ML20151M746

Summary of 851209 Operating Reactor Events Meeting 85-26. List of Attendees,Viewgraphs of Events Discussed & Assignment of Followup Review Responsibility Encl

ML20151M746
Person / Time
Site:	Peach Bottom, Pilgrim, Susquehanna, Vermont Yankee, Rancho Seco, 05000000
Issue date:	12/19/1985
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8601020689
Download: ML20151M746 (21)

Text

'

DEC 19 O 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 DECEMBER 9, 1985 - MEETING 85-26 On December 9, 1985, an Operating Reactor Events meeting (85-26) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 2, 1985. 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 follow-up 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 assignees are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date canr.ot be met.

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page DISTRIBUTION Central Files NRC PDR OPAB Rdg ORAB Members

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Harold R. Denton cc: D. Eisenhut H. Silver J. Taylor R. Shewmaker C. Heltemes J. Zudans T. Murley, Reg. I M. M. Campagnone J. Nelson Grace, Reg. II E. Adensam J. Keppler, Reg. III G. Gears R. D. Martin, Reg. IV P. Leech J. B. Martin, Reg. V V. Rooney R. Starostecki, Reg. I D. Muller R. Walker, Reg. II J. Zwolinski C. Norelius, Reg. III S. Miner E. Johnson. Reg. IV J. Stolz D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Spets W. Russell T, Novak F. Schroeder W. Houston B. Sheron D. Zitaann J. *anight C. Crutchfield G. Lainas V. Benaroya W..Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan K. Seyfrit

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-26)

DECEMBER 9, 1985 H. R. Denton NRR D. L. Ziemann DHFS M. J. Virgilio ORAS/NRR T. S. Rotella BWD1/NRR V. Rooney DBL /PD-2 E. Jordan IE E. Weinkam TOSB/NRR F. Schroeder PWR-B/NRR S. Black TOSB/NRR D. Tarnoff NRR/0 RAS C. J. Paperiello RIII R. Hernan TOSB S. C. Rhow DBL /EICSB E. J. Leeds AEOD/RCAB J. Stone IE/VPB R. A. Hermann BWR-PD#1 R. Perfetti PWR#8 M. J. Campagnone DBL D. B. Vassallo DBL / FOB M. Clausen OCM 3 W. Regan PD2/ FOB R. J. Bosnak NRR/DSR0 B. Sheron NRR/DSR0 H. Thompson DPL-A R. Bernero DBL J. Zwolinski DBL /PD#1 D. R. Muller NRR/ DBL G. Holahan NRR/0 RAS J. P. Knight NRR/PWR-A R. H. Wessman NRR/ORAS V. Benaroya PWR-A/ FOB G. Gears DBL-PD#2 S. Long IE/DEPER K. Eccleston NRR/TOSB S. Rubin AEOD E. Addensam DBL-PD#3 R. Singh IE E. Rossi IE/EAB S. H. Weiss PWR-A/EICSB G. Edison DPL-B/PD#6 G. Lapt.. sky PWR-A/ FOB R. Hernan NRR-TOSB K. Seyfrit AE0D H. Bailey IE/EAB I G. Dromerick IE/EGCB R. Shewmaker IE/EGCB

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k OPERATING REACTORS EVENTS BRIEFING 85-26 l 1

i DECEMBER 9, 1985 1 RANCHO SECO REACTOR TRIP  !

SUSQUEHANNA UNITS 1 AND 2 LOSS OF Till TRANSFORMER I

- r PILGRIM MAIN STEAMLINE DIFFERENTIAL  !

PRESSURE' SWITCH DRIFT [

i VERMONT YANKEE PIPE SUPPORT PROBLEMS PEACH BOTTOM UNITS 2 AND 3 RESIDUAL HEAT REMOVAL PUMP / WEAR RING AND MOTOR BEARING FAILURES i (UPDATE)  !

