ML20082R950
| ML20082R950 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/1991 |
| From: | Floyd S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NLS-91-002, NLS-91-2, NUDOCS 9109160315 | |
| Download: ML20082R950 (2) | |
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?a Caronna Power & Ught Company SEP 001991 SERIAL: NLS-91-002 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 NUREG-0737 ITEM ll.E.4.2.7 CONTAINMENT ISOLATION Gentlemen:
The purpose of this submittalis to resolve apparent discrepancies between the description of the modifications pertaining to NUREG-0737, item II.E.4.2.7, and the actual installed con *.guration, inspection t..) ort No. 50-325/89-44 and 50-324/89-44, dated February 2, 1990, documents two items whico the NRC Resident inspectors believed were installed differently than described in a December 17,1986 CP&L sul,mittal. The December 17, 1986 submittal described the proposed methods for electrical separation between existing safety-related systems and the norrsafety circuitry of the m:)d;fications to comply with NUREG-0737, item il.E.4.2.7.
In the December 17,1986 subn.atal, CP&L stated that tne fuse used to kolate the existing safety-related Containment Atmospheric Contal isolation trip overcide circuitry from the non-safety circuitry of the NUREG-0737, item II.E.4.2.' modification would be purchased 0-list. Based on the informction available at the time of the NRC inspection, CP&L believed that the installed fuse was actually purchased commerc' drade. Upon further review, CP&L has determined that the installed fuse was pJrchre commercial grade and upgraded for use in a safety-related system by performing an engineering evaluation. The Company will use O-list purchased fuses for this application.
The second item identified involves the relas used for electrical separation between the safety-relatec Reactor Building Exhaust Radiation Monitor circuitry and the non-safety circuitry of the NUREG-0737, Item II.E.4.2.7 modification. The Company's December 17, 1986 submittal stated that the installed re'ay would be a Square-D, Class 8501, Type HO-40 relay rated at 600 volts. As discussed in Inspection Report 89-44, the Resident inspectors identified that irista!!ed relay is in a 120 VAC circuit with a 120 VAC coil. This is not inconsistent with CP&L's commitment. The 600 volt rating is the relay contact ratinq and is an indication of insulating capability of the relay in the 120 VAC application, the 600 volt contact rating provides more than adequate insulating margin.
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Document Control Desk NLS 91-002 / Page 2 i
Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546 6063.
Yours very truly, i:
Stephen D. E oyd Manager i uclear Licensing Section WRM/wrm (2e427.wpf) cc:
Mr. S D. Ebneter Mr. N. B. Le Mr. R. L. Prevatte i
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