ML20215K751
| ML20215K751 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/05/1987 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-05, GL-87-5, NLS-87-091, NLS-87-91, NUDOCS 8705110332 | |
| Download: ML20215K751 (2) | |
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CD&L Carolina Power & Light Company W
5' B8T SERIAL: NLS-87-091 United States Nuclear Regulatory Commission ATTEN ION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & $0-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO GENERIC LETTER 87-05 ASSESSMENT OF LICENSEE MEASURES TO MITIGATE AND/OR IDENTIFY POTENTIAL DEGRADATION OF MARK 1 DRYWELLS Gentlemen:
On March 12,1987, the Staf f issued Generic Letter 87-05," Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells." This letter requested information regarding the Company's intended actions to determine if the Brunswick Plant drywells have degraded due to the corrosion mechanism experienced at the Oyster Creek Nuclear Generating Station. The following provides CP&L's responses to the specific requests.
Request i Provide a discussion of your current program and any future plans for determining if the drain lines that were provided at your facility for removing any leakage that may result from refueling or from spillage of water into the gap between the drywell and the surrounding concrete or from the sand cushion itself are unplugged and functioning as designed.
Response
The primary containment design at the Brunswick Plant consists of a steel-lined, reinforced concrete pressure vessel. The reinforced concrete is in direct contact with the steel liner. As such, there is no mechanism for leakage between the liner and the concrete.
Request 2 Provide a discussion of preventive maintenance and inspection activities that are currently performed or are planned to minimize the possibility of leakage from the refueling cavity past the various seals and gaskets that might be present.
8705110332 070505 PDR ADOCK 05000324 p
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411 Fayetteville street
- P O Don 1551
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'Docum:nt Control Desk NLS-87-091/ Page 2
Response
As noted in the response to Request 1, the design of the Brunswick Plant does not lend itself to leakage between the primary containment liner and the reinforced concrete.
Request 3 Confirm the information listed in Table 1 (of Generic Letter 87-05) is correct with regard to your facility.
Response
The information listed in Table i of Generic Letter 87-05 is correct for Brunswick, Units I and 2.
Please refer any questions regarding this matter to Mr. Stephen D. Floyd at (919) 836-6901.
Yours very truly,
./
titut&
. R.
imn erman
,a er Nuclear Licensing Section MAT /lah (5185M AT) cc:
Dr. J. Nelson Grace (NRC-RII)
Mr. W. H. Ruland (NRC-BNP)
Mr. E. Sylvester (NRC)
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