RANCHO SECO - REACTOR TRIP DECEMBER 5, 1985 - (S. MINER, NRR)

PROBLEM:

A REACTOR TRIP WITH FEEDWATER SYSTEM UPSET, FEEDWATER HEATER RELIEF VALVE OPENING AND SAFETY INJECTION SIGNIFICANCE:

INDICATION OF INADEQUATE PROCEDURES AND OPERATOR ERROR PROBLEM WITH PEGGING STEAM RELIEF VALVE OPENING WAS TO BE RESOLVED PRIOR TO NOVEMBER 2, 1985 STARTUP DISCUSSION:

_ PLANT AT 91% POWER R0D CONTROL AND FW CONTROL IN MANUAL WHILE CALIBRATING REACTOR COOLANT FLOW INSTRUMENTS WHEN TRANSFERRING TO AUTOMATIC, FW FLOW TO STEAM GENERATORS INCREASED RETURN TO MANUAL; REDUCED FLOW "A" FLOW METER RESPONDED "B" DID NOT DUE TO RECORDER PEN HANG UP REDUCED FLOW FURTHER - HIGH PRESSURE SCRAM LOW LEVEL IN PRESSURIZER INITIATED HP INJECTION RELIEF VALVE ON FW HEATER OPENED MANUALLY SHUT OFF STEAM TO FW HEATER PLANT STABILIZED WITHOUT EXCESSIVE C00LDOWN OR PRESSURE TRANSIENT FOLLOW-UP:

REGION V FOLLOWING~ LICENSEE'S CORRECTIVE ACTIONS LICENSEE REVISING PROCEDURES, RESETTING PEGGING STEAM CONTROLLER RESTART EXPECTED BY 12/12/85

SUSQUEHANNA UNITS 1 AND'2 - LOSS OF T111 TRANSFORMER DECEMBER 2, 1985 4M, CAMPAGNONE, NRR)

PROBLEM:

- LOSS OF Till TRANSFORMER CAUSED INTERRUPTION OF A 'C, POWER (C CHANNEL IN BOTH UNITS) TO INSTRUMENT AND CONTROL PANELS IN BOTH UNITS 1 AND 2 POWER INTERRUPTION CAUSED FEEDWATER PUMP CONTRDLLERS TO LOCK-UP SIGNIFICANCE:

A SINGLE LOSS OF POWER CAN CAUSE A FW TRANSIENT IN BOTH UNITS AND CAUSE EACH UNIT TO SCRAM CIRCUMSTANCES:

SUDDEN PRESSURE RELAY TRIPPED THE Till TRANSFORMER LOADS AUTOMATICALLY TRANSFERRED TO THE T211 TRANSFORMER M0MENTARY INTERRUPTION OF A.C. POWER TO CONTROL AND INSTRUMENT PANELS CAUSES FW CONTROLLERS TO LOCK-UP CAUSING THE THREE-VARIABLE SPEED, 33% CAPACITY FW PUMPS IN EACH PLANT T0. FAIL'"AS IS" UNIT 1 OPERATORS FAILED TO RESET SWITCHES WHICH WOULD ALLOW THE MANUAL CONTROL OF THE FW CONTROLLERS THIS RESULTED IN A STEAM-FEED MISMATCH WHICH CAUSED Rx WATER LEVEL TO INCREASE TO LEVEL 8 (+54") TRIPPING THE UNIT ON HIGH Rx WATER LEVEL

UNIT 2 OPERATORS RESET SWITCHES TO GAIN MANUAL CONTROL 0F FW CONTROLLERS THE "A" FW PUMP CONTROL LOGIC HAD A ERROR WHICH UPON RESETTING SWITCHES CAUSED THE "A" FW PUMP TO WIND DOWN TO ZERO FLOW THE OPERATORS TRIED TO MAKE-UP THE FLOW WITH THE "B" AND "C" FW PUMPS BUT THE LEVEL HAD ALREADY DROPPED TO LEVEL 3

(+13") CAUSING'A REACTOR SCRAM ON LOW Rx WATER LEVEL LEVEL DECREASED TO -311" RCIC AUTO INITIATED AT -30" MSIV'S CLOSED HPCI MANUALLY INITIATED FOLLOW-UP LICENSEE HAS MODIFIED LOAD LINE UP S0 THAT FW CONTROL INSTRUMENTATION WILL BE POWERED FROM VITAL A.C. POWER, THIS PROVIDES AN UNINTERRUPTED SOURCE OF POWER LICENSEE HAS BEEN REQUESTED TO IDENTIFY OTHER INSTRUMENTA-TION ON IRC PANELS, AND INVESTIGATE THE RESULTS OF A SIMILAR SCENARIO NOTE: A SIMILAR SCENARIO WAS ANALYZED AND DISCUSSED IN SSER 7 AND WAS DETERMINED TO BE BOUNDED BY CH 15 ANALYSIS AND THEREFORE ACCEPTABLE,

