ML20101K325
| ML20101K325 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/21/1984 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20101K328 | List: |
| References | |
| NLS-84-512, NUDOCS 8412310302 | |
| Download: ML20101K325 (1) | |
Text
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Cp&L Carolina Power & Light Company SERIAL: NLS-84-512 DEC 311384 w
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST
Dear Mr. Deaton:
In accordance with 10 CFR 50, Appendix J, paragraph V.B.1, and Section 4.6.1.2 of the Brunswick-2 Technical Specifications, the enclosed report entitled
" Reactor Containment Building Integrated Leak Rate Test" is provided for your information. The report presents the results of the primary containment integrated leak rate test performed in September 1984 on Brunswick-2. The results of this test indicate a leakage rate at the upper bound of the 95 percent confidence interval which was below the allowable leakage rate of 0.375 weight percent per day at the 49 psig test pressure, ensuring that the containment will perform its design function in the unlikely event of a major accident.
Brunswick-2 has experienced two consecutive scheauled integrated leak rate test failures, therefore, a Type A integrated leak rate test is required to be performed at each refueling outage or approximately once every 18 months, whichever occurs first. Upon successful completion of two consecutive Type A tests, the routine testing schedule s.hree tests at 40 i 10 month intervals during each 10 year plant inservice inspection period) may be resumed. On September 22, 1984, a Type A tes* was discontinued after identifying a water leak from the residual heat remov;l (RHR) suction and discharge lines to the RHR sump. After isolating the.aak, the test was performed again and successfully completed. Since the leakage was from the RHR system drain valves (which are not primary containment isolation valves), CP&L considers the Type A test successful. Based on this successful test, another consecutive successful integrated leak rate test is necessary before the routine testing schedule can be resumed.
Should you have any questions concerning this matter, please contact Mr. J. S.
Dietrich at (919) 836-6154.
Yours very truly, for S. R. Zi arman Manager Nuclear Licensing Section Enclosure cc:
Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC) h I
I I
t 411 Fayetteville Street
- P. O. Don 1551
- Raleigh. N C. 27602 8412310302 841221 r*DR ADOCK 05000324 P
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