ML20207E281

Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting

ML20207E281
Person / Time
Site:	Byron, River Bend, LaSalle, 05000000
Issue date:	07/16/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8607220289
Download: ML20207E281 (17)

Text

=

1 JIX.18 WB6 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Gary M. Holahan,. Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON July 14, 1986 - MEETING 86-24 On July 14, 1986, an Operating Reactor Events meeting (86-24) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 7,1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2.

In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard to their respective responsibilities.

Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION

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R. Vollmer J. T;nylor C. Heltemes

3. Bournia T. Murley, Reg. I E. Adensam J. Nelson Grace, Reg.11

1. 01shan J. Keppler, Reg. III V. Noonan R. D. Martin, Reg. IV S. Stern J. B. Martin, Reg. V W. Butler R. Starostecki, Reg. I S. Ebneter, Reg. I R. Walker, Reg. Il C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin I

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A.1e ses ENCLOSURE 1 LIST OF ATTENDEES 0JERAT,1N3 REACJ0RS EVENTS BRIEFING (86-24)

JULY 14, 1966 NAM (

DIVISI0N NAME DIVISION R. Vollmer NRR H Virgilio OR/S/NRR G. Holahan ORA 3/NRR S. Steln DBL /NRR

j. 01shan PkRA/NRk C. Trarnell PWRA/NRR T. Denning TSCB/DHFT G, Allison IE/EA9 W. Swenson ORAS/NRR S. Newberry 09AS/tif.R E. Weinkam PVPA/NRR V. Benaroys PWRA/NkR G. Murphy ORNL/h0AC W. Regan PWRB/NRR W. Paulson PWRB/NRR G, K)ingler IE/0RPC J Stone IE/VPB E. Jcrdan IE W. Russell DHFT/NRR R. Berner3 DBL /NRR T. Novak PWRA/NRT.

H. TRampscr PWRA/NRE E. F.ossi PWRA/NRR D. Narenansk/

OCM C. A 'er OCH/TR F. Schroedar PVfB/NRR F. 'liraglia FWRB/NRR M. Caruso CRAS/hRR i

J. T. Board ORAS/SRR D. Tarnoff ORAS/NRR 1

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ENCLOSURE 2 OPERATING REACTOR EVENTS BRIEFING 86-24 JULY 14, 1986 LASALLE 2 FEEDWATER TRAtlSIENT WITHOUT REACTOR SCRAM - UPDATE DIABLC CANYON 2 COMPARIS0N OF FIRST SIX MONTHS 1986 TRIP RATE DATA OTHER EVENTS OF INTEREST EYRON 1 USE OF 50.54(X)

RIVER BEND REACTOR TRIP hm

LASALLE 2 - FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM t

JUNE 1, 1986 - UPDATE, (J. T BEARD, NRR)

PROBLEM:

WHEN VESSEL LEVEL FELL SEVERAL INCHES BELOW SCRAM SETPOINT, 3 0F 4 LEVEL SWITCHES (DIFFERENTIAL PRESSURE, DP) DID NOT TRIP.

ANOTHER DP SWITCH (ADS PERMISSIVE) FAILED TO TRIP WITH MAXIMUM AVAILABLE DP, DURING SUBSEQUENT VESSEL LEVEL TESTS OTHER DP SWITCHES USED TO CONTROL ECCS PUMP MINI-FLOW RECIRCULATION VALVES ACTUATED AT VERY LOW VALUES DURING SUBSEQUENT SYSTEMS TESTS SIGNIFICANCE 1 ATWS PRECURSOR INCIDENT ALL DP SWITCHES BY THIS MANUFACTURER (STATIC "0" RING) ARE NOW SUSPECT GENERIC APPLICABILITY TO SEVERAL BWRs AND PWRs PRECURSOR EVENTS AT OYSTER CREEK (JAN. 1986) AND LASALLE (FEB 1986, MAY 1986)

DISCUSSION:

AUGMENTED INSPECTION TEAM DISPATCHED INF0P.MATION NOTICE (86-4') ISSUED

/

PUBLIC MEETING (INFORMATI0h EXCHANGE) HELD PLANT VISIT LICENSEE TESTING SOR DP SW:TCHES GE ANALYSIS MAY SHOW WIDER TOLERANCES 10 BE ACCEPTABLE - NEW LICENSING BASIS UPDATE:

