ML20100N557
| ML20100N557 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/10/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-11, NLS-84-485, NUDOCS 8412130223 | |
| Download: ML20100N557 (2) | |
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Cp&L Carolina Power & Light Company SERIAL: NLS-84-485 Mr. Darrell G. Eisenhut, Director Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SUPPLEMENTAL RESPONSE TO GENERIC LETTER 84-11 INSPECTIONS TO BWR STAINLESS STEEL PIPE
Dear Mr. Eisenhut:
By letters dated June 1, 1984 and October 9, 1984, Carolina Power & Light Company (CP&L) responded to NRC Generic Letter 84-11 by providing our plans for performing inspections for intergranular stress corrosion cracking (IGSCC) on Brunswick Units 1 and 2.
In these letters, CP&L committed to perform a visual examination for leakage during each plant outage in which the containment is de-inerted.
At the time this commitment was made, the Company did not foresee the possible need to shutdown a unit and de-inert the containment (and, therefore, perform a visual inspection for leakage) after having just performed such an inspection. Therefore, CP&L wishes to modify its commitment with respect to the frequency for performing these visual inspections. A visual exanination for leakage of the reactor coolant piping will be performed during each plant outage in which the containment is de-inerted unless such an inspection has been performed during the previoua 92 days. The examination will be performed consistent with the requirements of IWA-5241 and IWA-5242 of the 1980 Edition of Section XI of the ASME Boiler and Pressure vessel Code. The system boundary subject to this examination will contain the susceptible welds inside the primary containment.
Crack growth that could occur during a 92-day interval would be small when compared to the margin between the point at which detectable leakage will occur and the poirt of net section collapse.
In addition, performing these visual inspections on the revised frequency will enable the plant to avoid unnecessary personnel exposures. Personnel exposures for each visual inspection exceed 1 man-rem and are divided equally between gamma and neutron exposure. The neutron exposure is of particular concern when these inspections are performed very shortly after unit shutdown.
Carolina Power & Light Company believes that the insignificant safety benefit obtained by performing visual examinations when outages are less than 92 days apart does not justify.he additional radiation exposure and costs incurred as a result of these inspections.
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[Should you have any question concerning this. matter, please contact Mr. Sherwood R. Zimmerman at. (919) 836-6242.-
Yours'very truly r
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b dent' A. B Cutter - ice Nuclear Engineering & Licensing MAT /pgp (876 MAT) cc:
.Mr. D. O. Myers (NRC-BNP).
Mr. J. P. O'Reilly.(NRC-RII)
Mr. M. Grotenhuis (NRC) 4