ML20235Z589

Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl

ML20235Z589
Person / Time
Site:	Dresden, Byron, Turkey Point, 05000000, Fort Saint Vrain
Issue date:	10/08/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-87-034, OREM-87-34, NUDOCS 8710210213
Download: ML20235Z589 (23)

Text

- __ __

gM RIG Oq[g UNITED STATES

[d 'g NUCLEAR REGULATORY COMMISSION

,. 5 :j WASHINGTON, D. C. 20555 l

OCT # 8 gy MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment l

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING  ;

OCTOBER 6,1987 - MEETING 87-34 On October 6, 1987 an Operating Reactors Events meeting (87-34) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events KSich occurred since our last meeting on September 29, 1987. The list of.

attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 provides a summary of reactor scrams and a com-parison of this week's statistics with industry averages. There were two significant events identified for input to NR,'s performance indicator program.

hv Way$eLanning,' Chief Events Assessment Branch Division of Operationa vents Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page l

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f4EMORANDUtt FOR: Charles E. Rossi, Director Division of Operational Events Assessment-FROM: Wayne Lanning, Chief Events Assessment Branch' Division of Operational Events' Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING -

OCTOBER 6,1987 - MEETING 87-34 ,

)

On October 6, 1967 an Operating Reactors Events meeting (87-34) was held to ,

brief senior managers from NRR, RES, AEOD and Regional Offices on events 1 which occurred since our last meeting on' September 29, 1987. The list of n attendees is included as Enclosure 1.  ;

ihe events discussed and the significant elements of these events are presented  !

in Enclosure 2. Enclosure 3 provides a summary of reactor scrams and i a comparison of this week's statistics with industry averages._ There were no i significant events identified for. input to NRC's performance indicator program. j The events discussed and the significant elements of these events are presented  !

in Enclosure 2. Enclosure 3 provides a summary of reactor' scrams and a com- I parison of this week's statistics with industry averages. There were two-significant events identified for input to NRC's performance indicator program.

Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION Centra M 11e NRC PDR EAB Rdg NFields R/F EAB Members

}fb k  ::C:EAB RR 0FC :EAB:NRR  :  :  :  :

'NAME :MLReardon  ::W ilm( :  :  :  :

DATE 10/S 7/87 :10//#/87  :  :  :  :  :

--_______MRMRGLM M MOL U

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T. Murley . K. Heitner .l J. Sniezek E. Tomlinson- i

F. Miraglia-L. 01shan R. Starostecki J..Stevens '

i E. Jordan- M. Grotenhuis J. Taylor. -

T..Ross E. Beckjord. . D. Mcdonald W. Russell, Reg. I 'E..Tourigny 1 J. Nelson Grace, Reg. II- J. Calvo B. Davis, Reg. III D. Muller R. D. Martin, Reg. IVL L. Rubenstein

- J. B. Martin, Reg. V W. Kane, Reg. I.

L. Reyes, Reg. II C. Norelius, Reg. III

, R. Hall, Reg. IV l D. Kirsch, Reg. V S. Varga i D. Crutchfield  !

B. Boger G. Lainas 1

G. Holahan F. Schroeder L. Shao l J. Partlow B. Grimes F. Congel E. Weiss l S. Black ,

l T. Martin, EDO j E. Herschoff l R. Hernan .;

H. Bailey "

J. Guttmann 1

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-33)

September 29, 1987 NAME ORGANIZATION R T Starostecki NRR C.E.Rossi NRR/DOEA C.Berlinger NRR W.Lanning. NRR/00EA P.Baranowsky NRR/EAB R.Scholl NRR/EAB R. Woodruff NRR/EAB M.L.Reardon NRR/EAB Y.Benaroya AEOD/DSP H.Berkow NRR/DRP i D.Kubicki NRR/ECEB l J.Hannon NRR/0LB G.Bagchi NRR/ESGB L.Shao . NRR/ DEST J.Richardaon NRR/ DEST .