LASALLE RESTART SUBMITTAL / MEETING SCHEDULEDs NRR HAS LEAD IE BULLETIN DEVELOPED IDENTIFY SOR DP SWITCH APPLICATIONS (7 DAYS)

ALERT REACTOR OPERATORS (7 DAYS)

SPECIAL OPERABILITY TESTING 0F SOR SWITCHES (30 DAYS)

SHORT-TERM CORRECTIVE ACTIONS ANALYSIS TO DETERMINE LONG-TERM CORRECTIVE ACTIONS (60 DAYS)

OTHER MECHANICAL DP SWIYCHES TO BE HANDLED SEPARATELY BY NRR/ DBL BULLETIN ISSUANCE EXPECTED WEEK OF JULY 14, 1986

w

---w-4 4.

OTHER KNOWN APPLICATIONS OF SOR DP SWITCHES WNP-2 VESSEL LOW LEVEL MILLSTONE I TORUS TO REACTOR BUILDING VACUUM BREAKER DUANE ARNOLD VESSELDOUILE.LOWLEVEL OYSTER CREEK VESSEL LOW LEVEL VESSEL DOUBLE LOW LEVEL SEQUOYAH UPPER HEAD INJECTION LOW LEVEL ISOLATION BROWNS FERRY RHR MINI-FLOW CONTROL s

COMPARIS0N OF FIRST SIX MONTHS 1986 TRIP RATE DATA (0 RAS)

OPERATING TIME TRIP FRE0VENCY (TRIPS /1000 CRIT. HOURS) 4 (THOUSANDS OF PERIOD CRITICAL HOURS)

ALL TRIPS TRIPS WITH COMPLICATIONS 1985 411.7

.1.31

.16 1986 213.4

'.1.14'

.16' EXTRAPOLATED FROM DATA FOR FIRST 5 MONTHS OF 1986 OTHER FIRST SIX MONTHS RESULTS 1.

MOST O'JTLIERS ARE THE PLANTS MOST RECENTLY LICENSED 2.

INDIAN POINT 2 FREQUENCY EXCEPTIONALLY HIGH CONSIDERING PLANT AGE 3.

75% OF ALL TRIPS ARE THE RESULT OF PLANT TRANSIENTS

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l Peca No.

1 j

07/14/86 SIMI-ANNUAL SCRAM SUtttARY i

01/01/86 TO 06/30/86 i

PLANT AUTO AUTO MANUAL MANUAL EQUIP. PERS. OTHER SCRAMS TOTAL PLANT CR. HRS

• SCRAMS

• j SCRAMS SCRAMS SCRAMS SCRAMS WITH SCRAMS OPER.

/ 1000 j

>15%

<154

>15%

<155 COMPL.

