ML20134G412

Summary of 850815 Meeting W/Bnl,Util,Westinghouse & Bechtel in Bethesda,Md Re Limiting Conditions for Operation Relaxation Program.Attendance List & Slide Presentation Encl

ML20134G412
Person / Time
Site:	Byron
Issue date:	08/20/1985
From:	Olshan L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
CON-FIN-A-3810 NUDOCS 8508260060
Download: ML20134G412 (22)

Text

.

AUG 2 01995 Docket Nos.: STN 50-454 l

and STN 50-455 APPLICANT:

Comonwealth Edison Company FACILITIES:

Byron Station, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

- STATUS REPORT ON REVIEW 0F BYRON LC0 RELAXATION l'R0 GRAM On August 15, 1985, at a meeting held in Bethesda, Maryland, Brookhaven National Laboratory (BNL) presented the status of its review of the Byron LCO (Limiting Conditions for Operation) Relaxation Program. Members of the NRC, Comonwealth Edison (the applicant) and Westinghouse were present at the meeting. A list of attendees is given in Enclosure 1.

The slides used by BNL are included in.

The results presented by BNL were preliminary; a draft of BNL's report is due by September 30, 1985. BNL's review indicated that a static fault tree analytical approach, such as that utilized in the Byron study, was adequate for assessing the risk impact of an increase in Technical Specification Allowed Outage Times (A0Ts). The BNL evaluation shows that the maintenance outage time contribution I

to core damage frequency (CDF) is approximately linearly dependent on maintence outage time. As shown in the second figure in Enclosure 2, the BNI results in-dicate a relatively weak CDF dependence on maintenance outage times for a number of systems, including ECCS injection and AFWS. BNL identified a number of short-comings in the Byron analysis, but overall, preliminary findings indicate l

approximate agreement between BNL results and the Byron study results with re-gard to CDF.

1 The NRC indicated the end of 1985 to be a target date for possible resolution of the applicant's request for an increase in the allowable outage time of certain equipment from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days.

Leonard Olshan, Project Manager Licensing Branch No. 1 Division of Licensing

Enclosures:

As stated cc: See next page f

A LB#1/DL LB VDL01shan/mac BJY lood 6/ O /85 g/

/85 1

850826006o 85o820 PDR ADOCK 050 4

P

Mr. Dennis L. Farrar Byron Station Commonwealth Edison Company Units 1 and 2 cc:

Mr. William Kortier Ms. Diane Chavez Atomic Power Distribution 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III U. S. Nuclear Regulatory Commission Michael Miller 799 Roosevelt Road Isham, Lincoln & Beale Glen Ellyn, Illinois 60137 Cn? First National Plaza 42id Floor Joseph Gallo, Esq.

Ch.cago, Illinois 60603 Isham, Lincoln & Beale Suite 840 Mrs. Phillip B. Johnson 1120 Connecticut Avenue, N.W.

1907 Stratford Lane Washington, D. C.

20036 F.ockford, Illinois 61107 Douglass Cassel, Esq.

Dr. Bruce von Zellen 109 N. Dearborn Street Department of Biological Sciences Suite 1300 Northern Illinois University Chicago, Illinois 60602 DeKalb, Illinois 61107 Ms. Pat Morrison Mr. Edward R. Crass 5568 Thunderidge Drive Nuclear Safeguards & Licensing Rockford, Illinois 61107 Sargent & Lundy Engineers 55 East Monroe Street Ms. Lorraine Creek Chicago, Illinois 60603 Rt. 1, Box 182 Manteno, Illinois 60950 Mr. Julian Hinds U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Offices

,o 4448 German Church Road 1

Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive Springfield, Illinois 62704

a i

ENCLOSURE 1-STATUS OF REVIEW OF BYRON LCO RELAXATION PROGRAM AUGUST 15, 1985 NRC Brookhaven National Laboratory

?! haranowski N. Z. Cho A. Busiik T. Chu S. Newberry R. Youngblood L. 01shan G. L. Plumlee R. Robinson Commonwealth Edison 4

