ML20116E458
| ML20116E458 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/19/1985 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NLS-85-107, NUDOCS 8504300300 | |
| Download: ML20116E458 (1) | |
Text
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CD&L Carolina Power & t.lght Coinpany SERIAL: NLS-85-107 APR 1 3 1985 Director of Nuclear Reactor Regulation 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 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 EMERGENCY RESPONSE CAPABILITY
Dear Mr. Vassallo:
A conference call was held between Caro. lina Power & Light Company (CP&L) and members of your staff on February 21,1985. The discussions addressed the design of the Safety Parameter Display Systems (SPDS) at Brunswick. Specifically, CP&L was asked if the data validation system and isolation devices were designed in accordance with guidance provided by General Electric (GE) in GESTAR2. As stated during the February 21,1985 conference call, the Company hereby confirms its belief that the data validation system and isolation devices of the Brunswick SPDS are similar in concept to General Electric's GESTAR2 design and exactly the same as the GE basic Emergency Response Facility Isolation System described in Topical Report NEDE 30284P. This system is presently being installed at Perry, Limerick, and River Bend.
Should you have questions concerning this matter, please contact Mr. John S. Dietrich at (919) 836-6154.
Yours very truly, S.
. Z' imerman anager Nuclear Licensing Section MAT /crs (1340 MAT) -
cc:
Mr. L. W. Carner (NRC-BNP)
Dr. 3. Nelson Grace (NRC-Ril)
Mr. M. Grotenhuis (NRC)
.b 85043 850419
/ [, /)
PDR Ig 411 Fayettevdte street
- P. o Box 1551
- Rafeigh. N C. 27602 L.