ML20138M928

Summary of Operating Reactor Events Meeting 85-25 on 851202 Re Listed Events.Attendee List,Summary of Events Discussed & Viewgraphs Encl

ML20138M928
Person / Time
Site:	Three Mile Island, Crystal River, Diablo Canyon, San Onofre, 05000000
Issue date:	12/12/1985
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8512230222
Download: ML20138M928 (16)

Text

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. DEC 121985 p

MEMORANDUM FOR: Har.31d R. D;nton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON DECEMBER 2, 1985 - MEETING 85-25 On. December 2, 1985, an Operating Reactor Events meeting (85-25) was held to brief the Office Director, the Division Directors and their representatives on events _which occurred since our last meeting on November 25, 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 cannot be met.

Original Signsd By:

Gary M. Folahan, Director Operating Reactors Assessment Staff

Enclosures:

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.....- DEC 121Ng 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 2, 1985 - MEETING 85-25 On December 2, 1985, an Operating Reactor Events meeting (85-25) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on November 2F,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 cannot be met.

N Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page e

.o Harold R. Denton -?-

cc: D. Eisenhut H. Silver J. Taylor. R. Dudley C. Heltemes J. Thoma T. Murley, Reg. I J. Stolz J. Nelson Grace, Reg. II G. Lear J. Keppler, Reg. III S. Varga R. D. Martin, Reg. IV H. Schierling

'J. B. Martin, Reg. V R. Starostecki, Reg. I R. Walker, Reg. II 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

-8. Sheron D. Ziemann J. Knight D. Crutchfield G. Lainas c, V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan K. Seyfrit

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.I ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-25)

DECEMBER 2, 1985 Name Division Name Division H. R. Denton NRR R. Dudley PAD #1/NRR D. G. Eisenhut NRR C. Grimes ISAPD/NRR G. M. Holahan ORAS/NRR J. T. Beard ORAS/NRR M. J. Virgilio ORAS/NRR T. S. Rotella BWD1/NRR M. Caruso ORAS/NRR E. Jordan IE D. Houston ACRS R. L. Baer IE/DEPER F. A11enspach F0B-B/NRR T. P.-Speis OSR0/NRR J. Stone IE/VPB F. Rowsome HFIB/DHFT/NRR J. Henderson IE/DEPER J. Stolz PD-6/NRR H. Silver ORB 4/DL/NRR H. L. Thompson PWR-A/NRR B. Regan- F0P/PWR-B/NRR J. P. Knight PWR-A/NRR T. M. Novak PWR-A/NRR F. Schroeder PWR-B/NRR D. Crutchfield PWR-8/NRR R. Bernero DBL /NRR E. Weinkam TOSB/NRR F. J. Miraglia PWR-B/NRR S. Black TOSB/NRR J. A. Zwolinski OBLPD#1/NRR B. Mozafari ORB 4/DL/NRR J. O. Thoma PD-6/NRR J. Lyons PPAS/NRR H. Schierling PWR-A/NRR J. E. Dyer IE/0RPB D. Tarnoff ORAS/NRR

'J. Shapaker PSB-A/NRR J. Singh PSB-A/NRR W. P. Gammill BSB-A/NRR V. Benaroya F08-A/NRR

-S.-Long DEPER/IE H. Bailey DEPER/IE S. Varga PWR-A/NRR R. Freeman AGOD/ROAB K. Seyfrit AEOD T. Sullivan . PEBA/NRR G. Lear PD#1/NRR H. L. Serkiz DSK0/NRR

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OPERATING REACTORS EVENTS BRIEFING (85-25)

DECEMBER 2, 1985 SAN ON0FRE. UNIT 1 LOSS OF 0FFSITE POWER AND FEEDWATER SYSTEM DAMAGE - UPDATE N0, 1 CRYSTAL RIVER UNIT 3 MFW FAILURE /AFW ACTUATION / REACTOR TRIP DIABLO CANYON UNIT 2 APPARENT REACTOR TRIP BREAKER FAILURE TMI UNIT 1 REACTOR TRIP DN OVERPRESSURE O

