ML19345G090
| ML19345G090 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 02/10/1977 |
| From: | Crane P PACIFIC GAS & ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 8103020183 | |
| Download: ML19345G090 (2) | |
Text
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[Rifdatory Docket File
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PACIFIC G-AS AND E LE C T RI C C O M PANY BONS l
77 BE ALE S T R EET. S A N F R A NCISCO. C ALIFO R NI A 94106 * (415) 731 4211
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Mr. R. H. Engelken, Director 9
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Dear Mr. Engelken:
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Our letter of January 27, 1977 transmit a Licensee Event Report for our Humboldt Bay Power Plant Unit No. 3 (LER77-01).
This Licensee Event Report concerns the discovery, during the course of the seismic design review of the Unit, of a lower flow capability of the reactor vent valves than that given in the Technical Specifications.
Larger valves are on order and will be installed during the course of the current refueling and modification outage.
A concern was raised by Mr. Jesse Crews of your staff that this occurrence could be generic in nature.
As discussed with Mr.
Crews, the circumstances involved in procuring these valves in 1965 were such that we believe that this was a unique occurrence.
Our investigation shows that a properly prepared procurement specification containing all requirements for the valves, including flow capability requirements, was originally prepared.
We subsequently learned that the vendor upon whom this order was placed could not meet our quality or delivery time requirements, which were based on a NRC licensing com-mitment for installation of the valves.
A vendor with suitable valve body castings who could meet our requirements was located and a revised procurement specification was prepared.
All pertinent procurement infor-l mation (size, pressure rating, model number, etc.) was incluc%d on this I
specification with the exception of valve flow capability.
Neither the l
specifying engineer nor the vendor can account for the fact that flow capability was not specified.
In order ".o resolve this concern, the Company's Quality As-surance Department vill conduct an audit, the scope of which will include the Company's engine 3 ring procurement specifications involved with new 1
P00R ORIGINAL. =
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Mr. R. H. Engelken 2
February 10, 1977 safety related components (not replacement components).
This audit will be limited to ccmponents the performance of which has not been directly verified through preoperational testing or routine surveillance testing.
The audit will cover the period between initial commercial operation of the Unit in August 1963 and the implenentation of the Company's Quality Assurance Manual for Operating Nuclear Power Plants on April 1, 1976.
This audit will be completed prior to the time the Unit is returned to service following the present refueling and modifi:ation outage.
Any significant deficiencies found as a result of thir audit will be reported as Licensee Event Reports.
Additional Emergency Core Cooling System (ECCS) analyses under the Commission's Final Acceptance Criteria are planned in response to questions raised by the NRC Division of Operating Reactors in their review of our submittal on this subject.
These analyses will include a parametric study of the effect of vent valre flow capability on ECCS performance.
Previous analyses have indicated that ECCS performance is not affected by vent valve flow for most hypothetical break sizes and locations.
Very truly yours,
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Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l
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