C.Haughney NRR/DRIS. '

U.Minners RES/DRP5 G.Holahan NRR/DRSP 1

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ENCLOSURE 2f

0PERATING REACTORS EVENTS" BRIEFING-87 ,

TUESDAY OCTOBER 6,1987

.THE AGENDA INFORMATION.MAY ALSO BE.0BTAINED BY DIALING EXTENSIONL27174-l FT, ST, VRAIN LOSS'0F. FORCED: CIRCULATION FLOW BYRON-2 LOSS.0F ALL OFFSITE POWER, CALIFORNIA EARTHOUAKE.

TURKEY POINT-3 UNAUTHORIZED CONTROL MANIPULATION.

1 DRESDEN-3 UNAUTHORIZED CONTROL MANIPULATION a 1

.i

FORT ST, VRAIN LOSS OF FORCED CIRCULATION FLOW OCTOBER 3, 1987 PROBLEM FIRE IN TURBINE BLDG CAUSE COMPONENT FAILURE ON HYDRAULIC FLUID SYSTEM FOR MSIVs HYDRAULIC FLUID ON HOT REHEAT LINE RESULTS IN FIRE SAFETY SIGNIFICANCE HELIUM FLOW IN BOTil LOOPS LOST FOR ABOUT 20 MINUTES SM0KE IN CONTROL ROOM DISCUSSION  ;

POWER ASCENSION AT 26% POWER (2359 MDT)

FIRE RESULTS FROM FLUID ON STEAM LINES EQUIPMENT OPERATOR DISCOVERED FIRE COOLANT LOOP #2 LOST DUE TO CIRCULATOR TRIP (0006 MDT)

SOME CR INDICATIONS LOST (RADIATION MONITORS, STEAM FLOW, PUMP STATUS, AND VALVE POSITIONS) 0FFSITE FIRE DEPARTMENTS RESPONDED LOST LOOP #1 DUE TO LOSS OF POWER TO MONITORS OPERATORS SCRAM REACTOR (0009 MDT)

ALERT DECLARED (0030 MDT)

OPERATORS WORE AIR MASKS; SM0KE IN CR - FAILED HVAC DAMPER LOOP #1 FLOW RESTORED (0020 MDT)

TWO CABLE TRAYS AND SNUBBER DAMAGE EVENT APPEARS BOUNDED BY DBA-1 FOLLOWUP AIT DISPATCHED ON SATURDAY (3 NRR)

SCOPE OF INVESTIGATION PROVIDED FOR COMMENT CONTACT: W. LANNING

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j l DAMAGE T0' DISCONNECT SWITCH BETWEEN RING BUS AND SYSTEM AUXILIAPY TRANSFORMER (SAT) DELAYED RESTORATION OF 0FFSITE POWER CAUSE OPERATOR-ERPOR-

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LOSS OF ALL 0FFSITE POWER FOR 9.5 HR DISCUSSION ,

- ON 10/2/87, THE UNIT TRIPPED FROM 7% POWER WHILE STARTING UP ]

TRIP WAS CAUSED BY HIGH SG LEVEL RESULTING FROM A PROBLEM WITH A FEED REG BYPASS VALVE

- PER PROCEDURE, AN OPERATOR WAS DISPATCHED TO THE 305KV SWITCHYARD j TO OPEN THE MOTOR-0PERATED DISCONNECT BETWEEN THE MAIN TRANSFORMER AND THE RING BUS OPERATOR OPENED INSTEAD THE DISCONNECT TO THE SAT WHILE IT-WAS CARRYING POWER-1 - PROTECTIVE RELAYING PREVENTED'SIGNIFICANT DAMAGE'TO DISCONNECT; i HOWEVER, CORONA RINGS ON JAW END OF DISCONNECT WERE DAMAGED BY ARCING DAMAGE INCLUDED 1/2" HOLE AND ARC SPATTER

- SPATTER WAS REMOVED, H0LE EDGES WERE DEBURRED, AND A HOLE WAS DRILLED IN THE BOTTOM 0F THE CORONA RING TO DRAIN ANY WATER THAT MAY ACCUMULATE

- TO CHECK FOR OTHER DAMAGE, LICENSEE RESTORED. POWER FROM RING BUS TO LOADS IN A DELIBERATE AND DISCIPLINED MANNER ALL DGS. STARTED AND REACTOR WAS COOLED BY NATURAL' CIRCULATION UNIT 1 REMAINED AT 97% THROUGHOUT THE EVENT FOLLOWUP

