ML19323H136

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Slide Presentation Entitled, Limerick Preliminary Risk Assessment,Technical Program Description.
ML19323H136
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 05/21/1980
From: Mccandless R
GENERAL ELECTRIC CO.
To:
Shared Package
ML19323H130 List:
References
NUDOCS 8006120127
Download: ML19323H136 (13)


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LIMERICK PRELIMINARY RISK ASSESSMENT

TECHNICAL PROGRAM DESCRIPTION i

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PRESENTED IO U.S. NUCLEAR REGULATORY COMMISSION MAY 21, 1980 soosiso lat

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LIMERICK PRELIMINARY RISK ASSESEMENT OBJECTIVES I

STUDY RESULTS AND PRESENTATION TO NRC PER MAY 6,1980, LETTER TEXT ANALYSIS R8SULTS SIMILAR TO INDIAN POINT AND ZION STUDY RESULTS d

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LIMERICK PRELIMINARY RISK ASSESSMENT APPROACH e START WITH WASH 1400 REFEh?NCE Bhh (PEACH BOTTOM)

I e IDENTIFY LIMERICK DESIGN DIFFERENCES e UPDATE WASH 1400 EVEN,T/ FAULT IREES AND CONSEQUENCE ANALYSIS TO ACCOUNT'FOR LIMERICK DESIGN DIFFERENCES e COMPARE PROBABILITY RISK CURVES WASH 1400 REFERENCE BWR WASH 1400 REFERENCE BWR AT LIMERICK SITE - -

LIMERICK AT LIMERICK SITE s..

ExeECTeo OuTeur 5 0F PRELIMINARY RISK ASSESSMENT WASH 1400 AT LIMERICK SITE WASH 1400 PROBABILITY LIMERICK AT ITS SITE (THIS STUDY)

RISK

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LIMERICK PRELIMINARY RISK ASSESSMENT NORK SEQUENCE START WORK MEET WITH NRC TASK 1 IDENTIFY DESIGN. DIFFERENCES

TASK 2 IDENTIFY AND ANALYZE ACCIDENT SEQUENCES TASK 3 DEVELOP AND APPLY CONSEQUENCE MODEL TASK 4 PREPARE

SUMMARY

PRESENTATION TASK 5 REVIEW AND VERIFY

SUMMARY

PRESENTATION TO PECO TASK 6 .

REVISE AND ISSUE REPORT 9

TABLE 1 ,

EXAMPLES OF DESIGN DIFFERENCES BETWEEN LIMERICK AND THE WASH 1400 REFER NCE BWR e MARK ll CONTAINMENT NO TORUS HIGHER FREE CONTAINMENT VOLUME LESS COMPLEX GEOMETRY LESS SEVERE POOL SWELL LOADS e LARGER STANDBY LIQUID CONTROL IANK VOLUME e HIGHER HIGH PRESSURE COOLANT INJECTION FL0n e LOWER REACTOR CORE ISOLATION COOLING MAXIMUM EXHAUST PRESSURE e F0uR (vs. TWO) INDIVIDUAL LOW PRESSURE COOLANT INJECTION POINTS e F0uR EMERGENCY CORE COOLING SYSTEM ELECTRICAL DIVISIONS WITH DEDICATED DIESELS e HIGH PRESSURE COOLANT INJECTION INTO CORE SPRAY SPARGER e MORE REACTOR WATER CLEANUP SYSTEM PUMPS e MORE SAFETY / RELIEF VALVES (14 VS. 11) WITH NEW TOP WORKS AND NO SPRING SAFETIES

, TABLE 1 (CONTINUED) e PIPING MATERIAL CHANGES CORE SPRAY PIPING (316L VS 304)

RECIRCULATION PIPING (316 VS. 304)

LPCI/HEADSPRAY PIPING (316L VS. 304) 4 DRAIN LINE PIPES (316L vs. 304) e ANALOG IRANSMITTER IRIP UNITS e NEW FEEDWATER N0ZZLE AND SPARGER DESIGN e

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LIMERICKPRELIMINARYRISKASSESSMENT

}DEfRIFY DOMINANT ACCIDENT SEQUENCES e IENTIFY INITIATING EVENTS STARTING WITH WASH E00 e CmSTRuCT EVEtU IREES TO DEPICT SUCCESS / FAILURE TO HOT SHlRDOWN e UPDATE SYSTEM FAULT TREES,FOR EA W SEQUENCE e ANALYZE SEQUENm PROBABILITIES INCLUDiC[DUETOINSTRUMENTMISCALIBRATION INCLUDES Cf DUE TO ELECTRICAL /INSTRUNNTATION Cott0NALITY EXCLUES Of DUE TO OPERATOR ACTION EXCLUDES Of DUE TO EARm0uAKE/ FIRE /SAB0TAE e GROUP ACCImf6 SEQUENCES IfRO CONSEQUENCE CATEGORIES l

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, CMF = COMMON MODE FAILURE

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l LIff7.ICK PRELIMINARY RISK ASSESSMENT MARK ll CONTAINMENT ANALYSIS e ASSESSASSlPPTIONSUSEDINl'IASH1E e IDENTIFYDESIGNDIFFERnNCES e ANALYZESPECIFICCASESASIEEDED OVERPRESSWE FAILURE lbDE STEAM BCPLOSIm POTENTIAL DIAPHRACM FLOOR EFFECTS PEDESTAL DESim DWNCONRARRANGENNT e ASSIm PROBABILITIES TO FAI!URE MODES FOR POSTUL.ATED COREDISRLPTIVEACCIDENT -

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LIMERICK PRELIMINARY RISK ASSESSMENT

DEVELOP PuwT UNiouE CONSEQUENE EDDEL 1

e ibDIFY CRAC INPUT.TO INCLUDE:

e SITE SPECIFIC WEAmER (HOURLY) e SITE POPULATION DENSITY e PLANTFISSIONPR0auCTINVENTORY e AnoTOCRACANALYSIS:

e EVACUATION PLANS / EFFECTS' l

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