ML19246C054
| ML19246C054 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/31/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| NUDOCS 7907200103 | |
| Download: ML19246C054 (1) | |
Text
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TQ 4'o, UNITED STATES 8 'f 3 s, c ' j NUCLEAR REGULATODV COMMISSION
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KING OF PRUSSIA, PENNSYLVANI A 19406 May 31, 1979 Docket No. 50-219 Jersey Central Power and Light Company ATTN:
Mr. Ivan R. Finfecck, Jr.
Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Gentlemen:
The enclosed Bulletin 79-12 is forwarded to you for action.
A written responso is required.
If you desire additional information regarding this matter, nlease contact this office.
Sincerely,
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Boyce H. Grier Director Encloss es:
1.
List of IE P'11etins Issued in Last Twelve Months cc w/encls:
J. T. Carroll, Staticn Superintendent A. Z. Roisman, Natural Resources Defense Council 79072001o63 y j;dD4
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-12 Date: May 31,1979 Page 1 of 3 SHORT PERIOD SCRAMS AT BWR FACILITIES Summary.
Reactor scrams, resulting from periods of less than 5 seconds, have occurred recently at three BWR facilities.
In each case the scram was caused by high flux detected by the IRM neutron monitors during an approach to critical. These events are similar in most respects to events which were previously described by IE Circular 77-07 (copy enclosed).
The recent recurrences of this event indicate an apparent loss of effectiveness of the earlier Circular. Issuance of this Bulletin is considered appropria+' to further reduce the number of challenges to the reactor protective system hig. IRM flux scram.
Description of Circumstances:
The folicwing is a brief account of each event.
1.
Oyster Creek - On December 14, 1978, the reactor exper enced a scram as control rods were being withdrawn for approach to critical, following a scram from full power which had occurred about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> earlier.
The moderator temperature was 380 degrees F and the reactor pressure was 190 psig.
Because of the high xenon concentration the operators had not made an accurate estimate of the critical rod pattern.
The operator at the controls was using the SRM count rate, which had changed only slightly, (425 to 450 cps) to guide the approach.
Control rod 10-43 (first in Group 9) was being withdrawn in " notch override" to notch position
.J, when the reactor became critical on an estimated 2.8 second period.
The operator was attempting to reinsert the rod when the scram occurred.
Failure of the
" emergency rod in" switch to maintain contact, due to a bent switch stop, apparently contributed to the problem.
2.
Browns Ferry Unit 1 - On January 18, 1979, the reactor experienced a scram during the initial approach to critical following refueling.
The operator was continuously withdrawing in " notch override" the first control rod in Group 3 (a high worth rod) because the SRM count rate had led him to believe that the reactor was very subcritical.
A short reactor period, estimated at 5 seconds, was experienced.
The operator was attempting to reinsert cor.? ol rods when the scram occurred.
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