ML20072G415
| ML20072G415 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/24/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820, RTR-NUREG-0313, RTR-NUREG-313 IEB-83-02, IEB-83-2, LAP-83-281, NUDOCS 8306280489 | |
| Download: ML20072G415 (2) | |
Text
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SERIAL: LAP-83-281 Carolina Power & Light Company JUN 241983 Director of Nuclear Reactor Regulation At tention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commissioa Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCY.ET NO. 50-325 LICENSE NO. DPR-71 IE BULLETIN 83-02 RCS LEAK DETECTION 1
i
Dear Mr. Vassallo:
As requested during several conversations with members of your staff, Carolina Power & Light Company (CP&L) agreed to prepare and submit a letter committing to conduct certain actions relative to IE Bulletin 82-03 (dated March 4,1983) prior to startup of Brunswick Steam Electric Plant Unit No. 1 (BSEP-1). Accordingly, CP&L commits to implement additional monitoring and more restrictive limits on unidentified leakage consistent with NUREG-0313, Revision 1, ar listed below:
(1) Reactor Coolant System leakage shall be demonstrated to be within the limits of Technical Specification 3.4.3.2 and item (2) below by monitoring the drywell drain sunp flow rates at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(2)
Increases in unidentified leakage shall not exceed a 2 gallon per minute increase within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period following the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the reactor is in operational condition one (1).
i (3) Technical Specification 3.4.3.1 requires the primary containment atmospheric particulate radioactivity monitoring system to be l
operable in operational conditions 1, 2, or 3.
With the primary containment atmospheric particulate radioactivity monitoring system inoperable, grab samples of the containment atmosphere shall be obtained and analyzed at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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o Mr. D. B. Vassallo In addition, CP&L connaits to submit our plans for inspection and/or modification of the recirculation and other reactor coolant pressure boundary piping systems for the next refueling outage of BSEP-1.
These plans will be submitted to the NRC for review at least three (3) months prior to the start of the next scheduled r afueling outage.
Should you have any questions regarding this issue, please do not hesitate to call our staff.
Very truly yourc, U.
G.
m P. W. Howe Vice President Brunswick Nuclear Project JSD/tda (7222JSD) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Roilly (NRC-RII)
Mr. S. D. MacKay (NRC)
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