A. Spano L. Anastasia A. Thadani D. Farrar l

Westinghouse D. Sharp I

i Other D atson, Bechtel 4

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ENCLOSURE 2 1

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REVIEW 0F BYRON LC0 RELAXATION STUDY I

(FIN A-3810) 4

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f, 1

I RISK EVALUATION GROUP l

DEPARTMENT OF NUCLEAR ENERGY BROOKHAVEN NATIONAL LABORATORY l

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t AUGUST 15, 1985 J

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1 BROOKHAVEN Nail 0NAL LABORATORY l}gyl A5500ATED UNIVERSITIES, INC.($Ill 1

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e BACKGROUND COMMONWEALTH EDIS0N PROPOSED TO EXTEND A0Ts FROM 3 DAYS TO 7 i

DAYS FOR THE FOLLOWING BYRON SYSTEMS:

DGs ESWS AFWS CCWS CHRS (CF, CS) i ECCS (CHARGING, SI, RHR) e OBJECTIVES

)

TO ASSESS:

(1)

THE METHODS (2)

AN ESTIMATE OF CHANGE IN RISK i

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Figure 2.1 Block configuration of a sample problem.

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.A' Static Fault Tree 8

B FRANTIC

• C FRANTIC #

D Markov 7

Core Damage Frequency 6

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Unavailability x

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29 40 60 80 100 120 140 160 A0T (Hours) l Figure 2.2 Average Unavailability and Core Damage Frequency as functions-of A0T.

-_m

~ ---, -,,.., - -

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OUTLINE SURVEY OF METHODS e

STATIC FAULT TREE TIME DEPENDENT UNAVAILABILITY MARKOV a

REEVALUATION OF BYRON LC0 STUDY e

METHODS AND LIMITATIONS FAULT TREE MODEL MODIFICATIONS EVENT TREE MODEL MODIFICATIONS

[

f DATA e

RESilLTS FOR 8 CASES BETWEEN A0T1 AND A0T2 i

MINIMAL CUT SETS SYSTEM LEVEL SEQUENCE LEVEL PLANT DAMAGE STATE LEVEL CORE DAMAGE FREQUENCY LEVEL IMPORTANCE MEASURES SINGLE EVENT IMPORTANCE PAIRWISE IMPORTANCE PLANT DAMAGE STATE FREQUENCIES CORE DAMAGE FREQUENCIES BROOKHAVEN NAll0NAL LABORATORY l}l3l A5500ATED UNIVERSITIES,INC.(IIll

\\

1 REEVALUATION OF BYRON LCD STUDY e

METHODS AND THEIR LIMITATIONS AS APPLIED IN BYRON " STANDARD" PRA METHODS INITIATORS (ZION PSS)

ISSUES OF COMPLETENESS:

NO CONSIDERATIONS OF LOSS OF DC BUS AND LOSS OF SERVICE WATER AS INITIATORS EVENT TREES (SLIGHTLY MODIFIED ZION PSS)

FAULT TREES (DEVELOPED FOR BYRON)

COMPONENT UNAVAILABILITY = 1/2 A T + Po + A TM + T/T +

s 0

MFIR + HE MEAN TIME TO REPAIR (MTTR) FOR TR SINGLE TR FOR ALL SYSTEMS Po' = 1/2 A T + Pn FOR ACTIVE COMPONENTS ~

s LARGE EVENT TREE / SUPPORT SYSTEM DECOMPOSITION APPROACH 6 SUPPORT STATES CCWS IN EVENT TREES UNWARRANTED SEQUENCES IN EVENT TREE DEVELOPMENT NO SYSTEM SUCCESS IN EVENT TREE MODELING 1

BROOKHAVEN Nail 0NAL LABORATORY l}lyl A5500ATED UNIVERSITIES, INC.(ILll t

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REEVALUATION APPROACH FAULT TREE LINKING APPROACH CUTSETS, IMPORTANCE MEASURES TWO BOUNDING CALCULATIONS USING 2 A0Ts EASILY PROVIDES 00ANTITIES FOR ANY A0Ts BETWEEN THE 2 BOUNDING A0Ts.

