ML20147E850

Summary of Operating Reactors Events Meeting 97-02 on 970312.List of Attendees,Significant Elements of Discussed Events & Reactor Scram Statistics for Weeks Ending Feb 16, 23,Mar 2 & 9 Encl

ML20147E850
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	03/17/1997
From:	Chaffee A NRC (Affiliation Not Assigned)
To:	Martin T NRC (Affiliation Not Assigned)
References
OREM-97-002, OREM-97-2, NUDOCS 9703190253
Download: ML20147E850 (22)

Text

- - . . - . .

so March 17, 1997 6

5 MEMORANDUM T0: Thomas T. Martin. Director Division of Reactor Program Management FROM: Alfred E. Chaffee. Chief l Original signed byl Events Assessment and Generic Communications Branch Division of Reactor Program Management

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING MARCH 12, 1997 - BRIEFING 97-02 On March 12, 1997, we conducted an Operating Reactors Events Briefing (97-02) to inform senior managers from offices of the Commission. ACRS. AEOD NRR and regional offices of selected events that occurred since our last briefing on February 12, 1997. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events.

Attachment 3 contains reactor scram statistics for the weeks ending February 16. February 23. March 2. and March 9, 1997. No significant events were identified for input into the NRC Performance Indicator Program.

The statements contained in the attached briefing slides represent the best information currently available to the NRC. Future followup could produce new information that may alter the NRC's current view of the events discussed.

Attachments: As stated (3)  ;

cc w/atts:

See next page CONTACT: Kathy Gray. NRR (301) 415-1166 DISTRIBUTION: (w/atts)

< Central' Files '

PUBLIC LK11 gore. SECY f PECB R/F I KGray TKoshy

,g DOCUMENT NAME: G:\KAG\0RTRANS Ta receive a copy of this document, Indicate in the bos: "C' = Copy without attachment /encic% ire "E' = Copy with attachment / enclosure "N' = No copy OFFICE PECS ,pg lE PEC8 ,lC] PECB l C/PECB lN NAME KGray:1kd f)h TKoshy /rp EGoodwin (3 AChaffee y4V _

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S. Collins, NRR (0-12G18)

F. Miraglia, NRR (0-12G18) D. Skay, NRR (01301)

F. Gillespie, NRR (0-12G18) R. Capra, NRR (013D1)

R. Zinnerman, NRR (0-12G18)

A. Thadani, NRR (0-12G18)

B. Sheron, NRR (0-12G18)

S. Varga, NRR (0-14E4)

J. Zwolinski, NRR (0-14H3)

J. Roe, NRR (0-13E4)

E. Adensam, NRR (0-13E4)

G. Lainas, NRR (0-7D26)

G. Holahan, NRR (0-8E2)

D. O'Neal, NRR (0-10E4)

B. Boger, NRR (0-9E4)

M. Markley, ACRS (T-2E26)

C. Rossi, AE0D (T-4A9)

F. Congel, AEOD (T-4D28)

R. Barrett, AE00 (T-4A43)

S. Rubin, AE00 (T-4028)

M. Harper, AE00 (T-4A9)

W. Leschek, AE00 (T-4A9)

V. McCree, EDO (0-17G21)

J. Gilliland, PA (0-2G4)

D. Morrison, RES (T-10F12)

W. Hill, SECY (0-16G15)

H. Miller, Region I C. Hehl, Region I L. Reyes, Region II J. Johnson, Region II S. Vias, Region II A. Beach, Region III J. Caldwell, Region III E. Mershoff, Region IV A. Howell (Acting), Region IV K. Perkins, Region IV/WCF0 G. Fader, INP0 J. Zinner, DOE l_ _. _

s>Mtv 3 S UNITED STATES lo . ,j

'f NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2G5&M)001

%, * * * * * ,o March 17, 1997 MEMORANDUM T0: Thomas T. Martin, Director Division of Reactor Program Management FROM: Alfred E. Chaffee, Chief k ((' b Events Assessment and Generic Communications Branch Division of Reactor Program Management

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING MARCH 12, 1997 - BRIEFING 97-02 On March 12, 1997, we conducted an Operating Reactors Events Briefing (97-02) l to inform senior managers from offices of the Commission, ACRS, AE00, NRR and <

regional off:ces of selected events that occurred since our last briefing on l February 12, 1997. Attachment I lists the attendees. Attachment 2 presents l the significant elements of the discussed events. l Attachment 3 contains reactor scram statistics for the weeks ending i February 16, February 23, March 2, and March 9, 1997. No significant events I were identified for input into the NRC Performance Indicator Program.

