ML20134M747
| ML20134M747 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/30/1985 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20134M750 | List: |
| References | |
| NLS-85-311, NUDOCS 8509040243 | |
| Download: ML20134M747 (2) | |
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- Cp&L Carolina Power & Light Company SERIAL: NLS-85-311 AUG 3 0 1985 i
l Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing l
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 CONTROL ROOM HABITABILITY
Dear Mr. Vassallo:
On May 29,1985, a meeting was held with members of your staff to discuss control room habitability at Brunswick. As a result of this meeting, Carolina Power & Light Company agreed to recalculate the postulated maximum dose rates which would be experienced by operators in the control room based on the extrapolated flow rates required to achieve 1/8-inch positive pressure in the control room during operation of the Control Room Emergency Ventilation System. Enclosed is the Control Room Radiological Reanalysis performed in accordance with this commitment.
With the exception of unfiltered inleakage, the assumptions and parameters used in this reanalysis are the same as those used in the original habitability study submitted on March 2,1983. A conservative value of 3000 cfm was calculated for the unfiltered inteakage. The value was determined by extrapolating existing pressure versus inleakage data to the inleakage which would correspond to a 1/8-inch positive pressure. Four combinations of recirculated flow and pressurization flow through the charcoal filter were considered in the reanalysis.
Case I represents the existing configuration at Brunswick.
Results of the reanalysis indicate that dose rates at the increased unfiltered inleakage rate of 3000 cfm would not exceed General Design Criteria 19 limits. In addition, a sensitivity study was performed to determine the maximum permissible unfiltered inleakage into the control room by setting the dose -levels at those prescribed by GDC 19. This study showed that the doses from airborne radioactivity in the control room will peak and level off at 2.8 rem thyroid,0.004 rem whole body and 0.06 rem beta skin for unfiltered inleakage of 100,000 cfm or greater.
Based on the Control Room Radiological Reanalysis, Carolina Power & Light Company has determined that the existing Technical Specifications regarding ' control room pressure requirements adequately ensure the safety of plant operators. Therefore, we do not plan to submit a license amendment request regarding this issue.
8509040243 850830 E
PDR ADOCK 05000324 g
i 411 Fayettevelle street
- P. O. Box 1551
- Raleigh, N C. 27602 6
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Mr. D. B. Vassallo NLS-85-311/ Page 2 Please refer any questions regarding this matter to Mr. Stephen D.
Floyd at (919) 836-6901.
Yours very truly, S.
.Z' merman anager Nuclear Licensing Section SRZ/ MAT /mf (1873 MAT)
Enclosure cc:
Mr. W. H. Ruland (NRC-BNP)
Dr. J. Nelson Grace (NRC-RII)
Mr. M. Grotenhuis (NRC) i e
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