CR.BRS i

ARKANSAS 1 1

0 0

0 1

0 0

0 1 ARKANSAS 1 3181 0.31 i

ARKANSAS 2 3

3 0

0 4

2 0

0 6 ARKANSAS 2 3543 1.41 BEAVER VALLEY 1 1

2 0

0 2

1 0

0 3 BEAVER VALLEY 1 3220 0.93 BIG ROCK POINT 1 0

0 0

0 0

0 0

0 0 BIG ROCK POINT 1 3495 0.00 BROWNS FERRY 1 0

0 0

0 0

0 0

0 0 BROWNS FERRY 1 0

0.00 I

BROWNS FERRY 2 0

0 0

0 0

0 0

0 0 BROWNS FERRY 2 0

0.00 i

BROWNS FERRY 3 0

0 0

0 0

0 0

0 0 BROWNS FERRY 3 0

0.00 l

BRUNSWICK 1 2

1 0

0 3

0 0

1 3 BRUNSWICK 1 3437 0.87 BRUNSWICK 2 1

0 0

0 1

0 0

0 1 BRUNSWICK 2 0

0.00 BYRON 1 2

0 1

0 2

1 0

0 3 BYRON 1 3241 0.93 CALLAWAY 1 3

1 0

0 1

2 1

0 4 CALLAWAY 1 2338 0.86 i

CALVERT CLIFFS 1 1

0 0

0 0

1 0

0 1 CALVERT CLIFFS 1 3456 0.29 CALVERT CLIFFS 2 2

0 1

0 3

0 0

0 3 CALVERT CLIFFS 2 3541 0.85 i

CATAWBA 1 4

2 0

0 2

4 0

0 6 CATAWBA 1 3395 1.47 i

CATAWBA 2 1

1 0

1 2

1 0

1 3 CATAWBA 2 373 10.00 COOK 1 1

0 0

0 1

0 0

'0 1 COOK 1 3527 0.28 i

COOK 2 1

0 0

0 1

0 0

.0' 1 COOK 2 1353 0.74 COOPER 1 1

0 0

0 1

0 0

0 1 COOPER 1 3595 0.28 j

CRYSTAL RIVER 3 1

0 0

0 1

0 0

1 1 CRYSTAL RIVER 3 24 41.67 DAVIS BESSE 1 0

0 0

0 0

0 0

'O O DAVIS BESSE 1 0

0.00 1

DIABLO CANYON 1 1

0 0

0 0

1 0

1 1 DIABLO CANYON 1 3592 0.28 j

DIABLO CANYON 2 6

0 1

0 7

0 0

2 7 DIABLO CANYON 2 1844 3.25 DRESDEN 2 1

0 0

0 0

1 0

0 1 DRESDEN 2 3119 0.32 DRESD1IN 3 0

0 0

0 0

0 0

0 0 DRESDEN 3 0

0.00 DUANE ARNOLD 1 0

0 0

1 1

0 0

0 1 DUANE ARNOLD 1 3098 0.00

)

FARLEY 1 3

0 0

0 3

0 0

0 3 FARLEY 1 3575 0.56 FARLEY 2 1

1 0

0 2

0 0

0 2 FARLEY 2 2533 0.79 FERMI 2 0

0 0

0 0

0 0

0 0 FERMI 2 0

0.00 FITZPATRICK 1 1

0 0

0 1

0 0

0 1 FITZPATRICK 1 3217 0.31 FORT CALHOUN 1 0

0 0

0' O

O O

O O FORT CALBOUN 1 3428 0.00 FORT GT. VRAIN 1 1

0 1

0 1

1 0

1 2 FORT ST. VRAIN 1 2457 0.81 GINNA 1 0

0 0

0 0

0 0

0 0 GINNA 1 2633 0.00 GRAND GULF 1 1

2 1

0 3

1 0

0 4 GRAND GULF 1 3299 1.21 HADDAM NECK 1 0

3 2

0 2

2 1

0 5 HADDAM NECK 1 693 1.44 HATCH 1 2

0 0

0 1

1 0

1 2 HATCH 1 660 3.03 HATCH 2 3

1 0

0 4

0' O

1 4 HATCH 2 3470 0.86 i

HOPE CREEK 1 0

1 0

1 1

1 0"

0 2 HOPE CREEK 1 0

0.00 INDIAN POINT 2 3

1 1

0 3

1 1

2 5 INDIAN POINT 2 441 6.80 INDIAN POINT 3 4

2 0

0 4

1 1

1 6 INDIAN POINT 3 2962 2.03 KEWAUNEE 1 3

1 0

0 2

2 0

1 4 KEWAUNEE 1 2447 1.63 LACROSSE 1 3

4 0

1 7

1 0

2 8 LACROSSE 1 1832 3.28 LASALLE 1 0

0 0

0 0

0 0

0 0 LASALLE 1 0

0.00 LASALLE 2 2

2 0

0 1

2 1

0 4 LASALLE 2 3180 1.26 i

LIMERICK 1 1

0 0

0 1

0 0

0 1 LIMERICK 1 2158 0.46 l

• THE CRITICAL HOURS OF OPERATION AND SCRANS/1000 CRITICAL HOURS ARE BASED ON DATA THROUGH NAY 31st l

Pega No.

2 07/14/86 SEMI-ANNUAL SCRAM SUtttARY 01/01/86 TO 06/30/86 PLANT AUTO AUTO MANUAL MANUAL EQUIP. PERS. OTHER SCRAMS TOTAL PLANT CR. HRS

• SCRAMS

• SCRAMS SCRAMS SCRAMS SCRAMS WITH SCRAMS OPER. / 1000

>15%

<15%

>15%

<15%

COMPL.