The statements contained in the attached briefing slides represent the best information currently available to the NRC. Future followup could produce new i information that may alter the NRC's current view of the events discussed. l l

Attachments: As stated (3) cc w/atts:

See next page I CONTACT: Kathy Gray, NRR (301) 415-1166

LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (97-02)

MARCH 12. 1997 NAME OFFICE NAME OFFICE A. Chaffee NRR J. Rosenthal AE00 K. Gray NRR A. Hsia OCM-ND R. Dennig NRP C. Rossi AE00 E. Goodwin N' . . E. Collins DCM T. Koshy NRR M. Markley ACRS J. Munday NRR J. Carter NRR W. Burton NRR D. Lynch NRR R. Capra NRR E. Adensam NRR

, G. Galletti NRR TELEPHONE ATTENDANCE (AT ROLL CALL)

Reaions Resident Insoectors ,

Region II M. Miller. St. Lucie  !

Region III i Region IV l l

Misc. l M. Dapas. AIT Team Leader '

i ATTACHMENT 1 l

l

k i

j i OPERATING REACTORS EVENTS BRIEFING 97-02 l

LOCATION

0-10B11, WHITE FLINT l WEDNESDAY, MARCH 12, 1997 11:00 A.M.

t

) ZION, UNIT 1 IMPROPER CONTROL R0D MOVEMENT DURING SHUTDOWN (AIT)

J i

i i

PRESENTED BY:

EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH

DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR ATTACHMENT 2

97-02 ,

ZION UNIT 1 IMPROPER CONTROL R0D MOVEMENT DURING SHUTDOWN FEBRUARY 21, 1997 PROBLEM A REACTOR OPERATOR D10 NOT UNDERSTAND A STEP IN THE SHUTDOWN PROCEDURE AND CONTINUOUSLY INSERTED RODS INTO SHUTDOWN CONDITION. HE THEN CONTINUOUSLY WITHDREW RODS IN AN ATTEMPT TO RESTART THE REACTOR WITHOUT DIRECTION FROM SHIFT MANAGEMENT.

CAUSE e INADEQUATE COMMAND AND CONTROL IN THE CONTROL ROOM.

e SIGNIFICANT DEFICIENCY IN THE KNOWLEDGE OF REACTOR PHYSICS.

SAFETY SIGNIFICANCE UNCONTROLLED ADDITION OF REACTIVITY.

SEQUENCE OF EVENTS 2/19 1203 CONTAINMENT SPRAY PUMP DECLARED IN0PERABLE.

ENTERED TECH SPEC (TS).

L 2/21 0700 MAIN FOCUS OF SHIFT TURNOVER IS THE RESTORATION OF THE 1C CONTAINMENT SPRAY (CS) PUMP TO AVOID A REQUIRED SHUTDOWN OF UNIT 1.

L l CONTACTS: M. DAPAS, AIT TEAM LEADER AIT: YES T. K0 SHY, NRR/DRPM/PECB

REFERENCE:

10 CFR 50.72 #31828 SIGEVENT: TBD

ZION, UNIT 1 97-02 i

l 2/21 0930 PLANT MANAGEMENT REQUESTS THAT NUCLEAR 3

ENGINEERS AND OPERATIONS SUPERVISION i DISCUSS SHUTDOWN STRATEGY REGARDING THE USE l OF CONTROL RODS VERSUS B0 RATION, AND OTHER i

REACTIVITY CONCERNS.

i

i BRIEFING NOT CONDUCTED DUE TO LACK 0F

SUPPORT FROM SHIFT ENGINEER (SE) AND UNIT SUPERVISOR (US).

l 2/21 1100 INFORMAL DISCUSSION BETWEEN PLANT l MANAGEMENT AND OPERATIONS MANAGEMENT l REGARDING CS STATUS AND WHEN TO SHUTDOWN i UNIT 1. 1 o- INADEQUATE COMMUNICATIONS RESULTS IN DIFFERENT UNDERSTANDINGS OF WHEN TO ABANDON 1C CS PUMP i RESTORATION ATTEMPTS AND PLACE THE PLANT IN HOT SHUTDOWN.