SYSTEM LEVEL FAULT TREE MODIFICATIONS 1

TECHNICAL SPECIFICATIONS MAINTENANCE OVERLAPS WERE DELETED WITHIN A SYSTEM, BETWEEN FRONTLINE AND SUPPORT SYSTEMS 2

RECONFIGURATION 3

SYMMETRIC TRAINS o

OPERATING VS STANDBY TRAINS o

TEST INTERVALS EVENT TREE MODIFICATIONS 1

REMOVED NA0H SYSTEM 2

TREATED CCWS AS A SUPPORT SYSTEM 3

REMOVED UNWARRANTED SEQUENCES 4

COMBINED EVENT TREE 12 (LOSS OF 0FFSITE POWER WITH ONSITE POWER AVAILABLE) WITH EVENT TREE 12A (LOSS OF 0FFSITE POWER WITH NO ONSITE POWER AVAILABLE)

BROOKHAVEN Nail 0NAL LABORATORY l} gyl ASSOCIATED UNIVERSITIES, INC.(1 Ell

2 1

5 EVENT TREE N0DE E60 IN ET12A WAS DELETED BECAUSE IT WAS INCLUDED IN SUPPORT SYSTEMS 6

ET14-42 DELETED 7

1 WAS USED FOR So IN ET16 8.

SIMPLE LOGIC DEVELOPED FOR THE FOLLOWING EVENT TREE N0 DES (BYRON USED ZION QUANTITIES) TO REFLECT DEPENDENCY ON SUPPORT SYSTEMS:

SA2=SA1+HH2.

OP l = 0 P 1 -G U +P ORVT2 CCWOR V I N W + J U 51

• 1 D ) = ( PORV2HTFJB5T420).

J OP2=0P2-QD+0P2-QA*0P2-QR+HH2+0Pl.

7F3 = OP 3 - Q U '+ E 5 VKUTJB STUU+]B 51T20.

OP4=0P4-QD+JBS141D+9BS142D.

TP5-1=0P~5M ODTJB51+1D*7B5T4zo.

OPS-2=0P5-20D+JBS141D*JBS1420.

7PB;riiiUP3.

4 OP8-2=0P8-200+ESWAU+JBS141D*JBS1420 LK-T=LKTf0DTJB S1 TID *UR51T2D.

PR2=PR2-QD+JRS141D*dBS142D.

S 2 = S 2-Q A

• E S W A U + 5FG86TJB 5141 D + JII5TU D ) + 57 - o c.

QUANTiclCATION 1

THE SETS CODE WAS USED TO GENERATE AND QUANTIFY MINIMAL CUT SET EQUATIONS 2

A0T2 AND VERY SMALL CUT 0FF PROBABILITIES WERE USED TO MINIMIZE THE POSSIBILITY OF MAINTENANCE EVENTS BEING TRUNCATED BROOKHAVEN NATIONAL LABORATORY l)lyl A5500ATED UNIVERSITIES, INC.(1lll

3 DATA 1

INITIATOR FRE00ENCIES (EVENTS / YEAR)

INITIATOR GROUP #

INITIATOR 3YRON THIS STUDY j

1 LARGE LOCA 9 40(-4) 9 40(-4) 2 MEDIUM LOCA 9 40(-4)

9. 40(-4 )

3 SMALL LOCA 3 54(-2) 3 54(-2) 4 SG TUBE RUPTURE 3 70(-2) 3.70(-2) 5 STEAM BREAK INSIDE 9 40(-4) 9 40(-4) 4 CONTAINMENT 6

STEAM BREAK OUTSIDE 9 40(-4) 9 40(-4) l CONTAINMENT 7

LOSS OF MFW 3 00 3 00 8

CLOSURE OF MSIV 2.52(-1) 6 00(-1) 9 LOSS OF RCS FLOW 3 58(-1) 3 58(-1) 10 CORE POWER EXCURSION 2 28(-2) 2 28(-2) 11 TURBINE TRIP 4.00 4 00 12A LOSS'0F 0FFSITE POWER 5 76(-2) 9 10(-2) 13 SPURIOUS SAFETY INJECTION

8. 00 (-2 )

