LER-2077-010, License Event Report 1977-010-00 Re Four PCP Loss of Flow |
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| 2552077010R00 - NRC Website |
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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 February 14, 1977 Mr James G Keppler Office of Inspection & Enforcement Region III US Nuclear RegulatorY Commission 799 Roosevelt Road Glen Ellyn, IL 60137
- COCKET 50-255, LICENSE DPR PALISADES PLANT - ER-77 FOUR PCP LOSS OF FLOW Rf 6Ui.11
- Y DOClffT FILE CP1>11 On February 1, 1977, we notified the IE staff of increased icing on the~~Jhs mission towers and lines between the Palisades Plant and the 345 kV switchyard.
The consequences of a complete tower failure could result in a condition not specifically considered in the FSAR Section 14.7.
We, therefore, initiated analysis to determine the structural adequacy of the towers and lines as well as a 4-pump loss of flow without steam generator coastdown.
The 4-pump loss of flow analysis has been completed and transmitted to the NRC staff for review.
The results indicated the transient to be less severe than others presented in Section 14.7 of the FSAR.
PreliminarY analyses of the transmission towers and lines have been completed which indicate that a margin of safety exists for observed ice loadings.
Additional evaluations are being made to 'determine if any modifications to the towers or lines are required.
David P Hoffman Assistant Nuclear Licensing Administrator FEB 1 7 1977
LICENSEE EVENT REPORT-Palisades CONTROL BLOCK: I 1 I I I I *' I (PLEASE PAINT ALL REQUIRED INFORMATION)
REPORT TYPE.
6 LICENSE NUMBER I ol ol-lol ol ol ol ol-1 ol ol 15 25 REPORT SOURCE OOCKET NUMBER LICENSE TYPE 1411l1l1l 1I 26 30 EVENT DATE EVENT TYPE Io 11 I 31 32 REPORT DATE
@El CON'T T *. ].* I 7
8 57 58 w llJ lo 15 lo I-lo 1215151 I o I 1 I 3 I 1. I 1 I 1 I lol2!1141117.I 59 60 61 68 69 74 75 80
EVENT DESCRIPTION
lol2I I On Januarv 31, 1977, 7
8 9 ice loading on the 345 kV bus tie and station nower lines between I 80 lol3I I the Palisades 7
8 9 Plant and the switchyard were observed to be greater than normally ex-lol41 I pected due to the cooling tower plume passing the lines..
- 7. 8 9 Plant power level was held I
80 I
80 lo151 I at 60% until 4 PCP loss of flow without turbine generator 7
8 9 coastdown could be analyzed I lfilID I and proper operation of both diesel generators verified.
7 8 9 SYSTEM CODE
@El I El GI 7
8 9 10
CAUSE
CODE L£J 11 CAUSE DESCRIPTION COMPONENT CODE I z I z I z I zl zl z I 12 17 PRIME COMPONENT SUPPUER w
43 COMPONENT MANUFACTURER I z I z I z I z I 44 47 80 (ER-77-10) 1 80 VIOLATION L~J' 48
@:@ I Abnormal icing is due to enviromnental conditions and operation of the cooling towers. I.
7 8 9 lolsl I FSAR.l'.ccident Analysis (Sec 14. 7) does not consider 4 pump loss of flow incident l8j j without turbine generator assist as. credible.
~9 EEI 7
8 FACILITY STATUS LE..I 9
FORM OF ACTIVITY RELEASED
% POWER OTHER STATUS I o I 6 I o I NA 10 12 13 44 CONTENT rn w OF RELEASE AMOUNT OF ACTIVITY
~ _j _____
NA ____ --~
7 8
9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
IT@] I ol o I ol LIJ 7
8 9 11 12 13 PERS"ONNEL INJURIES NUMBER
DESCRIPTION
B:Eilololol 7
8 9 11 12 PROBABLE CONSEQUENCES METHOD OF DISCOVERY w
45 45 NA NA DISCOVERY DESCRIPTION I Visual Obs of Towers & Lines 46 LOCATION OF RELEASE NA lTifil I None; loss of 4 PCP analysis 7
8 9 indicates adequate MDNBR.
LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
QEW NA 7
8 9 10 PUBLICITY NA I :oomoNAL FACTORS
@fil NA 7
8 9 [iliJ NA 7
8 9 80 I
80 I
80 80 80 80 80 80 80 80 BO BO
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