~4 REGION III TEAM (SECTION CHIEF AND TWO SPECIALISTS)'0N SITE EAB FOLLOWING CONTACT: R. WOODRUFF i

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DISCUSSION

- ON 10/2/87, THE UNIT TRIPPED FP0M 7% POWER WHILE STARTING UP l TRIP WAS CAUSED BY HIGH SG LEVEL RESULTING FROM A PROBLEM WITH A- 1 FEED REG BYPASS VALVE I

- PER PROCEDURE, AN OPERATOR WAS DISPATCHED TO THE 345KV SWITCHYARD d TO OPEN THE MOTOR-0PERATED DISCONNECT BETWEEN THE MAIN TRANSFORMER 1 AND THE RING BUS OPERATOR OPENED INSTEAD THE DISCONNECT TO THE SAT WHILE IT WAS CARRYING POWER PROTECTIVE' RELAYING PREVENTED SIGNIFICANT DAMAGE TO DISCONNECT; HOWEVER, CORONA RINGS ON JAW END OF DISCONNECT-WERE DAMAGED BY ARCING i -

DAMAGE INCLUDED 1/2" HOLE AND ARC SPATTER

- SPATTER WAS REMOVED, HOLE EDGES WERE DEBURRED, AND A.H0LE WAS DRILLED IN THE BOTTOM 0F THE CORONA RING TO DRAIN ANY. WATER THAT MAY ACCUMULATE

- TO CHECK FOR OTHER DAMAGE, LICENSEE RESTORED POWER FROM RING BUS TO LOADS IN A DELIBERATE AND DISCIPLINED' MANNER ALL DGS STARTED AND REACTOR WAS COOLED BY NATURAL. CIRCULATION UNIT 1 REMAINED AT 97% THROUGHOUT THE EVENT FOLLOWUP REGION III TEAM (SECTION CHIEF.AND TWO SPECIALISTS) ON SITE EAB FOLLOWING CONTACT: R. WOODRUFF

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OCTOBER 1, 1987 EARTHQUAKE IN LOS ANGELES AREA GE0 LOGY - SEISM 0 LOGY )

MAGNITUDE 6.1 ON OR NEAR WHITTIER FAULT LITTLE OR NO SURFACE RUPTURE l LARGEST AFTERSH0CK OCTOBER 4, 1987, MAGNITUDE 5.3 LARGEST LOS ANGELES AREA EARTHOUAKE SINCE 1971 EFFECTS AT NUCLEAR POWER PLANTS I FELT AND TRIGGERED INSTRUMENTS AT SAN ON0FRE (95 KM)

UNITS 1 AND 3 AT FULL POWER, UNIT 2 DOWN FOR NORMAL REASONS l SURVEILLANCE AND WALKDOWN SHOWED NO DAMAGE OF MALFUNCTION  ;

INITIAL RECORDINGS (0.03G) WELL BELOW OBE i

NOT FELT AND DID NOT TRIGGER INSTRUMENTS AT DIABLO CANYON i (280 KM)  !

LARGEST AFTERSH0CK TRIGGERED ALARM AT SAN ONOFRE UNIT 1 BUT NOT AT-UNITS 2 AND 3 ,

COMPARISON WITH JUNE 10, 1987 ILLIN0IS EARTHQUAKE ILLIN0IS EARTHQUAKE MAGNITUDE 5.0 i EXCEEDED OBE AT HIGH FREQUENCIES (20 Hz) AT CLINTON (180 KM)

FELT AND TRIGGERED INSTRUMENTS AS FAR AWAY AS PRAIRIE ISLAND (780 KM)

EARTHQUAKES EAST OF ROCKY MOUNTAINS RARER BUT EFFECTS EXTEND '

0VER MUCH WIDER AREA NRC EARTHOUAKE RESPONSE FUNCTIONED WELL HEADQUARTERS, REGION, UTILITY AND OUTSIDE TECHNICAL EXPERTS INTERACTED WELL CONTACT: L. REITER

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EARTHOUAKE EFFECTS ARE WIDE RANGING  ; l ROADS OUT OF COMMISSION WATER, GAS LINES BREAK, FIRES STARTED TELEPHONE LINES DOWN .)

