ML19341A308
| ML19341A308 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/15/1981 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM NUDOCS 8101220571 | |
| Download: ML19341A308 (2) | |
Text
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im, January 15, 1981 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing g
Washington, DC 20555 l
Reference:
Beaver Valley Power Station, unit No. 1 Docket No. 50-334 Integrity of Systems Outside Containment - NUREG-0737 III.D.1.1 Gentlemen:
In accordance with your October 9, 1980 and subsequent discussions with Mr. W. Ross of your staff, we are submitting the results of the tests performed as part of Duquesne Light Company's program to reduce leakage from systems outside containment that would or could contain highly radio-active fluids during a transient or accident (NUREG-0737, Item III.D.l.1 and NUREG-0578, Item 2.1.6a).
Safety Iniection System Recirculation Mode The initial pressurization of the piping in the Low and High Head Safety Injection System that would be operational in the recirculation mode of operation yielded leakage rates at the following valves in the system:
3 drops /10 see CH-158 - 1A Charging Pume to Fill Header Isolation CH-159 - 1B Charging Pump to Fill Header Isolation N 3 drops /10 see MOV-SI-869B - High Head SI to R)( Coolant Hot Leg N 5 drops /30 min MOV-CH-308B - Containment Isolation for RCP 1B Seal Line N 20 ml/ min 0/
.5 SI-353 - Boron Injection Tank Vent N 5 ml/ min i D Maintenance performed packing adjustments on these valves and the system was repressurized and no external leakage was found.
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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Integrity of Systems Outside Containment - NUREG-0737 III.D.l.1 Page 2 Containment Depressurization System Recirculation Mode The piping associated with the recirculation mode for the Outside Recirculation Spray Pumps was pressurized in conjunction with surveillance testing of the pumps. No external leakage was noted during the test.
Post DP) Hydrogen Control System The Post DBA Hydrogen Control System was divided into Train A and Train B subsystems. Each subsystem was placed in a lineup to allow pressurization of all piping and components outside of the containment structure that would be in operation during a post accident condition.
Initially Train A could not be pressurized due to high leakage. Maintenance was performed on the seals on the blower outlet, [MOV-HY-103A], [MOV-HY-101A]
and [HY-121] and the system was retested. The major source of leakage was found to be past the seat of Purge Blower Discharge Isolation Valve [KY-121].
Valve HY-121 was checked for external leakage by pressurizing the system with Freon and using a detector to check for external leakage. No external leakage was found. The test was revised to open [HY-121], which was a boundary valve for the test, and close the Purge Blower Inlet Isolation Valve [MOV-HY-101A] which is normal lineup for operation of the Hydrogen Recombiners. Train A was retested and found to have a leak rate of 1.21 SCF/D. Train B was pressurized and found to have a leak rate of 0.91 SCF/D.
If you have any questions, please contact my office.
Very truly yours,
'[
C. N. Dunn Vice President, Operations cc:
Mr. D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555
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