R. Dietz, Plant General Manager
bec w/ enc 1:
R. Bernhara, RII
C. Casto, RII
P. Fillion, RII
E. Girard, RII
M. Thomas, RII
L. Nicholson, RI!
R. Schin, RII
G. Kelly, NRR
W. Truskoski, NRR
E. Sylvester, NRR
J. Chung, NRR
R. Barrett, NRR
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