ML19345G118
| ML19345G118 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 07/25/1974 |
| From: | Searls F PACIFIC GAS & ELECTRIC CO. |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| 7918, NUDOCS 8103020494 | |
| Download: ML19345G118 (2) | |
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July 25, 1974
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t U Mr. Karl R.
Goller
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Ab Assistant Director for I:
Operating Reactors d O!. Q g ' I' '3' Directorate of Licensing
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A L %7 Office of Regulation U. S. Atomic Energy Commission D diQc) b'p'g.y jh Washington, D.
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20545 Re:
Docket No. 50-133 License No. LPR-7
Dear Mr. Goller:
Pursuant to Section IX.H.2.b. (2) of Appendix A to the Humboldt Bay Unit No. 3 Facility Operating License, we are hereby notifying you of a malfunction of the reactor cleanup pump.
The cleanup pump was removed from service at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br /> on June 26, 1974 because of excessive leakage through the mechanical seal on the pump shaft.
At the time the pump was removed from service, the seal leakage rate could not be handled by the leakoff system resulting in a steam discharge to the pump area and the reactor equipment drain tank.
This resulted in a short term airborne radioactivity condition that was properly handled by the plant ventilation system.
This condition did not involve any personnel overexposure and has been documented in our files.
The loss of the cleanup pump does not render the cleanup system inoperable.
As in previous cases when the cleanup pump was out of service due to excessive seal leakage, the demineralizer effluent was valved to the condenser hotwell instead of the reactor, utilizing the pressure diffdrfntial between the reactor and the hotwell to operate the. system.
79J~3 P00R ORIGINAL.
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Mr. Karl R. Goller Page 2 July 25, 1974 Thus water quality will be maintained within license limits during normal operation.
The control rod hydraulic pumps (one of which is on the emergency power bus) may also be used to operate the cleanup system as a backup to the core spray. system during post-incident decay heat removal opera-tions.
Nevertheless, the loss of the cleanup pump does constitute a variance from the performance specifications contained in the Technical Specifications, specifically Section III.A.3.D.(2) and IV.A.4.
Accordingly, we consider-the loss of the pump to be an unusual event as described in Section IX.H. 2.b. (2).
A modification to the seal system, that involves bringing clean water from the hydraulic system header, has been proposed by the pump manufacturer.
This modification has been reviewed and approved by the On-Site Review Committee.
It is expected that the materials for the modification and necessary seal parts should be available by September 1, 1974, and that the pump will be repaired, modified, and returned to service by October 1.
Very truly yours, K1.Aw F.
T.
SEARLS cc:
Mr.
R.
H. Engelken Director Directorate of Regulatory Operations Region V U.
S. Atomic Energy Commission P. O.
Box 1515 Berkeley, California 94701
.