ML20212P033
| ML20212P033 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/26/1986 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NLS-86-256, NUDOCS 8609020146 | |
| Download: ML20212P033 (2) | |
Text
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b CD&L Carolina Power & U ompany SERIAL: NLS-86-256 AUG 26 Director of Nuclear Reactor Regulation Attention:
Mr. Dan Muller, Director BWR Project Directorate #2 Division of BWR Licensing United States Nuclear Regulatory Commission Washington, DC 20,555 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 ON HIGH RADIATION
Dear Sir:
On December 16,1983, Carolina Power & Light Company committed to provide drywell vent and purge valve isolation on primary containment high radiation signals in accordance with NUREG-0737, Item II.E.4.2.(7). This letter provides a description of the modifications to be performed at Brunswick and a schedule for completion.
The Company plans to modify the logic for the containment vent and purge valves so that a high radiation signal from the main stack monitor will cause their isolation on both units. The main stack monitor is in the release pathway and is capable of monitoring radioactive releases from primary containment. A manual override capability will be provided in order to allow the unaffected unit's vent and purge valves to be returned to their normal operating status once the cause of the isolation is determined. This override capability will also be used in the event of monitor malfunction. Administrative controls will be established to govern the use of the manual override.
The proposed logic design is based upon NRC guidance. The high radiation isolation signal source and associated portions of the logic are considered nonsafety related. The monitor's setpoint will be determined such that potential radiation releases will be limited to a small fraction of 10 CFR 100 limits without affecting operation of the plant. Since this isolation capability has no essential function for a design basis accident, no change in the Technical Specifications beyond the existing operability requirements for the main stack radiation monitor are necessary.
The proposed modifications are scheduled to be performed during Reload 5 for Brunswick-1 (scheduled to begin January 1987) and Reload 7 for Brunswick-2 (scheduled to begin January 1988) based upon the current design. Approval of the proposed design is requested by September 1986 in order to support the proposed installation schedule.
Carolina Power & Light Company has reviewed this request in accordance with the provisions of 10 CFR 170.12 and determined that an application fee is required. A check for $150 is enclosed in payment of this fee.
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Director of Nuctrar Reactor Regulation 4
NLS-86-256 / Page 2 Please refer any questions regarding this matter to Mr. Sherwood R. Zimmerman at (919) 836-6242.
Yours,ery trulp
(,lC A. B. Cutter - Vice President Nuclear Engineering & Licensing ABC/ MAT /pgp (4006 MAT)
Enclosure
, cc:
Mr. W. H. Ruland (NRC-BNP)
Dr. J. Nelson Grace (NRC-RII)
Mr. E. Sylvester (NRC) i o
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