ML20006E982
| ML20006E982 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/15/1990 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-90-033, NLS-90-33, NUDOCS 9002270032 | |
| Download: ML20006E982 (2) | |
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CD&L Carolina Power & Ught Company FEB 151990 SERIAL:
NLS-90 033 10CFR50.90 84TSB08 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSk'ICK ' STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2
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DCCKET NOS. $0 325 6 50 324/ LICENSE NOS. DPR 716 DPR-62 PRIMARY CONTAINMENT ISOLATION SYSTEM l.,
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Centlemen:
L On October 12, 1989, during the monthly status meeting with the Brunswick Project Manager, CP&L was provided seven questions pertaining to the September 20, 1989 license amendment request regarding the Primary Containment l_
. Isolation System. On December 5, 1989, CP&L responded to six of the seven questions. contains the Company's responses to the remaining question regarding RWCU Isolation Delta Flow High.
Please refer any questions regarding this submittal to Mr. M. R, oates at (919) 546-6063.
Yours very truly,
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Leonard I. Loflin Manager L
Nuclear Licensing Section l
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-LIL/ MAT En losure cc:
Mr. D. H. Brown Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny 9002270032 900215 l
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ll ENCLOSURE 1 TO NLS 90 033 PRIMARY CONTAINMEN*r ISOLATION SYSTEM RESPONSE TO REQUEST POR ADDITIONAL INFORMATION Ouestion Proposed Change Number 4 RWCU Isolation Delta Flow High:
Please confirm-
. that the isolation time for RWCU under high differential flow conditions is bounded by the high energy line break accident analysis.
Please address the DJ following times:
instrument response. time and value; AC/DC valve closure time and value; diesel generator start time and value; time delay timer time and val.ue;.londing requence delay Line and value; and total RWCU isolation time and value,
- 'i Etnaants The total time from initiation of a hsgh ds ffarential flow signal t, closure of the appropriate isolation valves is approximat61y 93 seconds, lhis includes approximately 3 sotonde for inrtrument respoose time 10 seconds for s
emergency diesel generator start t.me, the 45 second tin.e delay, cr.d 35 t
seconds for valve closure.
'An RWCU line break, assuming an isolation time of 93 seconds, has been reviewed against the high energy line break (HSLB) analysis to decermine the affects on the environment inside the reactor buildings, It has been determined that the RWCU line break As bounded by the existing generic IIELB profiles.used to qualify Brunswick equipment.
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