2/21 1110 FORMAL SHUTDOWN BRIEFING CONDUCTED BY US. '

THIS BRIEFING FOCUSES ON THE REACTIVITY STRATEGY TO RETURN TO POWER.

2/21 1209 RAMPDOWN COMMENCES AT 0.25 PERCENT POWER PER MINUTE.

' ZION, UNIT 1 97-02 2/21 1255 LICENSEE IDENTIFIES THAT CS PUMP SHOULD HAVE BEEN DECLARED IN0PERABLE AT 10:20 A.M.

VS 10:40 A.M. ON FEBRUARY 19. CONSEQUENTLY PLANT SHUTDOWN REQUIRED BY TECH SPEC BY l 2:20 P.M. VS 2:40 P.M. RATE OF RAMP DOWN l INCREASED TO 0.53 PERCENT PER MINUTE BY 12:59 P.M.

l 2/21 UNIT 1 AT 7 PERCENT POWER. i l PRIOR TO 1407 SE DIRECTS US TO MAINTAIN THE REACTOR I CRITICAL DUE TO THE EXPECTED RETURN OF THE

1C CS PUMP.

US READS STEP REGARDING ESTABLISHING POWER

! AT OR BELOW THE POINT OF ADDING HEAT ALOUD '

l TO THE NUCLEAR STATION OPERATOR (NS0) AND REQUESTS THAT THE NSO IDENTIFY .025 PERCENT POWER ON THE INTERMEDIATE RANGE POWER METER.

l l

NSO ASKS US IF HE WANTS HIM TO DRIVE RODS IN. US PROVIDES NO CLEAR ANSWER TO NSO, I BUT MERELY RE-READS THE STEP FOR ESTABLISHING POWER AT OR BELOW THE POINT OF ADDING HEAT.

l 2/21 1407 OPERATOR TRIPS TURBINE IN ACCORDANCE WITH l GOP-4.

ZION, UNIT 1 97-02 l

l US READS STEP ALOUD REGARDING ESTABLISHING POWER AT THE POINT OF ADDING HEAT. NS0 ACKNOWLEDGES US AND INITIATES CONTINU0US CONTROL R0D BANK "D" INSERTION.

QUALIFIED NUCLEAR ENGINEER (QNE) OBSERVES CONTROL BANK "C" INSERTION INDICATION (DUE j TO BANK OVERLAP) AS EXPECTED DURING A

NORMAL SHUTDOWN.

I QNE APPROACHES NSO, AND INDICATES THAT THE j REACTOR IS SUBSTANTIALLY SUB-CRITICAL.

NS0 INFORMS QNE THAT HE-IS FOLLOWING PROCEDURE.  !

NSO CONTINUES CONTINUOUS CONTROL R0D l

INSERTION.

l 2/21 1411 NSO HALTS CONTINU0US CONTROL R00 INSERTION

! AFTER 3 MINUTES AND 48 SECONDS WHEN INTERMEDIATE RANGE POWER INDICATES .025 PERCENT. (INSERTED 232 STEPS) 2/21 1412 NS0 OBSERVES THAT POWER HAS DROPPED TO .01 PERCENT (DUE TO SUBSTANTIAL NEGATIVE l REACTIVITY ADDITION) AND INFORMS US THAT HE l INTENDS TO WITHDRAW RODS TO STABILIZE POWER

! AT .025 PERCENT.

ZION, UNIT 1 97-02 US ACKNOWLEDGES NSO.

