ML20057A618

Summary of Operating Reactors Events Meeting 93-32 on 930825

ML20057A618
Person / Time
Site:	Palisades
Issue date:	08/30/1993
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
IEIN-87-043, IEIN-87-43, IEIN-91-021, IEIN-91-21, IEIN-92-021, IEIN-92-21, OREM-93-032, OREM-93-32, NUDOCS 9309150050
Download: ML20057A618 (11)

Text

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i August 30, 1993  !

MEMORANDUM FOR: Brian K. Grimes, Director I Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING

. AUGUST 25, 1993 - BRIEFING 93-32

'h on August 25, 1993, we conducted an Operating Reactors Esants

. Briefing (93-32) to inform senior managers fron offices of the

' Chairman, EDO, NRR, ACRS, SECI, AFOD, RES, and regional offices ,

of selected events that occurred since our last briefing on August 18, 1993. Enclosure 1 lists the attendees. Enclosure 2

- presents the significant elements of the discussed events.  !

Enclosure 3 contains reactor scram statistics for the week ending l August 22, 1993. No significant events were identified for input l i into the NRC Performance Indicator Program.

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t l [ original signed by] l 4

3 Alfred E. Chaffee, Chief 5

Events Assessnent Branch i

j. Division of Operating }

Reactor Support  ;

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Enclosures:

As stated DISTh'TJ TTON:  !

, 1Centralef.les s  ;

cc w/ enclosures: PDR  !

See next page LKilgore, SECY ,

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08/1/93 08/g/93 08/30/93 i OFFICIAL RECORD COPY _ / if.- y 3 b- f ( pcr bVf l DOCUMENT NAME: ORTRANS.KAG (G:\KAG) ( ((c 7j ,A &

4 JJ S ) i 9309150050 930830 I PDR DRO NRRB PDR ( i

_ . - - ~ _ - _ . -

• CC*

T. Murley, NRR (12G18) A. Hsia (PDIII-1)

F. Miraglia, NRR (12G18) T. Marsh (PDIII-2)

F. Gillespie, NRR (12G18) il J. Partlow, NRR (12G18)

S. Varga, NRR (14E4)

J. Calvo, NRR (14A4)

G. Lainas, NRR (14H3)

J. Roe, NRR (13E4)

J. Zwolinski, NRR (13H24)

E. Adensam, NRR (13E4)

W. Russell, NRR (12G18)

J. Wiggins, NRR (7D26)

A. Thadani, NRR (BE2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR (10H3)

F. Congel, NRR (10E2)

D. Crutchfield, NRR (11H21)

W. Travers, NRR (11B19)

D. Coe, ACRS (P-315)

E. Jordan, AEOD (MN-3701)

G. Holahan, AEOD (MN-9112)

L. Spessard, AEOD (MN-3701)

K. Brockman, AEOD (MN-3206)

S. Rubin, AEOD (MN-5219)

M. Harper, AEOD (MN-9112)

G. Grant, EDO (17G21)

R. Newlin, GPA (2G5)

E. Beckjord, RES (NLS-007)

A. Bates, SECY (16G15)

T. Martin, Region I W. Kane, Region I R. Cooper, Region I S. Erneter, Region II E. Merschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV B. Faulkenberry, Region V K. Perkins, Region V bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957

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....." August 30, 1993 MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING AUGUST 25, 1993 - BRIEFING 93-32 On August 25, 1993, we conducted an Operating Reactors Events Briefing (93-32) to inform senior managers from offices of the Chairman, EDO, NRR, ACRS, SECY, AEOD, RES, and regional offices of selected events that occurred since our last briefing on August 18, 1993. Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains reactor ceram statistics for the week ending August 22, 1993. No significant events were identified for input into the NRC Performance Indicator Program.

-(

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

Enclosures:

As stated cc w/ enclosures:

See next page

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- ENCLOSURE I )

LIST OF ATTENDEES  ;

OPERATING REACTORS EVENTS FULL BRIEFING (93-32) ,

s AUGUST 25, 1993 i

NAME OFFICl; NAME OFFICE [

I y

A. CHAFFEE NRR V. HODGE NRR E. BENNER NRR B. BOGER NRR f 4 K. GRAY NRR J. ZWOLINSKI NRR l S. BROWN NRR R. JONES NRR i T. KOSHY NRR W. JONES AEOD  :

L. PHILLIPS NRR R. SHEMBARGER OCM/IS  ;

L. KOPP NRR A. GODY, JR. OEDO l W. DEAN NRR D. COE ACRS -

, M. GAMBERONI NRR K. HART SECY l J. LENNARTZ NRR W. MINNERS RES  !

! T. YAMADA NRR l i i I

i i TELEPHONE ATTENDANCE j

=

(AT ROLL CALL) r

! Eenions Resident Inspectors  !