UTILITY HEADQUARTERS-(SOUTHERN CALIFORNIA EDISON) DAMAGED ,

AND EVACUATED  ;

1 CONFUSION AND UNCERTAINTY FOLLOWING EARTHOUAKE j EPICENTER NOT PINNED DOWN FOR SEVERAL-HOURS, DIFFERENT FAULTS IMPLICATED POSSIBILITY OF LARGER EARTHQUAKE IN NEXT FEW DAYS RUMORS OF LOS ANGELES GOING ON ALERT AND DANGER ON FAULT I 0FFSHORE OF SAN ONOFRE 1 NEED TO MAINTAIN SEISMOLOGIST AT RESPONSE CENTER OR ON CALL i IMMEDIATELY FOLLOWING EARTHQUAKE l OBE SHUTDOWN FOR OLDER PLANTS NOT REQUIRED FOR PRE APPENDIX A PLANTS COULD BE SOURCE-OF CONFUSION AND CONFLICT BETWEEN NRC AND UTILITY AFTER EARTHQUAKE l MAY BE.DIFFERENT FOR OLDER AND NEWER UNITS AT THE SAME SITE (SONGS 1, 2 AND 3)

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TURKEY P0ltR UNIT 3 UNAUEiORIZED COIRROL MANIPULATION PROBLE_M i

• A NON-LICENSED PERSON WHO WAS NOT IN A TRAINING STATUS WAS ALL0ED TO MANIPULATE THE REACTOR DILUTION CONTROLS IN TliE UNIT 3 C0fER0L ROOM

• IDEIRIFIED BY SR0 LICENSED I&C SUPERVISOR ON 9/13 BACK SHIFT

• REPORTED TO NRC ON 9/22 4

CAUSE j l

l

• OPERATOR ERROR; INADEQUATE TRAINING j

• FLUX MAPPING AT CONSTAfR 30% POWER; StilFT TECH ASST OPERATED SWITCH  !

l SIGNIFICANCE I l

• " CONTROLS" MIEN USED WITH RESPECT TO A NUCLEAR REACTOR WAf6 APPARATUS AND ECHANISMS TliE MANIPULATION OF WHIC11 DIRECTLY AFFECTS THE REACTIVITY OR POWER LEVEL OF THE PEACTOR j

• "0PERATOR" EANS ANY INDIVIDUAL LICENSED UNDER PART 55 TO MANIPULATE A CONTROL OF A FACILITY 1 i

• " SENIOR OPERATOR" EANS ANY INDIVIDUAL LICENSED UNDER PART 55 TO MANIPULATE THE CONTROLS OF A FACILITY AND TO DIRECT THE LICENSED ACTIVITIES OF LICENSED  :

OPERATORS C0fRACT:

JOHN N. HANNON, NRR X24868

l 4

- DISCUSSION-

• PART 55 DOES NOT REQUIRE A LICENSE FOR AN INDIVIDUAL WHO MANIPULATES'THE CONTROLS OF A FACILITY AS A PART 0F THE INDIVIDUAL"S TRAINING IN A FACILITY - J LICENSEE'S TRAINING PROGRAM AS APPROVED BY THE C0ltISSION TO QUALIFY FOR AN i OPERATOR LICENSE UNDER PART 55 j

• THE INDIVIDUAL TRAINEE MJST OFFICIALLY BE ENROLLED IN A HOT LICENSE CLASS .j

• MORE IMPORTAfRLY, THE TRAINEE HJST HAVE COMPLETED THE NECESSARY CLASSR0OM OR SIMULATOR TRAINING IN ACCORDANCE WITH THE APPROPRIATE TRAINING SEQUENCE-PRIOR TO MANIPULATING THE CONTROLS OF THE FACILITY I

FOLLOWUP l A CTNIhbk/h8  ;

arggNUhle%EE HAS EM MIGE MN WlE FIVE MANAGERS

&assc TFe%B5^i8n(NOT u TRAINING FOR' A LICENSE) MAY HAVE I

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= - _ - _ _ _

DRESDEN UNIT 3 UNAUEORIZED CONTROL MANIPULATION PROBLEM

• A NON-LICENSED NUCLEAR ENGINEER WHO WAS NOT IN A TRAINING STATUS WAS.

