ML19256C659
| ML19256C659 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/11/1979 |
| From: | Klinger G, Mckee P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| PNO-79-412, NUDOCS 7910110644 | |
| Download: ML19256C659 (2) | |
Text
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PRELIM 1 NARY NOTIFICATION September 11, 1979 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-79-412 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance.
The information presented is as initially received without verification or evaluation and is basically all that is known by IE staff on this date.
Facility:
Daiiyland Power Cooperative, Lacrosse (DN 50-409) Genoa, Wisconsin
Subject:
BREAKDOWN IN ADMINISTRATIVE CONTROL OF LOW RECIRCULATION FLOW BYPASS SWITCHES During a reactor startup on September 7,1979, operations personnel failed to take the low recirculation flow safety circuit bypass switches out of " bypass" prior to taking the reactor ' critical as required by the facility technical specification.
The key lock switches remained in the " bypass" position through five shift changes after criticality had been attained and in each case were logoed in the control room log as in " bypass."
Low power operation was conducted during this entire period and the reactor power level remained at less than one percent power.
This improper condition was identified and corrected while the recirculation pumps were on minimum flow and while the reactor power level was at less than one percent of power.
With the low recirculation flow safety circuit switches in " bypass," there is no automatic loss of flow reactor trip function until the " reactor power /re-circulation flow mismatch circuit" becomes effective at approximately 48 perceat power.
All reactor power monitoring trips were functioning properly and would have prevented core overpower situations.
The plant management is concerned about this breakdown in administrative control and is reviewing this mutter with all operations personnel.
The Operations Review Committee has reviewed this matter and has recommended strengthening the plant startup procedure and check lists to assure that this type of error does not occur in the future.
RIII inspectors are going to the site on September 11 to review the matter and evaluate corrective actions.
The reactor is currently at thirty percent power in a power ascention program.
The licensee did not issue a press release.
RIII does not plan to issue a
. press release at this time.
The State of Wisconsin has been notified.
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CONTINUED
]448 339 7910110 N
PHO-79-412
. September 11, 1979 Continued The RIII Duty Officer was notified of this event on September 9, 1979 and additional information was obtained from the plant during the morning of September 10, 1979. This information is current as of 2:00 p.m., September 10, 1979.-
Contact:
PMcKee IE, x?8019 GKlingler IE, x28019 Distribution:
Transmitted H St Chairman Hendrie Commissione. Bradford S. J. Chilk, SECY Commissioner Kennedy Commissioner Ahearne C. C. Kammerer, CA Commissioner Gilinsky ACRS (For Distribution)
Transmitted:
MNBB P. Bldg t7.'iE2L V. Stello, IE J
L. V. Gossick, EDO
- H. R. Denton, NRR Region ((J'_
H. L. Ornstein, EDO R. C. DeYoung, NRR J. J. Fouchard, PA R. J. Mattson, NRR Landow N. M. Haller, MPA D. Vassallo, NRR J. J. Cummings, 0IA R. G. 'Ryan, OSP D. Eisenhut, NRR H. K. Shapa'r, ELD SS Bldg (MAIL)
W. J. Dircks, NMSS R. Minogue, SD S. Levine, RES PRELIMINARY NOTIFICATION
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