ML20137P787

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Summary of 851016-17 Meetings W/Util & Impell Corp Re Licensee Auxiliary Feedwater Reliability Analyses.Viewgraphs & Proposed Outline of Reliability Analysis Rept Encl
ML20137P787
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/21/1985
From: Mccracken C
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8512050103
Download: ML20137P787 (22)


Text

~

November 21, 1985 hb

' Docket No. 50-346 LICENSEE: Toledo Edison Company FACILITY: Davis-Besse Unit No. 1

SUBJECT:

AUXILIARY FEEDWATER (AFW) RELIABILITY ANALYSIS MEETING, OCTOBER 16 AND 17, 1985 Introduction We met with the licensee to discuss the status and results of AFW Reliability Analyses. Copies of the view graphs are provided in Enclosure 1. Enclosure 2 presents the proposed outline of the reliability analysis report. This was a follow-on meeting to the one conducted on September 25, 1985 at the Davis-Besse site. The meeting was attended by:

TED IMPELL CORP. NRC S. Jain S. Mitra C. McCracken C. Minge A. El-Bassioni J. Ridgely F. Rosa Discussion The licensee presented a summary of their AFW unavailability results (see last two pages of Enclosure 1). Additionally, they stated that the AFW reliability results would be docketed by October 25, 1985. For a loss main feedwater event, the licensee predicts an unavailability ofs 8x10-5 for the modified AFW system, allowing for operator action to start the new motor driven feed pump. The staff requested that justification be provided for each of the assumptions in their analysis.

To evaluate single failure vulnerability of the SFRCS, the staff requested a block diagram failure modes and effects analysis (FMEA). The licensee committed to provide this analysis by October 25, 1985.

?<- W Conrad McCracken Operating Reactors Branch #4 Division of Licensing

Enclosures:

As Stated cc w/ enclosures:

See next page -

s l-8512050103 851121 PDR ORB #4:DL ADOCK 05000346 CMcCracken;cr P PDR 11p//85

Enclosure 1 l OCTOBER 16-17, 1985 MEETING WITH NRC ON AFWS RELIABILITY ANALYSES

. S. C. JAIN PURPOSE OF MEETING

, S. C. JAIN BRIEF DISCUSSION OF DB-1 AFWS d

. S. C. JAIN REVIEW 0F ONG0ING AFWS RELIABILITY ANALYSES

. S. P. MITRA SCOPE OF SRP ANALYSES

. S. P. MITRA PLANNED SHORT-TERM MODIFICATIONS TO AFWS

. NRC, S. C. JAIN DETAILED REVIEW 0F THE IMPELL SRP S. P. MITRA ANALYSES

. S. C. JAIN

SUMMARY

OF ACTION ITEMS

. S. C. JAIN PLANS FOR FUTURE INTERACTIONS O

I

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AUXILIARY FEEDWATER OVERVIEW

. TWO 100% CAPACITY STEAM DRIVEN PUMPS

. CAPABILITY TO PF] VIDE MOTIVE STEAM TO AUXILIARY FEED PUMP TURBINES F".0M EITHER STEAM GENERATOR

. CAPACITY TO AL'f;N AUXILIARY FEED PUMP DISCHARGE FLOW TO EITHER STEli GENERATOR

. SAFETIGRADEINITIATIONBYTHESTEAMANDFEEDWATER

. RUPTURE CONTF JL SYSTEM

. SAFETY GRAD! STEAM GENERATOR. LEVEL CONTROL SYSTEM i

. TRAIN 1 MOV'S ARE DC POWERED i l TRAIN 2 M0V'S ARE AC POWERED l _

NORMAL SUCTION ALIGNED TO CONDENSATE STORAGE TANKS.

AUTOMATIC TRANSFER TO SAFETY GRADE SERVICE WATER SYSTEM ON LOW SUCTION PRESSURE l

l AUXILIARY FEEDWATER INITIATION THE SFRCS WILL INITIATE AFW UNDER THE FOLLOWING PLANT CONDITIONS:  !

. 1. LOW STEAM GENERATOR LEVEL

2. HIGH STEAM GENERATOR LEVEL
3. HIGH STEAM GENERATOR TO MAIN FEEDWATER DIFFERENTIAL PRESSURE
4. LOSS OF FOUR RCP'S
5. LOW STEAM GENERATOR PRESSURE ,

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e 8 9 PLANNED MODIFICATIONS TO RESOLVE HISTORICAL CONCERNS REPLACE WOODWARD PG-PL GOVERN 0R ON AFPT #1 WITH A WOODWARD PGG MODEL GOVERNOR TO RESOLVE BINDING AND CLUTCH CONCERNS. A PGG GOVERNOR WAS INSTALLED ON AFPT #2 DURING LAST REFUELING OUTAGE.

IMPROVED MAINTENANCE AND TESTING ON LIMITOROUE VALVE OPERATORS.

MOTIVE STEAM TO BE SUPPLIED DIRECTLY TO THE STEAM ADMISSION VALVES

~

ALIGNING ALL M0V'S IN THE N0RMAL PUMP DISCHARGE LINES NORMALLY OPEN. ,

INSTALLING ONE AIR OPERATED-FAIL OPEN VALVE IN THE STEAM SUPPLY LINE NEAR EACH AFPT TO RESOLVE CONDENSATION CONCERN

PLANNED MODIFICATIONS TO RESOLVE HISTORICAL CONCERNS '

(CONT'D)

. INCREASE MESH SIZE OF THE CST DISCHARGE STRAINER TO AFP TO REDUCE PRESSURE DROP IN SUCTION LINE.

. ELIMINATE BASKETS FROM THE AFP SUCTION STRAINERS.