Region I Palisades, SRI i

! Region II

Region III Region IV Region V I

IIT/AIT Tean Leaders Misc.

Edward Schweibinz, Region III  ;

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ENCLOSURE 2

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OPERATING REACTORS EVENTS BRIEFING 93-32 LOCATION: 10 B11, WHITE FLINT WEDNESDAY, AUGUST 25, 1993, 11:00 A.M.  ;

PALISADES LOSS OF SPENT FUEL P0OL NEUTRON ABSORBER MATERIAL 1

INVENTORY i

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PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR t

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93-32

j. PALISADES LOSS OF SPENT FUEL P00L NEUTRON ABSORBER MATERIAL Il1 VENT 0RY AUGUST 19, 1993 PROBLEM

. SURVEILLANCE OF SPENT FUEL P0OL (SFP) l1EUTRON ABSORBER MATERIAL INVENTORY INDICATED SOME MATERIAL IS MISSING.

CAUSE

. CURRENTLY UNKNOWN. ,

f SAFETY SIGNIFICANCE I POTEllTIAL FOR CRITICALITY ACCIDENT IN SFP.

SEQUENCE OF EVENTS j e PALISADES HAS HIGH-DENSITY STORAGE RACKS IN SFP WHICH INCORPORATE BORON-IMPREGNATED POLYMER SHEETS WITHIN 1 IllDIVIDUAL STORAGE CELL WALLS FOR NEUTR0t1 ABSORPTION.

l e RACKS SUPPLIED BY WESTINGHOUSE WITH PROPRIETARY NEUTRON i ABSORPTI011 MATERIAL (BORAFLEX) MADE BY BRAND INDUSTRIAL s SERVICES, INC. (BISCO).

l o FULL-LEl1GTH COUPON REMOVED F'>0M FUEL RACKS Oli

AUGUST 17, 1993, AS PART OF FIRST 5-YEAR SURVEILLANCE OF BORAFLEX CONTENT. INSPECTION OF COUPON REVEALED i MOST (85-90%) 0F BORAFLEX INVENTORY MISSING.

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CONTACT: E. bel 1NER, NRR/0EAB AIT: R0 j

REFERENCES:

10 CFR 50.72 #25952 SIGEVENT: TBD j AND MORNING REPORT DATED 08/20/93 i

= - - - - - - - - - , n, n - , , ,- -, , . , , . , . , . ,a,---.e-,

PALISADES 93-32 o THREE ADDITIONAL FULL-LENGTH COUPONS INSPECTED ON AUGUST 19, 1993: FOUND ALL THREE MISSING 40-50% OF BORAFLEX INVENTORY.

o ONE OF TWO HALF-LENGTH COUPONS INSPECTED: FOUND ALL BORAFLEX INTACT.

DISCUSSION o KNOWN CONTRIBUTORS TO BORAFLEX DEGRADATION:

NEUTRON FLUX - DEPLETION OF IMPREGNATED BORON t GAMMA FLUX - CHANGES IN MATERIAL CHARACTERISTICS OF BASE POLYMER INCLUDING HARDENING / EMBRITTLEMENT

/ SHRINKAGE / SOFTENING?)

CHEMICAL EXPOSURE - SFP BORIC ACID ENVIRONMENT MAY LEAD TO EDGE DETERIORATION / EROSION I

e DARK, CLOUDY MATERIAL OBSERVED SPILLING OUT OF SIDES AND BOTTOM OF FULL LENGTH COUPONS DURING REMOVAL.

o THE FOUR FULL-LENGTH COUPONS WERE OF THE SAME BORAFLEX MANUFACTURING LOT: THE HALF-LENGTH COUPON WAS FROM A DIFFERENT MANUFACTURING LOT.

o LICENSEE CRITICALITY ANALYSIS INDICATES MAXIMUM ACHIEVABLE K. OF 0.98 (ASSUMING LOSS OF ALL BORON  ;

POIS0N AND ALL BORAFLEX). CALCULATED K err IS 0.96-0.98.

DESIGN BASIS IS tK,r s 0.95. I o TECHNICAL SPECIFICATION MINIMUM ALLOWED BORON CONCENTRATION IS 1720 PPM. LICENSEE ADMINISTRATIVE CONTROLS REQUIRE z 1800 PPM. CURRENT BORON l CONCENTRATION IS BEING MAINTAINED AT 2 2000 PPM. l l

l

PALISADES 93-32 o LICENSEE IS MONITORING BORON CONCENTRATION DAILY AND HAS TAKEN STEPS TO MINIMIZE POTENTIAL FOR BORON DILUTION ACCIDENT.

l o LICENSEE HAS NOTIFIED WESTINGHOUSE, INPO, AND SOME OTHER NUCLEAR FACILITIES WITH BORAFLEX FUEL RACKS.

l FOLLOWUP o VENDOR INSPECTION BRANCH HAS BEEN INFORMED AND HAS FORWARDED THE PART 21 REVIEW TO THE REACTOR SYSTEMS BRANCH.