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SAN 0NOFR?-UNIT 1 - LOSS OF 0FF-SITE POWER AND FEEDWATER SYSTEM DAMAGE - UPDATE NO, 1 NOVEMBER 21, 1985 (R, DliDLEY, NRR)

~ PROBLEM:

LOSS 0FLOFFSITE POWER AND FEEDWATER SYSTEM DAMAGE AND LEAK

. CAUSED.BY WATER HAMMER SIGNIFICANCE:

COMPLICATED: WATER HAMMER EVENT-NOT YET FULLY UNDERST0OD; POSSIBLE GENERIC IMPLICATIONS LCIRCUMSTANCES:

LOSS OF AUX, TRANSFORMER C DE-ENERGIZED SAFETY BUS 2C AND

. EAST MAIN FEEDWATER PUMP (ELECTRIC-DRIVEN)

WEST MFW PUMP CONTINUED TO RUN SINCE POWERED FROM SAFETY-BUS IC IIT HYP0 THESIS IS THAT CHECK-VALVE IN EAST MFW PIPING DIDN'T SEAT ALLOWING WEST MFW PUMP TO OVERPRESSURIZE EAST FW TRAIN TUBES IN STH-POINT FW HEATER RUPTURED, FAILING SHELL (15' X 2' HOLE)

WEST MFW PUMP STOPPED ABOUT 30 SEC, LATER AFTER OPERATORS TRIPPED REACTOR TURBINE-DRIVEN AFW PUMP AUT0-STARTED ON LOW SG LEVEL AND FED STEAM GENERATORS AFTER 3 MIN, WARM-UP, AS DESIGNED

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• ELECTRIC DRIVEN AFW PUMP STARTS WHEN OFF-SITE POWER RESTORED. TOTAL AFW FLOW 100-150 GPM TO EACH SG, 6 MIN.

• AFW FLOW REDUCED TO ZERO, THEN INCREASED TO 25 GPM SINCE RCS C00LD0WN IS T00 RAPID, RCS PRESSURE WAS 1800 PSIG; SIAS SETPOINT IS 1750 PSIG, 15 M!n,

• LOUD BANG HEARD BY OPERATOR WHO ALSO OBSERVED STEAM ON TURBINE MEZZANINE LEVEL IIT HYPOTHESIS IS THAT CHECK VALVE IN "B" FW TRAIN DIDN'T CLOSE, REDUCTION OF AFW FLOW ALLOWED STEAM BUBBLE FROM SG "B" TO FLOW INTO FW LINE. COLD AFW CONTACTED STEAM BUBBLE, CONDENSING IT RAPIDLY, SLUG 0F WATER IN "B" FW LINE PULLED TOWARD DIRECTION OF CONDENSATION (TOWARD AFW SUPPLY) CAUSING WATER HAMER IN DIRECTION AWAY FROM SG, FOLLOW-UP:

IIT LEFT SITE ON DECEMBER 1, AFTER NINE-DAY STAY; REPORT

IS IN PREPARATION, DUE BY MID-JANUARY' TIA INITIATED BY R-V, TRANSFERRING WATER HAMMER EVALUATION TO NRR; PWR-A DIV. HAS TECHNICAL LEAD LICENSEE EVALUATING CONDITION OF FW PIPING NRR REVIEWING PAST SERs, ETC., WHICH MAY BE RELATED TO EVENT

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= CRYSTAL RIVER UNIT 3 - MFW FAILURE /AFW ACTUATION /PEACTOR TRIP NOVEMBER 22, 1985, (H. SILVER, NRR)

PROBLEM:

OPERATOR ERROR CAUSED PARTIAL MFW FAILURE, AFW ACTUATION AND REACTOR TRIP SIGNIFICANCE:

INAPPROPRIATE PROCEDURES AND TRAINING (MFW LOW POWER OPERATION, AFW TERMINATION)

POST-TRIP REVIEW PROCEDURES ALLOWED RESTART W/0 FULL KNOWLEDGE OF THE EVENT UNNECESSARY AFW CHALLENGE SAFETY-SIGNIFICANT COMPONENTS MAY NOT BE FULLY OPERABLE CIRCUMSTANCES:

PLANT AT 207 POWER, BEING SHUTDOWN TO REPAIR DROPPED ROD-OPERATORS CAUSED LOW MFW FLOW IN ONE OTSG AFW ACTUATED PROPERLY, SECURED QUICKLY BY OPERATORS (DIFFICULTY IN CLOSING AFW STEAM ADMISSION VALVE).

