05000255/LER-1979-041-01, /01T-0:on 791009,during Analysis Review,Main Steam Line Break Accident Analysis Found to Be Incorrect. Caused by Failure to Consider Continued Operation of Condensate Pumps.Feed Reg Valves Modified

/01T-0:on 791009,during Analysis Review,Main Steam Line Break Accident Analysis Found to Be Incorrect. Caused by Failure to Consider Continued Operation of Condensate Pumps.Feed Reg Valves Modified

ML18044A186
Person / Time
Site:	Palisades
Issue date:	10/30/1979
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18044A187	List: 05000255/LER-1979-041, Forwards LER 79-041/01T-0 05000255/LER-1979-041-01, /01T-0:on 791009,during Analysis Review,Main Steam Line Break Accident Analysis Found to Be Incorrect. Caused by Failure to Consider Continued Operation of Condensate Pumps.Feed Reg Valves Modified
References
LER-79-041-01T, LER-79-41-1T, NUDOCS 7911020282
Download: ML18044A186 (2)

LER-1979-041, /01T-0:on 791009,during Analysis Review,Main Steam Line Break Accident Analysis Found to Be Incorrect. Caused by Failure to Consider Continued Operation of Condensate Pumps.Feed Reg Valves Modified

Event date:
Report date:
2551979041R01 - NRC Website

text

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(c;@[jffi]~@Jffil17 General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 October 30, 1979 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Connnission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 79-041 - MAIN STEAM LINE BREAK ACCIDENT ANALYSIS On the reverse side please find Licensee Event Report 79-041 which is report-able under Technical Specification 6.9.2.a.9.

Due to an oversight by the Gener-al Office Licensing Staff, this LER is being submitted late.

The NRC Region III office was notified by TWX on October 9, 1979, of the Licensee Event Report.

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David P Hoffman Assista.~t Nuclear Licensing Administrator CC:

Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NOV 11979

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PALISADES PLANT NRC FORM3S6 17-nl U, S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I 1 G)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1

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9 LICENSEE CODE 14

,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [ilIJ 7

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=~~~~~ 11JG)I q 5 I 010 I 0 I 21 5 15 GI 11 010 ~ 17 I 9 KVll I 0 I 31° I 7 I 910 6ll 61 OOCICET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During an accident analysis review conducted pursuant to IE Notice 79-22,

(())] 1 it was discovered that during a MSLB accident, the condensate pumps would continue to feed the affected steam generator at an excessive rate.

This would result in both a more severe restart and a higher containment pressure than was analyzed in the FSAR accident analysis l))2J I for the MSLB accident.

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CAUSE

CAUSE COM?.

VALVE CODE CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCODE IHIHI@ ~@ L!.J@ IZIZIZIZIZIZI@ ~@ ~@

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L£J 32 eo TAICEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM :>UB.

SUPPLIER ACTION FUTURE EFFECT

. SHUTDOWN

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CAUSE DESCRIPTION ANO CORREC-rlVE ACTIONS @

44 47 ITJ]J I The :MFP rampdown was designed to mitigate the consequences of the MSLB OJI) accident; however the continued operation of the condensate pumps (shutoff head approx. 570 psi) was apparently not considered.

To correct o::r::Il I this condition, the feed reg valves control scheme will be modified so that low S/G press*. will cause the FRVS/bypass* valves to automatically EIIIl ~1---......... ~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~-~--

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STATUS

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9 10 11 80 METHOD OF

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DISCOVERY DISCOVERY DESCRIPTION ~

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