ML20202H227
| ML20202H227 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 03/26/1986 |
| From: | Olson P WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-86, REF-PT21-86-119-000 D-N-#62, GO3-86-183, PT21-86-119, PT21-86-119-000, NUDOCS 8604150162 | |
| Download: ML20202H227 (3) | |
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J-Washington Public Power Supply System Box 1223 Elma, Washington 98541 1223 (206)482-4428 b
March 26, 1986 h
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'S-Docket No. 50-508 U. S. Nuclear Regulatory Commission, Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 260 Walnut Creek, California 94596-5368 Attentian:
Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
Subject:
NUCLEAR PROJECT NO. 3 POTENTIAL 10CFR50.55(e) DEFICIENCY EMERGENCY DIESEL GENERATOR -
POTENTIAL OVERSPEED TRIP, D/N #62 On February 24, 1986, the Supply System notified your office of a potential 10CFR50.55(e) deficiency concerning the subject condition.
A subsequent Engineering evaluation has determined' that: if the deficiency had remained uncorrected, it could have adversely affected the safe operation of the plant.
Therefore, the subject condition is reportable in accordar.ce with the provisions of 10CFR50.55(e).
8604150162 860326 PDR ADOCK 05000008 S
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U. S. Nuclear Regulatory Commission, Region V G03-86-183 Attention: Mr. D. F. Kirsch, Acting Director March 26, 1986 Page Two Attached is the Supply System approved final report.
The report provides a 1
description of the deficiency, analysis of the safety implications and corrective actions taken/ planned.
Should you have any questions or desire further information, please contact me directly.
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Program Director, WNP-3 AGC/cae Attachment cc:
Mr. J. A. Adams, NESCO Mr. R. M. Boucher, Pacific Power & Light Co.
Mr. W. L. Bryan, Washington Water Power Co.
Mr. J. Crnich, Ebasco - Elma Ebasco, Elma Mr. W. J. Finnegan, Puget Sound Power & Light Co.
Mr. J. R. Lewis, BPA Mr. N. S. Reynolds, Bishop, Liberman, Cook, Purcell & Reynolds Mr. D. Smithpeter, BPA Mr. B. D. Withers, Portland General Electric Co.
Document Control Desk - U. S. NRC i
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WASHINGTON NUCLEAR PROJECT 3 (Docket No. 50-508)
POTENTIAL 10CFR50.55(e) DEFICIENCY FINAL REPORT EMERGENCY DIESEL GENERATOR - POTENTIAL OVERSPEED TRIP (D/N #62) t A.
Description of Deficiency:
l WNP-3 has two (2) Colt PC-2 series Emergency Diesel Generators furnished l
by Colt Industries-Fairbanks Morse Engine Division (P.O. No. 3240-053).
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Colt Industries has filed 10CFR Part 21 Report with the Nuclear Regulatory Commission and advised Washington Public Power Supply System of the potential deficiency and its resolution.
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The deficiency as identified on a similar unit installed at Seabrook l
Nuclear Plant (Unit 1B), resulted in an overspeed trip upon startup.
It was caused by a delay in venting of starting air from the rack boost cylinder after the start signal.had been terminated, causing the boost to fight the governor, creating an overspeed trip situation.
B.
Analysis of the Safety Implications:
The deficiency results in potential overspeed tripping of the Emergency Diesel Generator, which could result in the loss of the standby AC power source, required to service the safety related loads in the event of the l
t loss of the normal supply.
All loads required to achieve the safe shutdown of the plant and/or to mitigate the consequen::es of a design basis accident receive standby power from this system.
This deviation is considered "significant".
If left uncorrected, it could have adversely affected the safety of operations of the plant and hence is reportable under the provisions of 10CFR50.55(e).
C.
Corrective Actions:
1.
The Vendor (Colt Industries) has forwarded proposed modifications of the system whereby the air from the rack boost cylinder and its l
associated shuttle valves will be positively vented, after the engine is started.
2.
This deficiency has been documented on a Nonconformance Report and will be corrected upon resumption of construction.
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