LOW SG LEVEL CAUSED REACTOR TRIP ON HIGH PRESSURE PORV FAILED TO OPEN ON COMMAND, AND SUBSEQUENTLY THE BLOCK VALVE WAS CLOSED.

AFTER TRIP, AFW STEAM ADMISSION VALVE OPENED SPURIOUSLY, CAUSING MILD OVERC00 LING EVENT FOLLOWUP:

OPERATORS BEING TRAINED ON APPROPRIATE ACTIONS - MFW AND AFW (LICENSEE)

MONTHLY AFW SURVEILLANCE TEST SATISFACTORILY PERFORMED.

STEAM ADMISSION VALVE PROBLEM BEING STUDIED. (LICENSEE)

PORV PROBLEM IDENTIFIED, BEING REPAIRED (LICENSEE)

RESTART REVIEW PROCEDURES BEING MODIFIED (LICENSEE)

REG. Il CONSIDERING ENFORCEMENT ACTION RE INFO FLOW AND POST-TRIP REVIEW

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DIABLO CANYON tlNIT 2 - APPARENT REACTOR TRIP BREAKER FAILURE NOVEMBER 28, 1985, (J. T, BEARD, NRR)

PROBLEM: ONE RTB TRIPPED; OTHER RTB DID NOT TRIP SIGNIFICANCE: INADVERTENT PLANT TRIP CIRCUMSTANCES:

RTBs ARE W TYPE DB-50, UNLIKE D. C, COOK PLANT, RTB AUT0-SHUNT TRIP FEATURE IS INSTALLED AT THIS PLANT, PLANT AT 0,5% GETTING READY TO LATCH TURBINE; 18C REPAIR ACTIONS HAD S/G #2 LEVEL CHANNEL TRIPPED (LEAKING ROOT VALVE)

WHEN TilRBINE STOP VALVES OPENED, G0T INRUSH OF STEAM FLOW M0MENTARY REACTOR TRIP SIGNAL ON STEAM FLOW / FEED FLOW MISMATCH AND S/G LEVEL LOW, RTB "A" OPENED: RTB "B" DID NOT; RODS INSERTED, PLANT MANUALLY SCRAMMED PER PROCEDURE (RTB "B" OPENED)

FOLLOWUP:

POST-TRIP TESTING DETERMINED:

TRIP SIGNAL VERY BRIEF (LESS THAN 30 MILLISECONDS)

RTB "A" TRIPS CONSISTENTLY ON SIGNAL OF 20 MILLISECONDS RTB "B" TRIPS CONSISTENTLY ON SIGNAL 0F 40 MILLISECONDS OR LONGER IEB 85-02 UVTA TRIP FORCE MARGIN TESTS SUCCESSFUL RTBs PERFORM SATISFACTORILY OPERATING STAFF HAD NOTICED " FLICKER" 0F BISTABLE LIGHTS ON FLOW MISMATCH ON PREVIOUS TURBINE LATCHES, P: ANT RE-STARTED ON NOVEMBER 30, 1985 -

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?Dil UNIT 1 - REACTOR TRIP ON OVERPRESSURE

m. DECEMBER ], 1985 (JOHN THOMA, NRR)

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PR0BLEM: REACTOR TRIPPED ON OVERPRESSURE . STEAM GENERATOR CODE SAFETIES LIFTED, AS EXPECTED, LICENSEE REPORTED A

. RELEASE 0F SMALL' AMOUNTS OF RADI0 ACTIVITY T0 THE ENVIRONMENT AND MEDIA INTEREST OCCURRED, LICENSEE HAS.PREVIOUSLY EXPERIENCED SAME TYPE EVENT, ALSO

_ WITH THE SAME MEDIA INTEREST-SIGNIFICANCE: MEDIA INTEREST CIRCUMSTANCES:

, PLANT 0PERATING AT 75% POWER PER START-UP PROGRAM

-LOAD DISPATCHER ALLOWED GRID' VOLTAGE TO DRIFT HIGH IN THE ALLOWED

" BAND, PROTECTIVE RELAY MONITORING GRID VOLTAGE OFF THE. MAIN TRANSFORMER SENSED AN OVERVOLTAGE CONDITION AND TRIPPED THE

-MAIN GENERATOR OUTPUT BREAKERS, LTURBINE-GENERATOR TRIP LED TO AN AUTOMATIC TRIP ON RCS HIGH PRESSURE-AT 2 A.M.

DURING TRANSIENT, OTSG SAFETIES OPENED AS DESIGNED, LICENSEE REPORTED A SMALL RADI0 ACTIVE RELEASE TO ENVIRONMENT,

. MEASURED PRIMARY TO SECONDARY LEAKAGE BASED ON GRAB SAMPLES:

WAS 0,08 GPH ON NOVEMBER 30, T.S. LIMIT IS 1 GPM (60 GPH),

TRIP REC 0VERY WAS NORMAL-AFFECTED RELAY SETPOINT DETERMINED TO BE-LOW; RELAY REPLACED, WHILE SHUT DOWN, LICENSEE REPAIRED THREE FEEDWATER VALVES.

RX CRITICAL AT 2 P.M. BUT REMAINED LESS THAN 1% POWER UNTIL 8 P.M.

WHILE COMPLETING FEEDWATER VALVE REPAIRS, IP/ 4 A.M. DECEMBER 2, ~1985, THE PLANT WAS AT 71% POWER.

-F0LLOWUP:

LICENSEE INVESTIGATING CAUSE OF RELAY SETPOINT BEING LOW BUT EXACT CAUSE MAY NOT BE FOUND, DURING SHUTDOWN, RECURRENCE OF EARLIER PROBLEM;THAT IS OTSG "A"

. SAFETY VALVES OPENED MORE THAN EXPECTED (3 TIMES VICE ONCE FOR OTSG "B"), OPERATIONAL PROBLEM UNDER INVESTIGATION BY LICENSEE, PLANT CURRENTLY LIMITED T0 71% REACTOR POWER DUE TO REACHING B & W OPERATIONAL LIMIT ON OTSG LEVEL, LICENSEE AND B a W IN NEGOTIATIONS TO RESOLVE OTSG LEVEL LIMITIATION, 4

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SCRAM STATISTICS-WEEK ENDING 12/01/85 (SUN, MIDNIGHT)

I, PLANT SPECIFIC DATA (1)

TOTAL **

SCRAM INITIAL TO DATE COMPLICATIONS DATE PLANT POWER CAUSE THIS YEAR REPORTED (2) 11/25/85 GINNA 100% EQUIP.-B0P NO 11/25/85 COOK I 78% PERSONNEL AFW PUMP-11/26/85 DIABLO 2 75% EQUIP.-B0P

• SI INIT, 11/28/85 DIABLO 2 1% EQUIP.-B0P TRIP BKR, FAILURE 11/28/85 RIVER BEND 3% EQUIP.-B0P NO 11/29/85 INDIAN PT. 3 100% PERSONNEL NO PCH, BOTTOM 2

• 11/29/85 30% EQUIP.-B0P NO 11/30/85 INDIAN PT, 3 11% PERSONNEL N0 11/30/85 INDIAN PT, 3 0% E0 VIP. -INST,

• N0 12/01/85 DIABLO 2 40% EQUIP. -B0P NO 12/01/85 TMI-1 75% EQUIP, -B0P

• NO

• WILL COMMENCE THIS COUNT ON 1/1/86

• AVERAGE ANNUAL SCRAM FREQUENCY IN 1984 WAS 5,9 TRIPS / PLANT / YEAR (4) f

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i II, COMPARIS0N OF WEEKLY STATISTICS WITH INDUSTRi~ AVERAGES SCRAMS IN WEEK NORMALIZED '84 ITEM ENDING 12/01/85(5) WEEK, AVER,(3,6)