NS0 INITIATES CONTINU0US CONTROL R0D WITHDRAWAL. (PULLED 82 STEPS)

QNE OBSERVES NS0'S ACTIONS, BECOMES CONCERNED WITH EXCESSIVE R0D WITHDRAWAL AND TELLS NSO THAT HE DOES NOT LIKE WHAT NS0 IS DOING. THE NSO RESPONDS THAT HE IS NOT COMFORTABLE WITH WHAT HE IS DOING AS WELL.

SE APPROACHES QNE AND QNE INFORMS SE THAT HE IS DISTURBED BY "DOWN AND UP R0D MOVEMENT".

SE DOES NOT UNDERSTAND RELEVANCE AND WALKS i AWAY FROM QNE.

2/21 1414 SE DIRECTS US TO TRIP THE REACTOR DUE TO IMMINENT EXPIRATION OF TS LC0 ACTION

STATEMENT.

2/21 1415 NSO MANUALLY TRIPS UNIT 1 PLACING THE UNIT IN HOT SHUTDOWN AS REQUIRED BY TS ACTION STATEMENT.

2/21 1508 QNE AND LEAD NUCLEAR ENGINEER (LNE) DISCUSS CONCERNS REGARDING CONTROL R0D MANIPULATIONS WITH SE.

j.

i. ,

~

i ZION, UNIT 1 97-02 SE UNAWARE THAT THE REACTOR HAD BEEN SHUTDOWN AND THE CREW HAD ATTEMPTED TO l RESTART THE REACTOR.

l NUCLEAR ENGINEERS DIRECTED TO DISCUSS THE l ISSUE WITH THE US, NSO, AND ASSISTANT

OPERATIONS MANAGER. US AND NSO. FAIL TO UNDERSTAND SIGNIFICANCE OF EVENT.  !

[

! 2/21 ~1800 NUCLEAR ENGINEERS DISCUSS THEIR CONCERNS l REGARDING R0D MOVEMENT WITH SENIOR

! OPERATIONS MANAGEMENT.

l l l 2/22 ~0930 PLANT MANAGER BECOMES AWARE OF THE ACTUAL l l SIGNIFICANCE OF THE EVENT. SENIOR l MANAGEMENT WAS INFORMED AND THE CREW WAS

! TAKEN OFF SHIFT.  !

! PRELIMINARY AIT FINDINGS

! e LACK 0F COGNIZANCE BY OPERATIONS MANAGEMENT i l -

NS0 ACTION TO CONTINU0USLY WITHDRAW RODS l -

SE AND US NOT COGNIZANT OF THE EXTENT OF R0D

MANIPULATION i

i

! e CONTROL ROOM DISTRACTIONS 39 PEOPLE IN CONTROL ROOM ENVELOPE INCLUDING 15 IN j THE VICINITY OF NSO & US OPERATING STATIONS DURING j 8 MINUTES BETWEEN TRIPPING TURBINE AND REACTOR j -

US AND SE T00 INVOLVED IN CS PUMP REC 0VERY EFFORTS i -

"SAVE THE UNIT" MIND-SET IMPACT SE FOCUS

l ZION, UNIT 1 97-02 e SPECIFIC CONTROL ROOM COMMUNICATION DEFICIENCIES DURING THIS EVENT FORMAL SHUTDOWN BRIEFING FAILED TO FOCUS ON CONTROLLED SHUTDOWN 15 MINUTES BEFORE REQUIRED SHUTDOWN SE DIRECTED US TO KEEP REACTOR CRITICAL. SE DID NOT INFORM ENTIRE CREW 0F INTEND TO KEEP REACTOR CRITICAL FAILURE OF US TO CLARIFY CRITICAL STEP IN SHUTDOWN l PROCEDURE QNE FAILED TO ADEQUATELY COMMUNICATE HIS CONCERNS REGARDING R0D MANIPULATIONS BY NSO TO US AND SE INAPPROPRIATE RESPONSE TO ROD INSERTION LIMIT ALARM e INEFFECTIVE INFORMATION FLOW TO PLANT MANAGEMENT l -

QNE AND HIS SUPERVISOR RECOGNIZED THE PROBLEM ON l AFTERN0ON OF FEBRUARY 21; ATTEMPT TO G0 FROM SUBCRITICAL TO CRITICAL NOT DISCUSSED WITH PLANT MANAGER ON FEBRUARY 21.

