ML19263E535
| ML19263E535 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/29/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7906200054 | |
| Download: ML19263E535 (1) | |
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1 NUCl.E AR TEGUL ATORY COMi.11SSION E
ItEGION V
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4 Wi.Liviil Cis E E K. C AI IFORNI A 94 > C I4y 29, 1979 Docket th. 50-344 Portland Ceneral Electric Cohpany 121 S. W. Salinan S tree t Portland, Oregon 97204 Attention:
i.:r. Charles Goodwin, Jr.
Assistant Vice President Gentlwen:
This Informtion ilotice is provided as an early notification of a possibly significant inatter.
It is expected that recipients will review the information for possible applicability to their facilities.
lio specific action or res;]onse is requested at this time.
If further flRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding the isatter, please contact the Director of the appropriate liRC Regional Office.
Sincerely,
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Enclosure:
IE Information liotice fio
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B. Uithers, PGEQ8 240 F. C. Galdos, PGE 7 90620 0 0 sq
UffITED STATES liUCLEAR REGULATORY C0i',MISS10il 0FFICE OF ItiSPECTI0Il AND EriFORCEliEilT WASHIIiGTON, D.C. 20555 May 29, 1979 IE Information flotice flo. 79-13 ItiDICATION OF LOW UATER LEVEL Ill THE OYSTER CREEK REACTOR S_ummary A loss of feedwater transient at the Oyster Creek facility on May 2, 1979, resulted in a significant reduction in water inventory within the reactor core shroud area as measured by one set of water level instruments (triple low level), while the remaining level instruments, sensing from the reactor annulus area indicated water levels above any protective feature setpoint (Fi;ure 1). The water level within the core shroud area was reduced below the " trip M low level" setpoint of 4-fect, 8-inches above the top of the fuel. Subsequent analysis by the licensee has determined that the minimum collapsed water level (solid, without steam voids) over the top of the fuel was 1 to 1-1/2 feet. Coolant sample analyses and offgas release rates indicate that no fuel damage occurred. General Oyster Creek is a non-jet pump BWR with licensed power of 1930 MWt. The plant was first made critical May 3,1969. Status Before Transient Operating at near full power with the main parameters at levels as follows: 1895 l1Wt power level 79" Yarway (13'4" over top of fuel) reactor water level 1020pgigreactorpressure 7.1x10 #/hr feed flow 4 14.8x10 gpm recirculation flow rate (4 pumps) 12 psid coreop Equipment Out of Service (005) "0" recirc pump OOS due to s "B" startup transformer 00S M DUPLICATE DOCUMENT Entire document previously entered into system under: ANO No. of pages:}}