CR. HRS MAINE YANKEE 1 2

0 1

0 1

2 0

1 3 MAINE YANKEI 1 3163*

0.63 HCGUIRE 1 2

0 0

0 2

0 0

0 2 MCGUIRE 1 3113 0.64 HCGUIRE 2 1

2 0

0 3

0 0

0 3 HCGUIRE 2 1885 1.19 MILLSTONE 1 1

0 0

1 2

0 0

1 2 HILLSTONE 1 3440 0.58 i

MILLSTONE 2 1

0 0

0 1

0 0

0 1 MILLSTONE 2 3624 0.00 MILLS 70NE 3 1

7 1

0 5

3 1

0 9 MILLSTONE 3 840 10.71 MONTICELLO 1 0

0 0

0 0

0 0

0 0 HONTICELLO 1 2870 0.00 I

NINE MILE FOINT 1 0

2 0

0 1

1 0

0 2 NINE MILE POINT 1 1434 0.00 NORTH ANNA 1 4

1 0

0 3

1 1

1 5 NORTH ANNA 1 3163 1.58 NORTH ANNA 2 3

1 0

0 3

1 0

1 4 NORTH ANNA 2 2534 1.18 OCONEE 1 2

0 0

0 2

0 0

0 2 OCONEE 1 1455 1.37 OCONEE 2 2

0 0

0 0

2 0

0 2 OCONEE 2 3615 0.55 OCONEE 3 1

0 0

0 1

0 0

0 1 OCONEE 3 3620 0.28 OYSTER CREEK 1 1

0 0

0 0

1 0

1 1 OYSTER CREEK 1 2312 0.43 PALISADES 1 2

0 0

0 2

0 0

1 2 PALISADES 1 1491 1.34 PALO VERDE 1 5

0 0

0 3

2

.0 1

5 PALO VERDE 1 749 5.34 0,

1.

