ML19347E579
| ML19347E579 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/24/1981 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19347E578 | List: |
| References | |
| NO-81-724, NUDOCS 8105130056 | |
| Download: ML19347E579 (3) | |
Text
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Carolina Power & Light Compd
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FILE: NG-3513 (0)
SERIAL: NO-81-724 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.
Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1&2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS
Dear Mr. O'Reilly:
The Brunswick Steam Electric Plant (BSEP) has received IE Inspection Report 50-324/81-06 and 50-325/81-06 and finds that it does not contain any information of a proprietary nature.
The report identified one item that appear (s) to be in noncompli-ance with NRC requirements. This item and Carolina Power Sr Light Company's response is addressed in the following text:
Violation (Severity Level IV)
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Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained. Maintenance Procedure MP-14, Corrective Maintenance, requires that any change to instructions written on the Work Request and Authorization Form involving Q-list equipment, must be approved by Quality Assurance.
Contrary to the above, additional work was performed beyond the scope of the Work Request and Authorization Form No. 1586 submitted on June 20, 1980, without approval by the Shift Foreman or Quality Assurance, in that a component was removed (photohelic unit) from the containment post-accident radiation monitor 1-CAC-AQH-1262, that resulted in the establishment of a small undetected open flow path from the drywell via the open instrument lines to the reactor building.
j During this time period, the containment isolation valves in these 1
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'Mr. James P. O'Railly April 24, 1981 i
lines were operational and would have closed upon receiving a contain-ment iso 14 tion signal. This condition existed in excess of six conths until discovered on February 4, 1981, when the containment isolation valves were closed and tagged out.
Carolina Power & Light Company's Response l
Carolina Power & Light Company acknowledges that the removal of the photohelic unit from containment post-accident radiation monitor 1-CAC-AQH-1262 resulted in noncompliance with technical specifications pertaining to the maintenance of primary containment integrity. As stated, removal of the photohelic unit enabled both one-fourth inch instrument connecting lines to provide a small, direct, unisolated drywell-to-reactor building flow path.
Carolina Power & Light Company den.tes that the photohelic unit was removed for additional work beyond that authorized by Work Request and Authorization Form No. 1586.
The alleged violation was based upon incomplete information provided to the resident inspector at the time of the inquiry.
When it was discovered on February 4, 1981 (LER-1-81-19) that the 1-CAC-AQH-1262 photohelic unit was removed without proper isolation, an investigation of the event was initiated. A records search indicated that Work Request No: 1586 issued on June 20, 1980, contained a description in the Job Details section which sisted, "1262 has a trouble tiaket written on it.
The photohelic was removed for use in 2-CAC-1264 0 H2 ""IU*"
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9 assumed, based upcn inital interpretation of de statement, that the photohelic was removed without proper authorization as provided by Work Authorization No. 1586.
Subsequent to completion of the inquiry by the resident inspector, it was determined that'the photohelic had been previously removed on or about May 27, 1980, as authorized by Work Authorization No. 1370.
This Work Authorization was not provided for review at the time of the investigation.
Carolina Power & Light Company acknowledges that the removal of the photohelic unit as provided by Work Authorization No. 1370 was conducted in noncompliance with technical specifications pertaining i
to the adequacy of written procedures.
Implementation of this Work Authorization did not initiate requisite isolation valve closure to support primary containment integrity.
Appropriate review and training activities will be developed, including a review of the event report, to be conducted with Operations l
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,.Mr. Jame3 P. O'Railly April 24, 1981 and Maintenance personnel responsible for the isolation and maintenance of CAC monitoring systems. This activity will be completed by Jane 15, 1981.
Yours very truly,
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J. Furr Vice President Nuclear Operations SPC:ejj*
B. J. Furr, having been first duly sworn, did depose and say that the information contained hernin is true and correct to his own personal knowledge or based upon information and belief.
My conunission expires:
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