ALLWED TO MANIPULATE THE CONTROLS FOR THE CONTROL ROD DRIVE SYSTEM UNDER THE DIRECTION OF THE UNIT 3 NUCLEAR STATION OPERATOR (R0 LICENSED) ON 9/4/87 CAUSE I

.i

• OPERATOR OVERSIGHf SIGNIFICANCE

• " CONTROLS" WEN USED WITH RESPECT TO A NUCLEAR REACTOR EANS APPARATUS AND ECHANISMS THE MANIPULATION OF WHICH DIRECTLY AFFECTS THE REACTIVITY OR PGER.

LEVEL OF THE REACTOR

• "0PERATOR" MEANS ANY INDIVIDUAL LICENSED UNDER PART 55 TO FANIPULATE A C0KfROL OF A FACILITY l

i

• " SENIOR OPERATOR" MEANS ANY INDIVIDUAL LICENSED UNDER PART 55 TO MANIPULATE l 111E CONTROLS OF A FACILITY AND TO DIRECT 111E LICENSED ACTIVITIES OF LICENSED ,

OPERATORS  ;

1 i

DISCUSSION

• 10 CFR 50.54(J): APPARATUS AND ECHANISMS OTHER THAN CONTROLS, THE OPERATION OF WHICH MAY AFFECT THE REACTIVITY OR POWER LEVEL OF A REACTOR SHALL BE MANIPULATED ONLY WITH THE IdOWLEDGE AND CONSENT OF AN OPERATOR OR-SENIOR OPERATOR LICENSED PURSUANT TO PART 55 PRESENT AT THE CONTROLS CONTACT:

JOHN N. HANNON, NRR X24868 v

4

• PART 55 DOES NOT PEQUIRE A LICENSE FOR AN INDIVIDUAL.WHO MANIPULATES THE C0KTROLS OF THE FACILITY AS A PART OF THE INDIVIDUAL'S TRAINING IN A FACILITY LICENSEE'S TRAINING PROGRAM AS APPROVED BY THE C0ftllSS10N TO QUALIFY FOR AN OPERATOR LICENSE UNDER PART 55 THE INDIVIDUAL TRAINEE filST OFFICIALLY.BE ENROLLED IN A HOT LICENSE CLASS .

q 1

• f0RE IMPORTANTLY, THE TRAINEE I4JST HAVE COlPLETED THE NECESSARY CLASSROOM -

, OR SIltJLATOR TRAINING IN ACCORDANCE WITH THE APPROPRIATE TRAINING SEQUENCE i PRIOR TO MANIPULATING THE C0KIROLS OF THE FACILITY 1

FOLLOWUP  :

• REGION 111 C0ffENCED 24-HOUR EXPANDED COVERAGE DURING STARTUP AND TESTING ACTIVITIES AT BOTH UNIT 2 AND UNIT 3 TO FOCUS ON CONTROL ROOM ACTIVITIES

• FACILITY LICENSEE HAS REITERATED POLICY THAT MANIPULATION OF CONTROL ROOM PANELS WAS TO BE PERFORED BY LICENSED OPERATORS AND SUPERVISED TRAINEES' l

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.Ef1 CLOSURE 3 .'

REACTOR SCRAQ

SUMMARY

WEEK ENDING 10/04/97 R

.- -- t 1 PLANT SPECIFIC DATA ,h

-i DATE SITE UNIT POWER $1BNAL CAUSE COMPL1- YTD ' YTD YTD , , 3 1

CATIONS AB0VE BELOW. TOTAL -- - l 157. 151 09/28/B7 BEAVER VALLEY. 2 . 74 A EQUIP / ELECT. NO 5- .3 8

. 09/29/87 DRESDEN' 3 78 A UNKNOWN NO 6 0- 6 09/28/87 ROBINSON- 2 100 A PERS0WNEL N0 3 4' .7 2 15 A PERSONNEL NO 5 4 9'- 4 09/29/67 BEAVER VALLEY 2 3A PERSONNEL NO 0 4 4 {

10/01/87 NINE MILE POINT.