1 60(-1) 14 REACTOR TRIP 3.00 4 11 15 INTERFACING LOCA 2 10(-7) 7 80(-7)

(16)

ATWS 1 36(-5)

BROOKHAVEN NATIONAL LABORATORY l} ggl A5500ATED UNIVERSITIES, INC.(1 Ell

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BASIC EVENT DATA ZION PSS HARDWARE FAILURE DATA ZION PSS MAINTENANCE FREQUENCY EGRG COMMON CAUSE FAILURES SWAIN BOOK OPERATOR FAILURES NONREC0VERY OF 0FFSITE AND---ZION RESPONSE i

ONSITE POWERS TO BNL REVIEW i~

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RESULTS l

e A0T1:

TR = 19 HOURS A0T2:

TR = 168 HOURS e

8 CASES CASES A0T1 A0T2 1

ALL SYSTEMS NONE 2

NONE ALL SYSTEMS 3

ALL OTHERS DGs 4

ALL OTHERS ESW 5

ALL OTHERS CHRS (CF, CS) 6 ALL OTHERS CHo, SI 7

ALL OTHERS RHR 8

ALL OTHERS AFWS O

BROOKHAVEN NATIONAL LABORATORY l}l)l A5500ATED UNIVERSITIES, INC.(I Lll

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SYSTEM UNAVAILABILITIES i

LOSP NON LOSP A0T1 A0T2 SLOPE /HR

_ A0T1 A0T2 SLOPE /HR ESWS 1.08(-3) 4.66(-3) 2.40(-5) 2 98(-5) 1 47(-4) 7 87(-7)

AFWS 1 42(-3) 3 22(-3) 1.21(-5) 8.54(-4) 1.50(-3) 4 34(-6)

CS 1 71(-3) 5 24(-3) 2.37(-5) 5 58(-4) 7 27(-4) 1 13(-6)

CF 1.35(-3) 6.69(-3) 3 58(-5) 3 38(-5) 3 89(-4) 2 38(-6)

CCW(A) 1.20(-3) 4 86(-3) 2 46(-5) 5 49(-5) 1 73(-4) 7 93(-7)

CCW(B) 1 18(-3) 4 86(-3) 2 47(-5) 3 45(-5) 1 53(-4) 7.95(-7)

SIM(HH1) 1 40(-3) 6.11(-3) 3 16(-5) 3 50(-5) 1 74(-4 )

9 33(-7)

SIS (HH2) 1.08(-3) 4 66(-3) 2.40(-5) 2 98(-5) 1 47(-4) 7 87(-7)

LPI 1 1!

,e 4.19(-3) 2 01(-5) 2 35(-4) 2 69(-4) 2 28(-7)

R-1 2 01(-3) 3.38(-3) 9.19(-6) 1 68(-3) 1 88(-3) 1 34(-6)

R-2 8.83(-4) 1 88(-3) 6.69(-6) 5 02(-4) 6.43(-4) 9 46(-7) 1 I

BROOKHAVEN Nail 0NAL LABORATORY lg gyl A5500ATED UNIVERSITIES, INC.(IIll

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CORE DAMAGE FREQUENCY FROM ONE UNIT OPERATION QSE BYRON THIS STUDY i

S 1

1 41(-4) 1 24(-4) 4.19(-4) 2 2 63(-4) i 3

2 25(-4) 4 1 24(-4) 5 1.31(-4 )

6 1 31(-4) 7 1.50(-4) 8 9'

1 67(-4) 1 54(-4)

"ADT = 34 HOURS FOR ALL SYSTEMS I

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,______..m.,.__.--

AUG 2 01365 MEETING

SUMMARY

DISTRIBUTION "dDockEU' Nile' NRC Participants NRC PDR L PDR P. Baranowski NSIC A. Busiik PRC System S. Newberry LB#1 Reading File L. 01shan Project Manager L. Olshan G. L. Plumlee M. Rushbrook R. Robinson Attorney, OELD A. Spano R. Hartfield*

A. Thadani OPA*

OTHERS bec: Applicant & Service List

• Caseload Forecast Panel Visits

.