ML19341B796
| ML19341B796 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Trojan |
| Issue date: | 02/23/1981 |
| From: | Werling J DUQUESNE LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| BVPS:JAW:1111, RO-81-014-01P, RO-81-14-1P, NUDOCS 8102270609 | |
| Download: ML19341B796 (2) | |
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DUQUESNE LLCHT COMPANY Beaver Valley Pcwer Station Post Office Box 4 Shippingport, PA 15077 Feb rua ry 23, 1981 BVPS: JAW:1111 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, Licence No. DPR-66 LER 81-014/OlP Mr. B. H. Crier, Director of Regulation United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
In accordance with Appendix A, Beaver Valley Technical Specifications, Licensee Event Report LER 81-014/01P, Technical Specification 6.9.1.8.c, Pressure Boundry Weld Crack, is submitted. This occurrence was reported to the Beaver Valley NRC Resident Inspector Mr. J. D. Hegner at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> and on the Hotline phone at 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br /> on February 22, 1981.
At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on Saturday, February 21, 1981, while making preparations for plant startup, instrument technicians reported a leak at a reactor coolant system (RCS) valve. The reactor coolant system pressure was 2235 psig and temperature was 547* F.
The leak was traced to the v.icinity of RC-ll, which is the root stop for PT-RC-403 (RCS wide. range pressure transmitter] and MOV-RH-700 (Residual Heat Removal System inlet.) At this point it was felt that it was a body to bonnet leak on one of these *wo valves, but couldn't be confir=ed due to the mirror insulation surrounding the piping and valves, m
On the afternoon Plans were started to provide a method of scaling the valve.
RCS shift the RCS leakage inventory was calculated to be less than 0.5 gpm.
leakage was calculated on the midnight shif t on February 22,1961 to be 2.7 spo. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on February 22, 1981, a cooldown to mode 5 was commenced due to the increased leakage. While the cooldown was in progress the mirror
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e Mr. B. H. Crier Feb ruary 23, 1981 BVPS: JAW:1111 Page 2 insulation was being removed for a complete view of the leak. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> the leak rate'was up to 10gpm. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on February 22, 1981 workmen entered the containment building and were able to identify positively a weld leak where the RC-ll nipple penetrates the RCS boundry.
At the present time discussions are proceeding with Westinghouse and Duquesne Light Company Engineering Department to determine an action plan to be followed. The plant is in mode 5 and is being drained to mid span in the RCS loops to allow the cracked weld to be repaired. A complete followup report will be submitted and the resident inspector wi11 be kept up to date on the progress of the job.
Very truly yours,
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J. A. Werling Superintendent ec: Director Of Management & Program Analysis United States Nuclear Regulatory Commission Washington, D. C.
20555 D. A. Chaney, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, D. C.
20555 D. A. Eeckman, Nuclear Regulatory Commission, BVPS Site Inspector Nuclear Safety Analysis Center, Palo Alto, California Mr. John Alford,' PA Public Utilities Commission, Harrisburg, PA e
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