ML19254A662
| ML19254A662 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/31/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907200356 | |
| Download: ML19254A662 (1) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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May 31, 1979 In Reply Refer To:
RIV Docket No. STN 50-482/IE Bulletin No. 79-12 Kansas Gas & Electric Co.
Attn:
Mr. Glenn L. Koester Vice President-Operations Post office Box 208 Wichita, Kansas 67201 Gentlemen:
The enclosed IE Bulletin 79-12 is forwarded to you for informatior.
No written response is required.
If you desire additional int'ormation regar
,this matter, please contact this office.
Sincerely, 6p)f1g/g, [
Il Karl V. Seyfr)
Director
Enclosures:
1.
IE Circular No. 77-07 3.
List of IE Bulletins Issued in I.ast Twelve Months cc:
w/ enclosures Messrs.
Nicholas A. Petrick, SNUPPS D. i. McPhee, Kansas City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Compan.'
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UNITED STATES NUCLEAR REGULATORY C051 MISSION 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 hi h 8
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 appropriate to further reduce the number of challenges to the reactor protective system high IRM flux scram.
Description of Circumstances:
The following is a brief account of each event.
1.
Oyster Creek - On December 14, 1978, the reactor experienced a scram as control rods were being withdrawn for approach to critical, following a scram from full power which had occurred about 15 hours1.736111e-4 days 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 rod in Group 9) was being withdrawn in " notch override" to notch position 10, 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 Lim to believe that the reactor was very subcritical.
A short reactor period estimated at 5 seconds, was experienced.
The operator was attempting
.o reinsert control rods when the e
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