ML20062J851
| ML20062J851 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/06/1980 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-17, NUDOCS 8011120500 | |
| Download: ML20062J851 (2) | |
Text
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PHILADELPHIA ELECTRIC COMPANY Peach Bottom Atomic Power Station Delta, Pennsylvania
.j, Q "-d 17314 Emetentev.6g ps0 Mr. Boyce H.
Grier Office of Inspection sad Enforcement
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Region 1 W -j#!WCI5 United States Nuclear Regulatory Commission
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G31 Park Avenue King of Prassia, PA 19406
..r SU34BCT: _REPORTABLR OCCUKIENCE - PROMPT NQTI_PTCATION
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Ceafirming W. T.
Ulitich's conversation with Mr. Blough on November 6, 1980.
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Reference:
Docket No. 50-277 Peach Bottoa Unit 2 Technical Specification
Reference:
Nome IE Bulletin 80-17 (July 3, 1980)
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Report No. 2-80-27/IP Cecurrence Date:
November 6, 1980 7
Identification of decurr,ence_:_. --
U;:
M During an ineresse of reactor power from a hot standby condition 6,,
cm November 6, m-1980, the No. 3 main steam bypass valve exhibited otratic operation.
Reactor power was reduced until the probles En.-
could be identified.
n-h Conditions Prior to occurrence:
THIS DOCUMENT CONTAINS
- M Unit 2 at hot standby.
g POOR QUALITY PAGES
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Apparent Cause of occurrence:
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ti;:
Investigation of the posi. tion.Sontrolling circuitry associated l M. uith No. 3 bypass valve idedtifled a defective.c.ircuitry board.
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- Q T.his circuitry board.was res,oyed failing th~e bypass valve to a
W closed pe~sition.
Removing the defective component from the
}T cystem re-established a stable pressure control system frer the
. g; reactor via the usin stesa bypass valve system.
Reactor power j tras suh equently increased in preparation for returning the A
t=9 turbine generator to service.
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7.g Auslysis of Occurrence:
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.- V The Peach Sotton Unit 2 has installed nine asia steem bypass valves, h p otal capacity of this system is 25% of rated steam flow.
The
- g: v rimary function of this bypass valve system is to centrol reactor
.ui*
eam pressure when the main turbine generator is not operating.
5 h val of one bypass valve from this systes decreases the main f
eas bypass capability from 25% to spyrexiastely 22%.
This A
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8011 12.0 To O-
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.kg'l f#.
.m
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reduction in bypass espability has minimum safety significanco.
-- The main-steam bypass sytes is not considered safety relatsd-and has no technical specification. associated with it.
Corrective Action:
Operability of the No. 3 bypass valve will be re-established after component repairs are completed.
Frevious Pailures:
Previous failures of this type have occurred but have not been reported since this reporting requirement was only established 4,._
on July 3, 1980, by Bulletin 80-17.
[s Very truly yours, M
t-f W. T.
Ullrich Station Superintendent T
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