OPERATIONS MANAGEMENT FAILED TO RECOGNIZE THE SIGNIFICANCE OF THE NSO ACTIONS. OPERATIONS MANAGEMENT RETURNED STAFF TO LICENSED DUTIES WITHOUT SENIOR MANAGEMENT CONSULTATION.

1 I e OPERATOR TRAINING DEFICIENCIES POINT OF ADDING HEAT ONLY ADDRESSED IN INITIAL TRAINING l NORMAL SHUTDOWN NOT DONE IN REQUALIFICATION l

NS0'S LACK OF KNOWLEDGE IN REACTOR PHYSICS THAT RESULTED IN CONTINU0US INSERTION OF 232 STEPS AND WITHDRAWAL OF 82 STEPS.

ZION, UNIT 1 97-02 e RELATED HISTORIC EVENTS AT ZION INSPECTION REPORT ISSUED ON APRIL 8, 1996 ADDRESSED i INADVERTENT MODE CHANGE IN JANUARY FROM COLD WATER ADDITION FEBRUARY 28, 1996 NUCLEAR ENGINEERING REPORT ON l ADVERSE TREND IN REACTIVITY MANAGEMENT VIOLATIONS ISSUED ON JANUARY 28, 1997 FOR INAPPROPRIATE lt0D WITHDRAWAL IN SEPTEMBER 1996

DURING START UP FOLLOW UP

! o CONDUCTED AN AIT INSPECTION WITH NRR AND TRAINING

. CENTER PARTICIPATION. CONCLUDED WITH A PUBLIC EXIT ON MARCH 7, 1997 -

o PECB WILL EVALUATE GENERIC IMPLICATIONS FROM THE AIT I FINDINGS.

! RELATED GENERIC COMMUNICATIONS o IN 92-39: UNPLANNED RETURN TO CRITICALITY DURING i REACTOR SHUTDOWN o IN 94-90: TRANSIENT RESULTING IN A REACTOR TRIP AND MULTIPLE SAFETY INJECTION SYSTEM ACTUATIONS AT SALEM

REACTOR SCRAM Reporting Period: 03/03/97 to 03/09/97 YTD YTD ABOVE BELOW YTD E.A.li PLANT & UNIT POWER JIP{ CAU$t COMPLICAfl0NS M M TOTAL 03/03/97 TURKEY PolNT 3 0 SM Equipment Falture NO 0 1 1 03/04/97 SAINT LUCIE 1 100 SA Other NO 1 0 1 03/06/97 WATTS BAR 1 100 SA Equipnent Failure No 2 0 2 ,

1 03/09/97 PEACH BOTTOM 3 14 SM Maintr--nce Error No 0 1 1 l

l 1

l l

1 l

l l

I l

l t

Note: Year To Date (YTD) Totals include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period ETS 10 Page:1 03/17/97 Attachment 3

.- .~ . . . . . . . . - . - . - - . . - . - .~ - ._ .. .. _ . ~ . . - _ . - . . . . . . .

. , ~ . _ _ . . . ..

i l .

4 e

j COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 03/09/97 l .

1996 1995 1994 1993

)

• NUMBER 1997 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEK'.Y 4 SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YtD)

~ POWER GREATER THAN OR EQUAL To 15%

i EQUIPMENT FAILURE 1 0.51 1.52 1.83 1.52 1.83 DESIGN /INSTALLAfl0N ERROR 0 0.10 0.10 0.12 0.08 0.04 OPERAflNG ERROR 0 0.10 0.08 0.15 0.21 0.27 MAINTENANCE ERROR 0 0.21 0.50 0.38 0.54 0.52

EXTERNAL 0 0.10 0.13 0.21 -0.17 0.13 I

OTHER 1 0.10 0.10 0.06 - 0.02-E Subtotal 2 1.12 2.43 2.75 2.52 2.81 1

a A

POWER LESS THAN 1**.