3 PALO VERDE 2 427 4.68 PALO VERDE 2 2

1 0

0 2

1 3

PEACH BOTTOM 2 3

0 0

0 2

1 0

0 3 PEACH BOTTOM 2 3082 0.97 PEACH BOTTOM 3 1

1 0

1 0

3 0

0 3 PEACH BOTTOM 3 1770 1.69 PERRY 1 0

0 0

0 0

0 0

0 0 PERRY 1 0

0.00 PILGRIM 1 1

3 0

0 2

2 0

1 4 PILGRIM i 1716 2.33 POINT BEACH 1 1

0 0

0 1

0 0

0 1 POINT BEACH 1 2784 0.00 POINT BEACH 2 1

0 0

0 0

1 0

0 1 POINT BEACH 2 3619 0.28 i

PRAIRIE ISLAND 1 0

1 0

0 0

1 0

0 1 PRAIRIE ISLAND 1 2775 0.36 PRAIRIE ISLAND 2 2

0 0

0 0

2 0

0 2 PRAIRIE ISLAND 2 3801 0.56 4

QUAD CITIES 1 0

1 0

0 1

0 0

0 1 QUAD CITIES 1 1436 0.70 QUAD CITIES 2 1

0 0

0 0

1 0

0 1 QUAD CITIES 2 3378 0.30 RANCHO SECO 1 0

0 0

0 0

0 0

0 0 RANCHO SECO 1 0

0.00 RIVER BEND 1 11 2

0 0

5 8

0 1

13 RIVER BEND 1 2171 5.07 ROBINSON 2 5

2 0

0 3

4 0

1 7 ROBINSON 2 2271 2.64 SALEM 1 6

1 0

0 5

1 1

3 7 SALEM 1 2471 1.62 SALEM 2 1

1 0

0 2

0 0

1 2 SALEM.2 3128 0.64 SAN ONOFRE 1 0

0 0

0 0

0 0

0 0 SAN ONOFRE 1 0

0.00 SAN ONOFRE 2 1

2 1

0 4

0 0

0 4 SAN ONOFRE 2 1707 0.59 SAN ONOFRE 3 2

1 0

0 2

1 0

0 3 SAN ONOFRE 3 2835 1.06 SEQUOYAH 1 0

0 0

0 0

0 0

0 0 SEQUOYAH 1 0

0.00 SEQUOYAH 2 0

0 0

0 0

0 0.-

0 0 SEQUOYAH 2 0

0.00 j

SAINT LUCIE 1 2

0 0

0 0

2 0

0 2 SAINT LUCIE 1 3610 0.55 SAINT LUCIE 2 1

1 0

0 0

2 0

0 2 SAINT LUCIE 2 2244 0.45 SHOREHAM 1 0

0 0

0 0

0 0

0 0 SHOREHAM 1 0

0.00 1

SUttfER 1 4

1 0

0 3

2 0

0 5 SUttfER 1 3554 1.13 SURRY 1 0

1 2

0 1

2 0

0 3 SURRY 1 2730 1.10 SURRY 2 2

0 1

0 3

0 0

1 3 SURRY 2 3414 0.59 SUSQUEHANNA 1 0

0 0

0 0

0 0

0 0 SUSQUEHANNA 1 1897 0.00 3

• ' THE CRITICAL HOURS OF OPERATION AND SCRAMS /1000 CRITICAL HOURS ARE BASED ON DATA THROUGH MAY 31st

Pass No.

3 07/14/86 SEMI-ANNUAL SCRAM SUtt1ARY 01/01/86 TO 06/30/86 PLANT AUTO AUTO MANUAL MANUAL EQUIP. PERS. OTHER SCRAMS TOTAL PLANT CR. HRS

• SCRAMS

• SCRAMS SCRAMS SCRAMS SCRAMS WITH SCRAMS OPER. / 1000

>15%

<15%

>15%

<15%

COMPL.

CR. HRS SUSQUEHANNA 2 0

1 1

0 2

0 0

0 2 SUSQUEHANNA 2 3353 0.60 THI 1 3

1 0

0 2

1 1

2 4 THI 1 2608 1.15 TROJAN 1 2

0 0

0 1

1 0

0 2 TROJAN 1 2507 0.40 TURKEY POINT 3 3

1 0

0 1

3 0

0 4 TURKEY POINT 3 2502 1.20 TURKEY POINT 4 0

0 0

0 0

0 0

0 0 TURKEY POINT 4 225 0.00 VERMONT YANKEE 1 0

1 0

0 1

0 0

0 1 VERMONT YANKEE 1 0

0.00 WNP 2 1

2 0

0 1

2 0

0 3 WNP 2 1779 1.12 WATERFORD 3 3

0 0

0 3

0 0

0 3 WATERFORD 3 3014 0.66 WOLF CREEK 1 3

0 0

0 2

1 0

1 3 WOLF CREEK 1 41 48.78 YANKEE ROWE 1 1

0 0

0 1

0 0

0 1 YANKEE ROWE 1 3623 0.00 ZION 1 2

0 0

0 2

0 0

0 2 ZION 1 3210 0.62 ZION 2 3

0 0

0 1

2 0

1 3 ZION 2 2479 0.81 03* Total ***

157 66 15 6

151 84 9

35 244 4

L THE CRITICAL HOURS OF OPERATION AND SCRAMS /1000 CRITICAL HOURS ARE BA' ED ON DATA THROUGI MAY 31st S

I

OTHER EVENTS OF INTEREST BYRON 1 - USE OF 50.54(X)

JULY 3, 1986, (L. OLSHAN, NRR)

PROBLEM:

POSSIBLE IMPROPER USE OF 50.54(X)

SIGNIFICANCE:

FIRST PLANT TO INV0KE 50.54(X)

DISCUSSION:

DETECTED UNIDENTIFIED LEAKAGE OF 1.007 GPM BEGAN C00LDOWN AS PER TECH SPECS FOUND BORON DILUTION PROTECTION SYSTEM (BDPS) IN0PERABLE TECH SPECS INFER THAT C00LDOWN SHOULD BE STOPPED WHEN BDPS IS INOPERABLE LICENSEE INV0KED 50'54(X) AND CONTINUED C00LDOWN TAKING COMPENSATORY MEASURES 50.54(X) INTENDED FOR EMERGENCY SITUATIONS WHEP.E PUBLIC HEALTH AND SAFETY NECESSITATES DEPARTURE FROM TECHNICAL SPECIFICATIONS OTHER OPTIONS: COULD HAVE REQUESTED WAIVER OF COMPLIANCE OR ENFORCEMENT DISCRETION FOLLOWUP:

REGION III DETERMINING IF LICENSEE PROPERLY USED 50.54(X)

OR WAS OTHER ACTION APPROPRIATE NRR WILL INVESTIGATE THE NEED TO CHANGE THE STANDARD TECH SPECS 4

RIVER BEND STATION - REACTOR TRIP JULY 8, 1986 (S. STERN, NRR)

PROBLEM:

INADEQUATE TORQUING ON MANWAY FLANGE GASKET IN NON-SAFETY RELATED MAIN STEAM MOISTURE SEPARATOR REHEATER DRAIN RECEIVER TANK RESULTED IN REACTOR TRIP.