. REVISE SUCTION TRANSFER LOGIC TO MINIMIZE SPURIOUS TRANSFER TO SERVICE WATER INSTALL NEW 800 GPM MOTOR DRIVEN FEED PUMP I

D

. . l INSTALLATION OF MOTOR DRIVEN FEED PUMP

. INSTALL NEW MOTOR DRIVEN FEED PUMP PRIOR TO STARTUP

, UEW PUMP DESIGN FEATURES:

. PROVIDES 100% CAPACITY AUXILIARY FEEDWATER FLOW

. PUMP DISCHARGE ALIGNED TO THE AUXILIARY FEEDWATER HEADERS DURING NORMAL FULL POWER OPERATION

. PUMP SUCTION NORMALLY FROM THE CONDENSATE STORAGE TANK

. PUMP CAPABLE OF BEING ST,ARTED FROM THE CONTROL ROOM e

l

l INSTALLATION OF MOTOR DRIVEN FEED PUMP PRE-STARTUP (CONT'D)

. PUMP MOTOR CAN BE SUPPLIED FROM EITHER EMERGENCY DIESEL GENERATOR FOLLOWING A LOSS OF 0FFSITE POWER CAN BE MANUALLY REALIGNED TO FEED THE MAIN FEEDWATER SYSTEM. THIS WILL BE THE NORMAL ALIGNMENT DURING LOW POWER OPERATION. PUMP SUCTION IN THIS ALIGNMENT WILL BE FROM THE DEAERATOR STORAGE TANK.

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._. - . . . _. -_.___-_,_,-,__.,.,y. _ . , _ _ . _

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OVERVIEW OF ONG0ING RELIABILITY ANALYSES l

STANDARD REVIEW PLAN /NUREG-0611 ANALYSES

. CASES ANALYZED

. LOSS OF MAIN FEEDWATER (LMFW)

. LMFW WITH LOSS OF 0FFSITE POWER

. LMFW WITH LOSS OF ONSITE AC POWER CONFIGURATIONS ANALYZED

. EXISTING AFWS CONFIGURATION h

PLANNED SHORT-TERM AFWS CONFIGURATION

. NUREG-0611 DATA BASE UTILIZED 1

OVERVIEW 0F ONG0ING RELIABILITY ANALYSES DETAILED RELIABILITY EVALUATION

. FEATURES:

. GENERAL UPDATE OF 1981 EDS (IMPELL) STUDY

. PLANT SPECIFIC DATA BASE MUCH MORE DETAILED THAN NUREG-0611 MODELS

. CONFIGURATIONS ANALYZED

~

PRE-TMI AFWS CONFIGURATION

. AFWS CONFIGURATION AS OF JUNE 9, 1985 PLANNED SHORT-TERM AFWS CONFIGURATION MODEL IS MORE PLANT SPECIFIC AND PROVIDES ADDITI0NAL INSIGHT INTO DAVIS-BESSE AFWS UNRELIABILITY

l SCOPE OF STUDY IN RESPONSE TO SRP 10,4,9 l

. RELIABILITY OF THREE (3) AFWS CONFIGURATIONS WERE STUDIED

. EXISTING (AS OF JUNE 9, 1985)

. PLANNED PLANNED WITH INCLUSION OF MOTOR DRIVEN FEED PUMP RELIABILITY ASSESSED FOR EACH CONFIGURATION IN RESPONSE TO THREE (3) INITIATING EVENTS LOSS OF MAIN FEED (LMFW)

. LOSS OF 0FFSITE POWER (LOOP)

. LOSS OF ALL A.C. (LOAC) -

\

1 l

REGULATORY PRESCRIPTION FOR DEMOSTRATING i COMPLIANCE WITH SRP 10.4.9 ACCEPTANCE CRITERIA

. SRP 10.4.9 ACCEPTANCE CRITERIA FOR AFWS

. AFWS UNRELIABILITY 10-4 TO 10-5 PER DEMAND.

OTHER METHODS FOR ACCOMPLISHING AFWS SAFETY FUNCTION OR RELIABLE METHODS FOR CORE COOLING MAY BE CONSIDERED TO JUSTIFY A HIGHER UNRELIABILITY

. PRESCRIPTION

\ .

TO BE PERFORMED IN ACCO.RDANCE WITH ITEM II.E.1.1 0F NUREG-0737 ,

i i

. IDENTIFY MAJOR CONTRIBUTORS TO AFWS SYSTEM FAILURE

. DATA AND METHODS FROM NUREG-0611 (APPENDIX III a ANNEX 1 0F APPENDIX X) -

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AFWS SUCCESS CRITERIA

. USED FOR SRP AFWS STUDY

, EXISTING AND PLANNED CONFIGURATIONS

. ONE (1) 0F TWO (2) STEAM GENERATORS RECEIVE AFW FROM 1 0F 2 AFW PUMPS

. PLANNED CONFIGURATION WITH MOTOR DRIVEN MAIN FEED PUMP.

. ONE (1) 0F TWO (2) STEAM GENERATORS RECEIVE AFW FROM 10F 2 TURBINE DRIVEN AFW PUMPS OF! MOTOR DRIVEN FEED PUMP AFW TO BE DELIVERED IN TIME TO AVERT STEAM GENERATOR DRYOUT CONDITION LMFW - ew 5 MINS.

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i MEETING

SUMMARY

DISTRIBUTION Licensee: Toledo Edison Company

  • Copies also sent to those people on service (cc) list for subject plant (s).

Docket File NRC PDR L PDR ORB #4 Rdq Project Manager - C. McCracken

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JStolz BGrimes (Emerg. Preparedness only)

OELD EJordan, IE ACRS-10 NRC Meeting

Participants:

AEl-Bassioni JRidgely FRosa l

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