10/01/87 BYRON 2 92 A EDU!PMENT. NO 7 3 . 10 1 10/02/01 BYRON 2 13 A PERSONNEL NO 7 4- 11 10/02/87 CLINTON- 1 - 97 A PERSONNEL NO . 7- 2 9 10/02/87 SALEM- 1 0A EQUIP / ELECT. N6 - 1 l' '2. 1 10/03/87 FORT ST, VRAIN 1 26 M: EQUIP / MECH. YES' 3 0 3  :!

1 18 A EQUIP / ELECT.. NO. 1 1 2 .

10/03/87 VERMDNT YANKEE .

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SUMMARY

OF COMPLICAi!0NS SITE UNIT COMPLICATIONS FORT ST. VRAIN 1 SM0KE IN CONTROL ROOM i

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i II. COMPARISDN OF WEEKLY STATISTICE WITH.INDUSTRi AVERAGES-  :

1 SCRAf15 FUR WEEU ENDING 1 10/04/8'1 SCRAM CAUSE POWER NLINDER 1987 19D6 1985 )

OF WEEKLY WEEKLY WED:LY l SCRAMS (5) AVERAGE AVERAGE AVERAGE 1 YTD (3) (4) (8) (9) j I

i 44 POWER 215% I EOUTP. RELATED 2 G". 4 4.2 4.3 5.4 )

PERS. RELATED(6) >15% 2 1.4 1,. 8 2.O  !

OTHER(7) >15% 1- 1.2 O.4 0.6

• • Subtotal $4 7 6.9 6.G 8.0 44 POWER <15%

EOUIP. RELATED <15% i 1.3 1.4~ 1.3 PERS. RELATED <15% 3 O.7 0,8 O.9 OTHER <15% 0 C.3 O. 2 O.2

• • Subtotal **

4 2.3 2.4 2.4 ,

• • • Total ***

11 9.2 8.4 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY l SCRAMS AVERAGE AVERAGE AVERAGE YTD .

MANUAL SCRAMS 1 1.4 1.O 1.O l AUTOMATIC SCRAMS 10 7.8 7.9 9.4 i l

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w NOTES  !

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF'50.72-REPORTS.  :

FOR THE 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.

2. RECOVERY COMPLICATED BY EQUIPMENT. FAILURES OR PERSONNEL ERRORS i UNRELATED TD CAUSE OF SCRAM.-

3. 1986 INFORMATION DERIVED FROM ORAS' STUDY OF UNPLANNED REACTOR ^  ;

i TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS. l IN A GIVEN CATEGORY AND DIVIDING BY.52 WEEKS / YEAR.

4. IN 1986, THERE WERE AN ESTIMATED TOTAL' 0F 461 AUTOMATIC AND .

MtHUAL UNPLANNED REACTOR TRIPS'AT.104 REACTORS (HOLDING OriRATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS. 1

5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

6. PERSONNEL RELATED PROBLEMS INCLUDE' HUMAN ERROR,-PROCEDURAL -

DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLENS.

7. "0THER": INCLUDES AUTOMATIC S0 TAMS ATTRIBUTED TO ENVIRONMENTAL ,

CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL' TRIPS IN A GIVEN CATEGORY AND DIVIDING BY S2 WEEKS / YEAR.

)

9. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541' AUTOMATIC AND MANUAL--

UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). . THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

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.Page No. 11'

,10/06/87 . .

FERFDRMANCE INDICATORS SIGNIFICANT EVEkiS

PLANT NAE EVENT EVENT DESCRIP110N - GTRS!6NIFICANC[.

-i

=- l DATE BYRON 2 10/02/97 LOSS OF ALL OFFSITE POWER 10 UNIT 2 FOR 10 HDURS DUE TO 0 LOSS OF DFFSITE POWER-0FERATOR ERROR

FORTST.VRA!N 10/03/87 LOSS OF BOTH HELIUM PRIMARY C00LANI LOOPS SUBSEQUEsi 10- 0 POTENT!Ai. FOR 09 ACTUAL DE6RADAT!DN '

FIRE CAUSEL BY HYDRAULIC FLUID ON STEAM LINES OF SAFETY-RELAliD EQUIPMENT :-

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