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PILGRIM - MAIN STEAMLINE DIFFERENTIAL PRESSURE SWITCH DRIFT NOVEMBER 25, 1985 (ERIC WEISS, IE)

PROBLEM DURING QUARTERLY SURVEILLANCE ON 11/25/85 MAIN STEAM LINE DP SWITCHES WERE FOUND WITH SIGNIFICANT DRIFT SAFETY SIGNIFICANCE

- ALTHOUGH NOT AFFECTING SAFETY FUNCTION ON 11/25/85, DRIFT MAY BE S0 RAPID THAT SAFETY FUNCTION WOULD BE AFFECTED INSTRUCTIONS FOR CALIBRATING / ADJUSTING.DP SWITCHES MAY NOT BE ADEQUATE TO PREVENT PROBLEM FROM OCCURRING AT OTHER PLANTS CIRCUMSTANCES:

SWITCHES CLOSE MSIVs ON HIGH STEAM LINE FLOW

_-- ITT-BARTON MODEL 288A INSTALLED TO SATISFY EQ REQUIREMENTS BARTON PERSONNEL WERE NOT INVOLVED IN THE FIELD MODIFICATION SIGNIFICANT DRIFT IDENTIFIED Oli MOST OF DP SWITCHES 11 0F 16 DP SWITCHES AB0VE 123 PSID (N0 ADJUST LIMIT) 10 0F 16 DP-SWITCHES AB0VE 125.9 PSID (WATCH ENGINEER LIMIT) 5 0F 16 DP SWITCHES AB0VE 127.2 PSID WHICH = 140% FLOW (TECH SPEC LIMIT)

ON 12/3/85 ONE SWITCH DRIFTED 10 PSI IN ONE DAY SIMILAR MODELS USED ELSEWHERE WITHOUT DRIFT FOLLOW-UP:

LICENSEE BELIEVES DRIFT CAUSED BY BINDING IN LINKAGE, POSSIBLY IN UNUSED PORTION OF SWITCH LICENSEE HAS VOLUNTARILY CHANGED TO WEEKLY SURVEILLANCE IE AND REGION I ARE FOLLOWING JOINT E0 TEAM ONSITE AT PILGRIM CONSIDERING IE NOTICE

ITT-BARTON MODEL 288A -

SUMMARY

OF MOST SEVERE DRIFT SWITCH 261-2E INSTAILID 3/29/85 AT 120.5 PSID DATE FOUND (PSID) RESET (PSID) 5/30/85 112 120 8/30/85 109 119 11/25/85 148 120 i

SWITCH 261-2M INSTALLED 5/17/85 AT 121 PSID DATE FOUND (PSID) RESET (PSID) 5/30/85 120 -

8/30/85 111 121 11/25/85 143 121 12/2/85 110 119 12/3/85 109  ?

! 12/4/85 109  ?

VERMONT YANKEE - PIPE SUPPORT PROBLEMS NOVEMBER 27, 1985,(R, SHEWMAKER, IE)

PROBLEM: PIPE SUPPORT PROBLEMS IDENTIFIED IN HPCI AND RECIRC, SYSTEMS SIGNIFICANCE:

POTENTIAL INABILITY TO WITHSTAND SEISMIC OR ACCIDENT LOADS PROBLEMS APPARENTLY EXISTED SINCE ORIGINAL CONSTRUCTION CIRCUMSTANCES:

RECIRC LINE. PIPE WHIP RESTRAINT PROBLEM RECIRC SYSTEM BEING REWORKED PIPE WAS TO BE REMOVED

'IPE WAS CUT FOR PEMOVAL PIPE WHIP RESTRAINT FAILED AT WELD TO EMBEDDED PLATE EVIDENCE AT WELD INDICATED ONLY TACK WELDS DESIGN / DRAWINGS REQUIRED FULL PENETRATION WELDS CONSTRUCTION WAS APPARENTLY NOT COMPLETED 19 SIMILAR RESTRAINTS EXIST IN DRYWELL VISUAL INSFECTION WILL DETECT ANY SIMILAR PROBLEMS LICENSEE PLANS TO INSPECT THE OTHER 19 RESTRAINTS HPCI LINE PIPE SUPPORT PROBLEM PIPING REANALYSIS TO RG 1.60 (DEC, 1973) COMPLETED SUPPORT WAS TO BE STRENGTHENED FTANCHION CUT FOR REWORK EMBEDDED PLATE FELL NO EVIDENCE OF TENSION BARS IN CONCRETE EVIDENCE THAT TENSION BARS WERE ONCE ON PLATE TENSION BARS POSSIBLY CUT TO RESOLVE CONFLICTS IN WALL REINFORCING NO EXTERNAL VISUAL METHOD AVAILABLE TO INSPECT OTHERS NRC SEES ULTRAS 0NICS AS POSSIBLE INSPECTION TECHNIQUE LICENSEE CONSIDERING FURTHER ACTION FOLLOW-UP: REGION I FOLLOWING LICENSEE ACTIONS

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PEACH BOTTOM UNITS 2 AND 3 - RESIDUAL HEAT REMOVAL PUMP / WEAR RING AND MOTOR BEARING FAILURES (UPDATE)

DECEMBER 9, 1985, (J. ZUDANS, IE) 4 PROBLEM:

LOSS OF IMPELLER WEAR RING WITH SUBSEQUENT PUMP PERFORMANCE DEGRADATION OR POSSIBLE CATASTROP' HIC DAMAGE TO PUMP LOWER MOTOR RADIAL BEARING FAILURE WITH CATASTROPHIC MOTOR FAILURE SIGNIFICANCE:

LOSS OF LHSI AND LONG TERM COOLING CAPABILITY FOLLOWING A DBA ,

~ CIRCUMSTANCES:

PEACH BOTTOM INSPECTIONS OF PUMPS REVEALED PUMP 3B - LOWER IMPELLER WEAR RING TWISTED OFF AND JAMMED INTO CASING PUMP 3D - UPPER IMPELLER WEAR RING PULLED OFF' IMPELLER PUMPS 2A AND 2C - SIMILAR RESULTS TO UNIT 3 PUMPS, HOWEVER, IMPELLER WEAR RINGS WEAR NOT COMPLETELY DETACHED

, WEAR RING MATERIAL IMPELLER - A182 GRADE B6 (CHROME) WITH ROCKWELL C HARDNESS OF 33 TO 39 ,

1 CASING - CAST IRON WITH HIGH NICKEL CONTENT CAUSE OF WEAR RING FAILURES LICENSEE HAS CLASSIFIED FAILURES AS IGSCC ,

0THER MATTERS:

- . INSPECTION OF REMAINING PEACH BOTTOM UNIT 2 PUMPS

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FLOW ANOMALIES ON PUMP 2A ATTRIBUTED TO PUMP INLET VANES INSPECTION OF BROWNS. FERRY PUMPS,BEING CONSIDERED-  ;

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REACTOR SCRAM

SUMMARY

WEEK ENDING 12/08/85

. I. PLANT SPECIFIC DATA DATE _ SITE UNIT POWER CAUSE COMPLI- COMMENT CATIONS I ,

10/02/85 SUSOUEHANNA -

t 1 100 EQUIP /ELEC YES U2 TRP 12/02/85 SUSQUEHANNA 2 81 EQUIP /ELEC YES U1 TRP 12/03/85 DIABLO CANYON / 2 20 EQUIP / MANUAL YES SI 12/03/85 CRYSTAL RIVER '

3 93 EQUIP /ELEC NO 12/04/85 PALO VERDE .