SIGNIFICANCE:

INADEQUATE ATTENTION BY LICENSEE TO NON-SAFETY RELATED MAINTENANCE RESULTED IN PLANT TRANSIENT DISCUSSION AS A RESULT OF A SMALL STEAM LEAK, AN OUTSTANDING MAINTENANCE WORK REQUEST (MWR) HAD SPECIFIED REPLACING GASKET MATERIAL, TORQUING FLANGE " WRENCH TIGHT" PREVIOUS MWR ON SIMILAR TASKS HAD SPECIFIED TORQUE OF 1000 FT-LBS MAINTENANCE TECHNICIAN RECOGNIZED DEFICIENCY WITH REGARD TO TORQUING INSTRUCTIONS, TIGHTENING TO 300 FT-LBS (JUDGEMENT CALL).

DURING RESTART, MANWAY GASKET BLEW OUT CAUSING STEAM LEAK AND MINOR DAMAGE TO ADJACENT INSULATION AND FLEX CONDUIT.

STEAM LEAK FROM BLOWN GASKET RESULTED IN SCRAM ON HIGH TEMPERATURE FROM MSIV ISOLATION.

GASKET MATERIAL REPLACED WITH SUPERIOR MATERIAL (SPIRAL WOUND FLEXITALLIC)

TORQUED TO 1000 FT-LB, AFTER STUDY BY LICENSEE ENGR. STAFF LICENSEE QC VERIFIED NO WARPAGE TO FLANGE REPAIR OF MINOR DAMAGE ALL MWRs FROM PREVIOUS TWO OUTAGES - COMPLETELY REVIEWED BY LICENSEE MAINTENANCE AND ENGR DEPTS (341 MWRs) - ONE FLANGE TORQUE l

RECHECKED - FOUND TO BE ADEQUATE l

FOLLOWUP RESIDENT - REGION IV FOLLOWING UP CLOSELY OVERSIGHT GROUP ESTABLISHED BY PM (PM, ORAS, IE/ EVENT ANALYSIS, REGION IV, RESIDENT).

MONITOR PLANT OPERATIONS & EVENTS DURING BALANCE OF FIRST CYCLE RECOMMEND AGENCY ACTION, IF APPROPRIATE t

1 y

\\

7 REACTOR SCRAM

SUMMARY

WEEK ENDING 07/13/86 I.

PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 07/07/86 SAN ONOFRE 2

49 A EQUIP YES 5

07/07/86 COOK 2

OA EQUIP NO 2

07/08/86 LACROSSE 1

OA EQUIP NO 9

07/08/86 CATAWBA 2

29 A EQUIP NO 4

07/08/86 OCONEE 2

100 A EQUIP NO 3

07/08/86 RIVER BEND 1

.625 A EQUIP NO 14 49 A EQUIP /MFW PMP YES 10 07/09/86 DIABLO CANYON 2

4 07/10/86 WNP 2

100 A PERSONNEL NO 4

07/12/86 DRESDEN 2

90 A UNKNOWN NO 2

07/12/86 HOPE CREEK 1

3M UNKNOWN NO 4

07/12/86 PALO VERDE 1

100 A UNKNOWN YES 6

07/13/86 RIVER BEND 1

85 A EQUIP NO 15 07/13/86 DRESDEN 2

1 A EQUIP NO 3

SUMMARY

OF COMPLICATIONS SITE UNIT COMPLICATIONS SAN ONOFRE 2 ONE MFWP DID NOT RUNBACK PROPERLY DIABLO CANYON 2 UNPLANNED AUTO START OF EDG PALO VERDE 1 SI WITH INJECTION ON LOW PRESSURIZER PRESSURE SIGNAL i

l l

6'.

k f[,\\

t

(?

k",

p SI'.