4 EQUIPMENT FAILURE 1 0.21 '0.23 0.10 0.27 0.38 l DESIGN / INSTALLATION ERROR 0 0.00 - -

0.02 -

OPERAf!NG ERROR 0 0.00 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 1 0.10 0.06 ,0.08 -

0.02 4 EXTERNAL 0 0.00 - - -

0.04 OTHER 0 0.00 - - - -

)

Subtotal 2 0.31 0.39 0.31 0.37 0.57 i l

TOTAL 4 1.43 2.32 3.06 2.89 3.38 i

i I 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE j (YTD)

TOTAL 4 WATIC SCRAMS 2 0.72 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRAMS 2 0.72 1.10 1.13 0.69 0.94 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF E7$ 14 Page: 1 03/17/97

, i 1

REACTOR SCRAM

$ Reporting Period: 02/24/97 to 03/02/97 YTD YTD A80VE BELOW YTD M PLANT & UNIT POWE2 M CAUSE COMPLICATIONS jj} jj} TOTAL 02/25/97 SUSQUEHANNA 1 64 SM Maintenance Error NO 1 0 1 l

1 hoto: Vear To Date (YTD) Totals include Events Within The Calendar Year Indicated By The Eni Date Of The Specified Reporting Period ETS-10 Page:1 03/10/97

_ .. . . . _.,...__.m_.._ - - - _ . _ . _ . _ _ . _ _ . . _ . _ . ~ . - _ ..

. COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 03/02/97 NUM8ER 1997 1996 1995 1994 1993 i l OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY j- SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERA(.E AVERAGE (YTD)

POWCR GREATER THAN OR EQUAL 70 15%

e ,

EQUIPMENT FAILURE O 0.46 1.52 1.83 1.52 1.83

{ DESIGN / INSTALLATION ERROR 0 0.11 0.10 0.12 0.08 0.04

OPERATING ERROR 0 0.11 0.08 0.15 0.21 0.27 i MAINTENANCE ERROR 1 0.23 0.50 0.38 0.54 0.52 l EXTERNAL 0 0.11 0.13 0.21 0.17 0.13 OTHER 0 0.00 0.10 0.06 -

0.02

. \

, subtotal 1 1.02 2.43 2.75 2.52 2.81 j POWER LESS THAN 15%

EQUIPMENT FAILURE 0.11 0.23 0.10 0.27 0.38 f O DESIGN / INSTALLATION fRROR 0- 0.00 - - 0.02 -

OPERATING ERROR 0 0.00 0.10 0.13 0.08 0.13 j MAINTENANCE ERROR 0 0.00 0.06 0.08 -

0.02 EXTERNAL 0 0.00 - - -

0.04 l

, OTHER 0 0.00 - - -

• f subtotal 0 0.11 0.39 0.31 0.37 0.57 l

i TOTAL 1 1.13 2.82 3.06 2.89 3.38 1

4

! 1997 1996 1995 1994 1993 q NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE g

(YTD) i 4 ,

TOTAL AUTOMATIC SCRAMS 0 0.57 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRANS 1 0.57 1.10 1.13 0.69 0.94 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF ETS 16 Page: 1 03/10/97

REACTOR SCRAM Reporting Period: 02/17/97 to 02/23/97 YTD YTD ABOVE BELOW YTD 9A.Il PLANT & ft , POWER TY,P1 CAUSE COMPLICAff0NS 15% 15% TOTAL 02/18/97 SURRY 2 90 SM Equipnent f ailure NO 1 0 1 02/19/97 SURRY 1 55 SM Equipnent Failure NO 1 0 1 l

l l

l l

l l

.h Rots: Ysar To Date (YTD) Totals include Events Within The talendar Year Indicated By The End Date of The Specified Reporting Period ETS 10 Page:1 03/10/97

l l

l .. COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES j PER100 ENDING 02/23/97 l NUM8ER 1997 1996 1995 1994 1993

! 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAQ}{ SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE-(YTD)