1- 54 EQUIP /ELEC NO 12/05/85 RANCHO SECO f 1 91 EQUIP / BOP YES 'SI 3 12/fj6/85 ZION., .,

1- O PERSONNEL YES SRM FAILURES

'12/06/85 WATERFORD g s 100 PERSONNEL /CPC. NO 12/07/85 CRYSTAL RIVER. ( 3 '(O PERSONNEL NO 12/07/85- BIG ROCK PT 1 t 15 EQUIP / MANUAL ~YES HI SDV LEVEL J12/OS(85 CALLAWAY- 2 1' 90~ EQUIP / BOP NO 12/08/95 LIMERICK i l j 64-EQUIP /RECRC PMP NO k-

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS IN WEEK

, ENDING 12/08/85 1984 WEEK ITEM ACTUAL (5) NORMALIZED (6) AVERAGE (3)(4)

SCRAMS AB0VE 15% POWER-EQUIP, RELATED 8 7.2 3.9 (60%)

PERS. RELATED I7) .1 .9 1.8 (28%)

OTHER I8) 0 0 8 (12%)

SUBT0TAL 9 8.1 6.5 (68%)

SCRAMS BELOW 15% POWER EQUIP, RELATED 1 .9 1.4 (46%)

PERS RELATED 2 1.8 1.4 (46%)

OTHER 0 0 0.2 (8%)

SUBT0TAL 3 2.7 3.0 (32%)

MANUAL SCRAMS (9) 2 1.8 1.1 AUT0._ SCRAMS (9) 1Q 9.0 8.4' TOTAL AUTO. & MANUAL SCRAMS-(ALL POWER 12 10.8 9.5 (100%)

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NOTES (1) PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50,72 REPORTS FOR THE WEEK 0F INTEREST, PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN, SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE,

(?) RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM (3) 1984 INFORMATION DERIVED FROM AE0D TRENDS AMD PATTERNS REFORT OF UNPLANNED REACTOR TRIPS IN 1984, DATED 9/11/85, (SEE TABLES 2,0-2, 2,1-4, AND 2,2-1) WEEKLY DATA DETERMINED BY TAKING TOTAL

-TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR, (4) IM 1984, THERE WERE A TOTAL OF 492 AUTOMATIC AND MANUAL REACTOR TRIPS AT 83 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN. AVERAGE RATE'0F 5,9 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 9,5 TRIPS PER WEEK FOR ALL REACTORS, (5) BASED ON 9? REACTORS HOLDING A FULL POWER LICENSE, AS OF 11/30/85, (6) FORMALIZED VALUES ALLOW COMPARIS0N TO 1984 DATA BY FULTIPLYING ACTUAL 1985 VALUE BY: (83 PEACTORS IN 19P8)= 0.90 (92 REACTORS IN 1985)

(7) PERSONNEL RELATED PROBLEMS, AS USED IN AEOD TRENDS AND PATTERPS REPORT, INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS, (8) "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO SOME COMBINATION OF HARDWARE FAILURE AND HUMAN ERROR, ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE, (9) MANUAL. SCRAMS ONLY AFD AUTOMATIC SCRAMS ONLY ARE DER!VEn FRSM TOTAL AUTOMATIC AND MANUAL SCRAMS DATA PROVIDED IN TABLE 7,0-2 0F AEOD PEPORT,

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P. age No. 1

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OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MIETINti 65-26 ON DECEMBER 9 ,1985 (IN ASCENDING MEETIN6 DATE, NSSS VEND 09, FAC!lliY ORIER)

MEETINS FACILITY RESPONS!!LE TASK DESCRIPT!0N SCHEDULE CLOSED DATE ~ C0",MENTS NJiER/ hS!! VENOCR/ DIVIS! N COMPLET. If DOCUMENT, MEETINS EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC.

CATE CRYSTAL RIVER 3 ICSB/ ROSA,F. CONSIDER NEED FOR ADDITIONAL 12/30/85 DPEN / / ICSB CONSIDERIN3 01/03/E5 Bei / TEMP. LOSS / RECU!REMENTS ON ALARMS / 09/30/85 CCONEE 1 LOSS OF OF kNI 12/25/94 ANNUNCIATCRS 07/30/85 ANNUNCIA.

(4/25/B5) IN ANAL.

OF REQUIREMENTS.