o NRC INFORMATION NOTICE 87-43 AND REGION I TECHNICAL ISSUE

SUMMARY

91-21 REPORTED ON GAPS AND DEGRADATION FOUND IN BORAFLEX MATERIAL. l o REGION III HAS PREPARED A TECHNICAL ISSUE

SUMMARY

AND IS PREPARING EITHER A SUPPLEMENT TO INFORMATION NOTICE 1

87-43 OR A SEPARATE INFORMATION NOTICE.

o INFORMATION NOTICE 92-21 AND SUPPLEMENT 1 DISCUSS PREVIOUS ERRORS MADE IN SFP REACTIVITY CALCULATIONS. .

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BRIEFING 93-32 PALISADES o

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ENCLOSURE 3 i 4

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itEAC10R SCRAM Sep:rting Period: 08/16/93 to 08/22/93 ,

i YtD YTD ABOVE SELOW YTD g

• FtantT & t% f T PO To M CAUSE CCMPL I C AT IOM 2 M TCTAL 0B/16/93 TUSKEY 00th1 4 15 sA Operating Error No 2 0 2 j i

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I hete: Year To Date (Y1D) totals include Events Within The Cate-dar teer 1rdicated By The Erd Date of the specified Reporting Feriod Fage:1  !

[ig.10 1

___. _ _ _ - _ . ____ _ . _...._______.m m- . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . . . . _ . _

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r CCer AR150N 07 btErLY SCR Aw 51 All513CE WITH I C USTRY AvfRA0Es FERIOD 1 0 160 ,

08/22/93 kJwi E R 1993 1992 1991* 1990* 1989* .

OF WE f t L Y WE E KL Y WEEKLY WEEKLY VtfALY SCE*w CAut.[ 50RA*S AVE k a 0E *VERAGE hT E ALE A VE R ACE AVE R AGE (YTC) ,

power LREAlfR THAh OR E Q.;AL 10 151 (OU1PwEh1 f AILUGE' O 1.8 2.6 2.9 3.4 3.1 {

t E 51 Lh /1 h5t AL L AT 10h E R R DE

• 0 0.1 - - - -

! 0;f RAlthG Enoe 1 0.3 0.2 0.6 0.5 1.0 l PalkithAktE (FROR* 0 0.6 0.4 - - -

f f EWTERhAL* O 0.1 - -

! DTFER* O 0.0 0.2 - -

0.1 i

2.9 3.4 3.5 3.9 4.2 +

Lattetal 1

)

1 1 ro.'ta (155 T*Ah 15%

4 tcu1r*Eh1 FAltukt* 0 0.4 0.4 0.3 C.4 0.3 tts1Gk/ths ALLAT!ch ERROE' O 0.0 - - - -

l '

Or ts ATik; [R&DE' O 0.2 0.1 0.2 0.1 0.3

] i P.Alh1EkAhE 1RROR* O 0.0 0.1 - - -

!. I l [XTEFhAL* O 0.0 - - - -

CT bE R* 0 0.0 0.1 - - -

l l Subtetet 0 0.6 0.7 0.5 0.5 0.6

} TOTAL 1 3,5 4.1 4.0 4.4 4.8 j t

}

I 1993 1992 1991 1990 1989 l

i kD. Or WitLY VEEKLY WE E K L Y WEELY WEEKLY I f

f l $Cpsw 13P[ 50 Raws AVE R A0E A VE R A CE AvtRAGE A VE R AGE AVERACE  ;

(YTC)

I

( 101AL AUTOW.ATIC StRA*S 1 2.5 3.1 3.3 3.2 3.9 l

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TOTAL MAwuAL SCRAM 5 0 1.0 1.0 0.7 1.2 0.9 >

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j 101ALS MAY DlfFER EECAUSE OF RWClk; OF F {

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• Detailed breakdo.m nct in database f or 1991 ard earlier  ;

- EK!ERAAL ceae included in t001PMIhT F AILURE  !

- m.Ath1Eksh;f ERROR ard DIS!LN/lkSTALLAT10h ERROR causes included in OPERAYING ERRDR

- OTHER c asse included in (QU10MEhi 8 ALLURE 1991 e d 1990  ;

d 1 r 115 14 repe: 1 O!/24/93 v .v vr- m y --- T-irr--y v -,-t--m- w yw -w,e-- w a ,.as,m s,

4 FOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE l' WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD j MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

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2. PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

I 3 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES

(LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

OEAB SCRAM DATA l

l Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrans for 1988 ------------------ 291

Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrans for 1990 ------------------ 226 i Manual and Automatic Scrans for 1991 ------------------ 206 4

Manual and Automatic Scrams for 1992 ------------------ 212 -

1 Manual and Autonatic Scrans for 1993 --(YTD 08/22/93)-- 118 1 .

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