ML20151G931

Summary of Meeting w/C-E Re C-E Owners Group CEN-327, Rps/ ESFAS Extended Test Interval Evaluation

ML20151G931
Person / Time
Issue date:	07/19/1988
From:	Wohl M Office of Nuclear Reactor Regulation
To:	Butcher E Office of Nuclear Reactor Regulation
References
NUDOCS 8808010055
Download: ML20151G931 (3)

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MEMORANDUtt FOR:

Eoward J. Butcher Chief Technical Specifications Branch Division of Operational Events Assessment. NRR THRU:

Richard L. Erch Jr., Acting Section id r Special Projects Section Technical Specifications Branch Division of Operational Events Assesstent.

RR FROM:

flillard L. Wohl Special Projects Section Technical Specifications Branch Division of Operational Events Assessrent. NRR

SUMMARY

DF MEETING WITH COPBUSTION ENGINEERING ON C-E OWNERS GROUP 10PICAL REPORT CEN-327. "RPS/ESFAS EXTEhDED TEST INTERVAL EVALUATION" OTSB. SICB, and PRAB staf f wrbers met w' 6h personnel f rom Corbustion Engineering Con.pany to discuss problems encountered in the review of Combustion Engineering Owners Group (CE0G) Topical Report CEN 327. A Yendor/0wners Grous, presentation was rade on ext $nsion of surveillance intervals (Sils) for RP5/ESFAS, o

Risk Irpact of Extended ST!s for RPS/ESFAS CEN-327 analyses indicated that RPS/ESFAS STis can te increased without increasing overall core damage frequency (CDF) based upen use of the core damage event trees presented in the Calvert Cliffs IREP Study.

The decrease in C0F due to test-induced transients with extended Sils was evaluated using the T, sequences (Remaining Transients Requiring Reactor Trip).

The increase in CDF due to the increase in RPS unavailability was evaluated ustrg ATWS core melt sequences.

Because ESFAS unavailability is not as directly related to C0F as is RPS unavailability, the trpact of ESFAS unavatisoliity on C0F was evaluated by identifying cutsets involving ESFAS faults in each cominant core darage sequence.

CEh 327 proposes in order to rett the "no increase in core danage frequency" criterion, a variety of STi extensions involving 60 and 90 cay Sils replacing 30 day $11s anc it,volving vertous sequential and staggered testing scheres.

The staff h censidering a sirpler enveleping exterded STI. crong other options.

o ESFAS Typyss C E statf ciscussed three general types of ESFAS at C-E plants.

These are:

1) C E cesigned

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2) Non-C-E designed with relay logic 3 ' ^,

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Non-C E designed with solid state logic M

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C E ESFAS Actuation Signals The following actuation signals are generated by the ESFAS when the ronitored variables reach protective action levels:

1) Containment isolation Actuation Signal (CIAS)

2) Containment Spray Actuation Signal (CSAS)

3) Hain Steam isolation Signal (MSIS)

4) Saf ety injection Actuation Signal (SlAS)

5) Recirculation Actuation Signal (RAS)

6) Auxiliary feedwater Actuation Signal (AFAS)

The staf f raised sore concerns related to the conputed f ailure probabilities due to STI extension f or the AF A! signal.related items.

This concern is presently under internal statf discussion. is an attendance list. is the meeting announcerent.

Odrieat Synod By Hillard L. Wohl Special Projects Ser, tion Technical Specifications Branch Division of Operational Events Assesseent. NRR

Enclosures:

As stated i

DISTRIBUTI0h:

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COEA R/F N) Central files CERossi POR EJButcher RLEmen MLWohl OTSB Hecters WDLanning l

R8arrett Shewberry KCar.pe i

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l NAME AFILiAT10N PHONE NO.

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San 9 Rhow NRR/ DEST /51C6 301) 492 0779 Lloyd Philpot Combustion Engineering 203) 285 5210 i

David Finnicum Combustion Engineering 203) 265 3926 l

Richard A. Bernier Arizona Public Service Co.

(602 371 4295

l Ec Chow NRR/DREP/PRAB L301 492 1077 Kas Cage NRR/DREP/PRAB

[301 492 0192 i

Stuart Webster Combustion Engineering

( 203 285 4405 Kulin D. Desai NRR/00EA/0TSB (301 492 1166 t

492 3265 l

l Joseph P. Joyce NRR/0EST/IC58 (301)4921181 Millard Wohl NRR/00EA/0158 (301) i i

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DJCLOCORE 2 July 6, 1988 NEMORAN0bH FOR:

Edward J. Butcher. Chief Technical Specifications Branch Division of Operational Events Assessment, hRR l

FkOM Richard L. Emch. 1r.. Section Chief Special Projects Section Technical Specifications Branch

$UBJECT:

FORTHCOM!hG NEETING FOR CULMINATlhG REvlEW 0F COM8USTION

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ENGINEERING TOPICAL REPORT CEN.327. "RF5/ESFA5 EXTENCEO TEST INTERVAL EVALUATION" l

LATE & TIME:

Wednesday July 13. 1988. 9:30 12:30 LOCATION:

huclear Regulatory Cereission White Flint horth Building 3

Room 14811 11555 Pockville Fike l

Rockville. Maryland 20852 4

PUFPOSI:

TO DISCU5S FRA MODELLING. RPS AND ESFAS OPERATION AhD TESTING. AND ESFAS TECHNICAL SPECIFICATIONS 4

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FARTICIPANTS:

NRC

_ COMBUSTION ENGlhEERlhG CE0G

5. hewberry L. Fhilpot R. Bernier J. Mauct D. Finnirum R. Em:h j

11. Wohl J

D. Lasher K. Campe i

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Original Signed by I

Rchard L. Emch. Jr.

Richard L. Emch Jr. Section Chief lechnical Specifications Branch Divisien of Operationa) Events Assessrent. NRR b.

Y 07/e7/f6 07/ 7 /68

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