85-13 POINT LEACH IE /LONS, S. DRAFT IE NOTitE ON PT. BEACH 12/13/95 0 FEN // DRAFT IE NOT!CE IN 09/13/85 W / SAFETY ORAB/CARU50,M. EVENT.CCNS!!;ER TEMP. INSTR.FOR 10/18!B5 CONCURRENCE.NRR INJECTION RES.!NSPECTOR RESARDING 09/13/85 INPUT COMFLETE MIN!-FLOW C CIRC COMPLIAhCE WITH APP.K DESIBIL IEFICIENCY 85-13 TURLEY PO!NT 3 DE! /PA;R, D. REVIEu ALE 20ACf 0F GOVERNOR 01/05/86 OPEN / /

08/13/85 W / POST-TRIP / DEE!6N ON TURBINE DRIVEN AFW 10/13/B5 LDSS OF AFW FL?.PE /~/

B5-14 SEGUDYAH DL /STAHL C INiilATE STAFF REVIEW OF TVA 12/30/85 OPEN / /

/

06/26/95 W / UM!iS I & 2 SUIMITTALS 09/30/85 VCLL1TARY //

SHUTDONN BY TVA BECAUSE OF EG INA;EGUACIES 83-21 TROJAN DS! INERMIEL J REEIAMINENEEDFORTHIS 01/31/86 OPEN / /

IC428/85 / INTRECT / INSTALLAflCN AND GENERIC //

SETPOINTSFOR APPLICABILITY

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TRIP OF AFW PLMPS On LOW

, SUCT!DM PRES!UPE B5-22 MC EUIRE 1 & 2 IE /R SINSH C0hSIDER ISSUANCE OF AN IE 12/20/85 OPEN / /

!!/04/85 / FJAL Uhli / NOTICE  !!/20/85 TDIP DN LOSS Or //

INSTRUMINT AIR 85-23 950NNS FERRY IE /F KANT0R DISCUSS WITH FEMA NRC FOSITION 12/18/85 OPEN ./ /

11/1B/95 / OFFS!TE / WITH REEARD TO EMER6ENCY PLAN //  :.

C0hTMIN. EIERCISE / /

INCIDENT DUP!NG ,"

EMERS!NCYPLAN EIE5CISE B5-26 RANCHO SECD DHFS/ RUSSELL R WILL REVIEW WITH H R DENTON THE 12/31/95 DPEN / /

12/09/85 / REACTOR TRIP /' EIISTING POLICY ON INFORMAil0N / /

PLACED IN LICENSED 0*ERATOR //

FILE

Page he. 2

, OPE 8ATINS REACTORS EVENTS MEETING FOLLONUP ITERS AS OF MEETING E5-26 DN DECEMBER 9 ,1995 (IN ASCENDING MEETING DATE NSSS VEh30R, FACILITY 0;tER)

FLEETING FACILITY RESPONSIBLE TASF DESCR!Fi!0N SCHEDULE CLOSED

• BATE - COMENTS NUME;/ NSSS VECCR/ DIVISION / COMFLET. SY DOCUT NT, MEET!h5 EVEhi DESCRIP. INDIVIDCAL DATE(5) MEETING,ETC. ,

DP: l i

l EM6 RANCFD !!CD' RSB /LANT! E DETERMINE THE NEED FOR 01/30!E5 0 FEN / /

12/H!E! / REACICE TRIP / 0FERAi!0N CF THE H16H FRESSURE //

INJECT 10N SYSTEM DURING THE // i DEC. 5,1985 DVERHEATING EVENT -l AT RANCHD SECO r I

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. Pap N . , 1 OPERATINS REACTORS EVENTS MEETINS FOLLOWLP ITEMS AS CF MEETING 85-26 ON DECEMfER 9,1995

(!N ASCENDINS MEET!N6 DATE, NS$$ VENDOR, FACILlif ORDER)

MEETINS FACILITY- RESPONSIBLE TASL DESCRIPTION SCHEDULE CLOSECCATE C0"MENTS NUMIER/ ; NSSS VENDCRI DIVISION / COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC.

