ML20080G410
| ML20080G410 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/14/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 LAP-83-406, NUDOCS 8309200262 | |
| Download: ML20080G410 (1) | |
Text
.
Cp&L SERIAL: LAP-83-406 Carolina Power & Light Company e
SEP 141983 Director of Nuclear Reactor Regulation j
Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 CRD RETURN LINE N0ZZLES CRACKING (NUREG-0619)
Dear Mr. Vassallo:
In our letter of February 24,1983, (Serial No. LAP-83-34), Carolina Power & Light Company committed in item 2 to perform NUREG-0619 required testing. Carolina Power & Light Company finds that it cannot complete the return flow to vessel testing (NUREG-0619, item 7.3) at this time on Unit No.
I due to the absence of sufficient decay heat to maintain the vessel pressurized following a scram.
Previous data taken prior to the current outage shows that the required flow can be obtained with one pump on Unit No.
1 (return line isolated but not cut and capped) and on Unit No. 2 (return line cut and capped). Carolina Power & Light Company will perform the required 4
postmodification testing during a future planned outage during the current operating cycle where decay heat is sufficient to maintain vessel pressure near normal operating valves.
Should you have any questions regarding this issue, please contact our staff.
Yours very tr U.
l<>.
n P. W. Howe Vice President Brunswick Nuclear Project JSD/tda (7792JSD) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. S. D. MacKay (NRC)
@l 8309200262 830914 PDR ADOCK 05000324 P
PDR 411 Fayetteville Street
- P. O. Box 1551
- Raleigh N. C. 27602
,. -.. _,