ML20150C339

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Forwards PRA-Based Operational Safety Insp Repts 50-324/88-11 & 50-325/88-11 on 880229-0304 & 0314-18.Lack of Clearly Stated Program to Ensure Availability of Keys to Secured Areas When Card Readers Disabled Identified
ML20150C339
Person / Time
Site: Brunswick  Duke Energy icon.png
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

License Nos. DPR-71, DPR-62

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

,

Carolina Power and Light Company 2

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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