POWER GREATER THAN OR EQUAL TO 15%

EQUIPMENT FAILURE 2 0.52 1.52 1.83 1.52 1.83 l DESIGN /INSTALLAT10N ERROR 0 0.13 0.10 0.12 0.08 0.04 OPERATING ERROR 0 0.13 0.08 0.15 0.21 0.27 MAINTENANCE ERROR 0 0.13 0.50 0.38 0.54 0.52 EXTERNAL 0 0.13 0.13 0.21 0.17 0.13 l OTHER 0 0.00 0.10 0.06 -

0.02 l' Subtotal 2 1.04 2.43 2.75 2.52 2.81 POWER LESS THAN 15%

EQUIPMENT FAILURE O 0.13 0.2? 0.10 0.27 0.38 DES!GN/ INSTALLATION ERROR 0 0.00 - -

0.02 -

OPERATING ERROR 0 0.00 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 0 0.00 0.06 0.08 - 0.02 EXTERNAL 0 0.00 - - - 0.04 OTHER 0 0.00 - - - -

Subtotal 0 0.13 0.39 0.31 0.37 0.57 TOTAL 2 1.17 2.82 3.06 2.89 3.38 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERACE AVERAGE AVERAGE AVERAGE (YTD)

TOTAL AUTOMATIC SCRAMS 0 0.65 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRAMS 2 0.52 1.10 1.13 0.69 0.94 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF 1

l i

i i

.ETS.14 Page: 1 03/10/97

i 1

i e i

. REACTOR SCRAM l

Reporting Period: 02/10/97 to 02/16/97 YTD YTD ABOVE BELOW YTD ELII PLANT & UNIT POWER l!P1 [A!!!{ COMPLICATIONS 15% 15% TOTAL q l

02/15/97 PILGRIM 1 20 SM Equipnent Failure NO 1 0 1 l l

ote: Year To Date (YTD) Totals include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period Page:1 03/10/97 ETS-10

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

(-

I

• e COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 02/16/97 WUM8ER 1997 1996 1995 1994 1993 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE' SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) l POWER GREATER THAN OR EQUAL TO 15%

EQUIPMENT FAILURE 1 0.30 1.52 1.83 1.52 1.83 f DESIGN / INSTALLATION ERROR 0 0.15 0.10 0.12 0.08 0.04 OPERATING ERROR 0 0.15 0.08 0.15 0.21 0.27 MAINTENANCE ERROR 0 0.15 0.50 0.38 0.54 0.52 EXTERNAL 0 0.15 0.13 0.21 0.17 0.13 OTHER 0 0.00 0.10 0.06 - 0.02 Setotal 1 0.90 2.43 2.75 2.52 2.81 POWER LESS THAN 15%

EQUIPMENT FAILURE 0 0.15 0.23 0.10 0.27 0.38 DESIGN / INSTALLATION ERROR 0 0.00 - - 0.02 -

OPERATING ERROR 0 0.00 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 0 0.00 0.06 0.08 -

0.02 EXTERNAL 0 0.00 . - -

0.04 OTHER 0 0.00 - - - -

Subtotal 0 0.15 0.39 0.31 0.37 0.57 TOTAL i 1.05 2.82 3.06 2.89 3.38 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

TOTAL AUTOMATIC SCRAMS 0 0.74 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRAMS 1 0.30 1.10 1.13 0.69 0.94 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF l

l l

[

i ETS 14 Page: 1 03/10/97 i.

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A f*.

' NOTES

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 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.

i

} ' 2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL' DEFICIENCIES, j AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

1

" 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL

ERRORS UNRELATED TO CAUSE OF SCRAM.

4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES i (LIGHTNING), SYSTEM DESIGN, OR UNKNObi CAUSE.

t j OEAB SCRAM DATA l Manual and Automatic Scrams for 1987 ------------------ 435 i Manual and Automatic Scrams for 1988 -------------------291 Manual and Automatic Scrams for 1989 ------------------ 252 Manual ~and Automatic Scrams for 1990 ------------------ 226

-Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175 Manual and Automatic Scrams for 1994 ------------------ 150 Manual and Automatic Scrams for 1995 ------------------ 159 Manual and Automatic Scrams for 1996 ------------------ 146 Manual and Automatic Scrams for 1997 --(YTD 03/09/97)-- 14