DATE CRYSTAL RIVER 3 !CSBIROSA F. CONSIDER NEED FOR ADDITIONAL 12/30/85 0 FEN / / ICEB CONSIDERINS 01/03/25 fW / TEMP. L0iS / REOUIREMENTS ON ALARMS / 09/30/85 OCONEE 1 LOSS OF 0F NN! 12/29/E4 ANNUNCIATORS 07/30/65 ANNUNCIA.

(4/25/25) IN ANAL.

OF REQUIREMENTS.

85-!3 POINT BEACH IE /LONS, S. DRAFT !E NOTICE ON PT. BEACH- 12/13/25 CLO!ED 12/13/85 DRAFT !E N311CE IN C/13/85 W / SAFETY ORAB/CARUSD,M. EVENT. CONSIDER TEMP.!NSTR.FOR 10/19/85 IE NOTICE B5-94 CONCU5RENCE.NRK INJECTION RES.!NSFEtiOR REGAPDINS 09/13/E5 ISSUED 12/13/85 INFUT COMFLETE MIN!-FLOW RECIRC COMFLIANCE WITH AFP.K DESIGN DEFICIENCY 85-13 TUCrEIPOINT3 DS!/PAM,D. REVIEW A:EQUACY OF BOVERNCR 01/05/86 OPEN / /

02/13/25 W / POST-TRIP / DESIGN ON TURI!NE DRIVEN AFW 10/13/85 LOSS OF AFW PU"F C //

B5-14 SEGUDYAH DL /STAHL C IN!T! ATE STAFF REVIEW OF TVA 12/30/85 0 FEN //

06/26/85 W / UNITS 1 & 2 / SUBMITTALS 09/30/85 VOLUNTARY //

SHUTDOWN IY TVA SECA"SE OF EQ INADEGUACIES 95-21 TROJAN DSI /WERMIEL J REEIAMINE NEED FOR THl$ 01/31/86 OPEN / /

10/28/B5 / INCORRECT. / INSTALLAT!DN AND 6ENERIC //

SETPC!kTS FOR APPLICABILITY //

TRIP OF AFW PUMPSONLOW SUCTION PRESSURE 85-22 MC SUIRE I & 2 IE /R SIN 6H CONSIDER ISSUANCE OF AN IE 12/20/85 CLOSED 12/13/85 11/04/!5 / CUAL UNIT / NOTICE  !!/20/65 IEN0TitEWILL TRIP DN LOSS OF '/ / BEISSUED INSTRUMENTAIR 95-23 150WNSFERRY IE /F KANTOR DISCUSS WITH FEMA NRC POSITION 01/30/06 0*EN / / TO IE DISCUSSED ,

11/18/85 / OFFSITE / W!iHRE6ARD10EMERSENCYPLAN 12/18/85 DUR!hS NEIT CONTAM!N. EIERCISE // FEMA /NRC STEERINS INCIDENTDURING COMMITTEE P]NTHLY EMERSENCYPLAN MEET!hS EIEPCISE ,-

85-26 RANCHO SECO DHFS/ RUSSELL R WILL REVIEW WITH H R DENTON THE 12/31/95 0 FEN / /

12/09/25 / REACTOS TRIP / EllSTING POLICY ON INFCRMAil0N //

PLACED IN LICENSED DPERATOR //

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, OPERATING REACTORS EVENTS MEET!h6 FOLLONUP ITEMS 4 AS OF MEE11NG 85-26 DN MCEMBER 9,1985 (IN ASCENDING E ETIN6 DATE, NSSS VENDOR, FACILITY ORDER)

EETING , FACILITY . RESPONSIBLE TASL DESCR!FTIC4 SCHEDULE CLOSEDDATE COMMENTS t NUMBER / .NSSS VENXR/ O! VISION! COMPLET. BYSOCUMENT, j KET!N6 EVENT M SCRIP. INDIVIDL'AL DATE(S) EETING,ETC.

BATE B5-C6 RANCHD SECO RS! /LANTI E IETERMINE THE NEEI FOR 01/30/85 08EN / /

12/09/05 I EACTOR TRIP / QPERATION OF THE H16H PRESSURE //

INJECT!DN SYSTEM DL' RING THE I /

DEC. 5,1965 OVERHEATING EVENT AT RANCHO SECD t

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