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES k

SCRAMS FOR WEEK ENDING 07/06/86 ff-SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY S

SCRAMS (5)

AVERAGE AVERAGE YTD (3) (4) 1:-

/

• • POWER >15%

g'.

EQUIP. RELATED

>15%

7 4.4 5.4 (68%)

1 2.1 2.0 (25%)

PERS. RELATED(6) >15%

}ll OTHER(7)

>15%

O O.2 0.6 ( 7%)

• • Subtotal **

p-8 6.7 8.0 Pi.

2

• • POWER <15%

EQUIP. RELATED

<15%

4 1.6 1.3 (54%)

PERS. RELATED

<15%

0 1.1 0.9 (38%)

OTHER

<15%

0 0.1 0.2 ( 8%)

- ** Subtotal **

4 2.8 2.4

• • • Total ***

12 9.5 10.4 I

MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 I

OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1

0.8 1.0 AUTOMATIC SCRAMS 11 8.7 9.4 l

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1.

PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.

PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN. 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 UNRELATED TO CAUSE OF SCRAM.

~

3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985.

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

4.

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 PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

5.

BASED ON 97' REACTORS HOLDING A FULL POWER LICENSE.

6.

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

7.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

ENCLOSURE 3 Page No.

1 07/15/86 OPERATING REACTORS EvDTS MEETING FOLLONUP ITEMS AS OF MEETING 86-24 ON JULY 14, 1986 i

(IN ASCDDIN6 MEET!N6 BATE, NSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSEDDATE COMMENTS NUMBER /

NSSSVENDOR/

DIVISION /

COMPLET. SY DOCUMENT, MEETING EVENT DESCRIP.

INDIVIDUAL DATE(S)

MEETIN6,ETC.

DATE 86-10 OYSTER CREEK NRR / HOUSTON N RESOLVE THE QUESTION OF THE 10/30/86 OPEN

/ /

FOLLOWLP ACTION TO 03/31/86 6E / LEVEL

/

ACCEPTABILITY OF BLIND SWITCHES

//

BE INCORPORATED IN SNITCH SETPOINT AND DELETION OF DAILY CHANNEL

//

REVIEW 0F JUNE DRIFT CHECK 1,1986 EVENT AT LASSALLE 86-21 VERMONT YANKEE NRR /HOLAHAN 6.

DETERMINE STATUS A H 08/20/86 OPEN

/ /

06/23/86 SE / PROBLEMS

/

EFFECTIVENESS OF STAFF AND

//

WITH SCRAM LICENSEE ACTION ON

//

SOLEN 0!DVALVES POST-MAINTENANCE TESTING (6L 83-28). DEVELOP RECOMENDATIONS FOR FURTHER ACTION B6-21 TURKEYPOINT NRR / ROSA F.

CONSibERREVIEWINGELECTRICAL 08/30/86 OPEN

/ /

06/23/86 N / POTENTIAL

/

SYSTEM OF PLANT WITH SIMILAR'

//

FAILURE OF ALL SWING BUS DESIGN

//

i I

EMER6ENCY DIESEL 6ENERATORS 86-23 PERRY NRR / HOUSTON N.

OBTAIN AND REVIEN INFORMATION 08/29/86 OPEN

/ /

07/07/86 SE / FIRE IN

/

RELATED TO RECURRENCE OF FIRE

/ /

0FF6AS CHARC0AL ANDINVEST!6ATEPROPOSED

//

i BEDS ACTIONS

,fi 86-23 MULT!

NRR / HOUSTON U.

DETERMINE APPROPRIATE 09/30/86 OPEN

/ /

07/07/86 NA /

/

RESULATORY REQUIREMENTS BASED

/ /

SWRS-RESIDUAL ONRECOMMENDATIONSDISCUSSEDAT //

HEAT REMOVAL BRIEFING PUMP /NEAR RING FAILURES -

FOLLOWUP 86-23 MULTI-NRR / BERLIN 6ER C.

ASSURENRRANDIEC00RDINAT10N 08/30/86 OPEN

/ /

07/07/86 NA /

'/

TO DETERMIIE THE NEED FOR AN IE

//

PWRS-INADEQUATE BULLETIN

//

DESIGN OF ECCS PUMP MINIMUM l

FLOW PATHS t

4

- -,,,, _