ML20035H263
| ML20035H263 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/29/1993 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-93-115, TAC-M85064, TAC-M85065, TAC-M85127, NUDOCS 9305040035 | |
| Download: ML20035H263 (2) | |
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Cf8&L Carolina Power & Light Company (APR 29 23 SERIAL: NLS-93-115 10 CFR 50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO NRC REQUEST FOR CONFIRMATION OF MONITORING SRV DISCHARGE PlPING FOR LEAKAGE (TAC NOS. M85064, M8506S AND M86127)
Gentlemen:
l The purpose of this letter is to provide the NRC staff the written confirmation requested in a NRC l
Safety Evaluation, dated February 24,1993, granting Brunswick Steam Electric Plant, Unit Nos.1 l
and 2, relief from certain Inservice inspection Program requirements.
The NRC Safety Evaluation, Section 2.1.6, states: "The NRC Staff requests written confirmation that the licensees' alternative program has provisions for monitoring the discharge pipe in the i
suppression pool air space for leakage during the periodic test or normal operation." The written confirmation request is the result of information provided by CP&L to the NRC staff during a January 13,1993 conference call.
l During each restart from a refueling outage, Brunswick Plant personnel perform Periodic Test (PT)-11.1.2, " Automatic Depressurization Systtm (ADS) and Safety Relief Valve (SRV) Operability Test," at which time each of the SRVs is cycled at approximately 250 pounds of reactor pressure.
As PT-11.1.2 is being performed, instrumentation is monitored to detect increases in pressure and temperature in the suppression pool and corresponding air space, using a primary containment pressure recorder and indicator and suppression pool pressure indicators. Increases in pressure or temperature observed during the performance of the PT result in the initiation of an investigation into the cause of the increase. During plant operation, the pressurization of this line is limited to plant transients for whien use ol the ADS is necessary (i.e., Reactor SCRAMS). The suppression pool air space temperature and pressure instrumentation are monitored to ensure the blowdown is quenched as a part of the guidance in the Emerger.cy Operating Procedure (EOP) response for these events.
The above referenced instrumentation and procedural guidance provides adequate indication of a pressure boundary failure due to degradation in a SRV discharge pipe during testing and normal plant operation.
a 030045 A
v4 L 411 Fayetteydie Street
- P O. Box 1551
- Ratep hl C-27602 l
I 9305040035 930429 PDR ADDCK 05000324 t
I P
o NRC Document Control Desk 1
NLS 93-115 / Page 2 Please refer any questions regarding this submittal to Mr. D. B. Waters at (919) 546-3678.
Yours very truly, 8
D. C. McCarthy Manager Nuclear Licensing Section SHC/she (NLS93115.vrpf)
A cc:
Mr. S. D. Ebneter Mr. P. D. Milano i
Mr. R. L. Prevatte L
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