SCRAMS AB0VE 15% POWER EQUIP, RELATED 5,0 4,3 (60%)

PERS, RELATED I7) 2,0 2,0 (28%)

-0THER(8) 0 ,0 0,9 (12%)

LSUBT0TAL '7,0 7,2 (68%)

> SCRAMS BELOW 157 POWER EQUIP, RELATED 3.0 1,6 (46%)

PERS. RELATED 1,0 1,6 (46%)

OTHER- 0,0 .22 (8%)

SUBT0TAL 4.0 3,4 (32%)

-MANUAL' SCRAMS (9) 0,0 1,3 AUT0, SCRAMS (9) 11,0 9,3 TOTAL AUT0, a MANUAL -

SCRAMS ~(ALL POWER 11,0 10,6 (100%)

LEVELS)

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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, (2) REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM (3) 1984 INFORMATION DERIVED FROM AE0D TRENDS AND PATTERNS REPORT 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) IN 1984, THERE WERE A TOTAL OF 492 AUTOMATIC AND MANUAL REACTOR TRIPS AT 83 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5,9 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 9,5 TRIPS PER WEEK FOR ALL REACTORS, (5) BASED ON 92 REACTORS HOLDING A FULL POWER LICENSE, AS OF 11/30/85.

(6) NORMALIZED VALUES ALLOW COMPARIS0N TO 1985 DATA BY MULTIPLYING ACTUAL 1984 VALUE BY: (92 REACTORS IN 1985)= 1,11 (83 REACTORS IN 1984)

(7) PERSONNEL RELATED PROBLEMS, AS USED IN AE0D TRENDS AND PATTERNS 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 AND AUTOMATIC SCRAMS ONLY ARE DERIVED FROM TOTAL AUTOMATIC AND MANUAL SCRAMS DATA PROVIDED IN TABLE 2,0-2 0F AE0D REPORT,

l Page No, I l 0FERATINS REACTORS EVENTS MEETINS FOLLOWUF ITEMS AS OF MEETIN6 85-25 DN DECEMBER 2 ,1985 (IN ASCENDINS MEEi!NG DATE, NSSS VENDOR, FACILITY ORDER)

MEETIN6 FACILITV RESPONSIBLE TASK DESCRIPi!0N SCHEDULE CLOSED DATE COMMENTS NUM!!R/ NSSS VEN!DR/ DIVISION! COMPLET. BY DOCUMENT, MEETING EVENTDESCRIP.- INDIVIDUAL DATE(S) MEETING,ETC.

DATE CRYSTAL RIVER 3 !CSB/ ROSA,F. CONSIDER NEED FOR ADDITIONAL 12/30/85 OPEN / / ICSB CONSIDERINS 01/03/85 BW / TEMP. LOSS / REQUIREMENTS ON ALARMS / 09/30/85 0C0 HEE I LOSS OF 0F NN! 12/28/84 ANNUNCIATORS 07/30/85 ANNUNCIA.

(4/25/05) IN ANAL.

OF REQUIREMENTS.

B5-12 SEABROOK DSI / MARSH' ANALY!E SAFETY IMPLICATIONS OF 12/06/85 CLOSED 12/04/85 07/23/85 W / CROSBY MAIN / VALVE FLOW DEFICIENCY 10/30/85 !!/22/85 NEMD STEAM SAFETY 09/30/25 R.BERNER0 TO H.

VALVEFLOW THOMPSON DEFICIENCY 12/04 85-13 POINT BEACH IE /LONS, S. DRAFT !E NOTICE ON PT. BEACH 12/13/85 OPEN / / DRAFT !E NOTICE IN 08/13/25 W / SAFETY ORAB/CARUSD,M. EVENT. CONSIDER TEMP. INSTR.F0R 10/18/85 CONCURRENCE.NRR INJECTION RES.!NSPECTORRE6ARDING 09/13/85 INPUT COMPLETE MIN!-FLOW RECIRC COMPLIANCE WITr! AFF.K DES!6N DEFICIENCY 85-13 TURLEY POINT 3 DSI /PARR, D. REVIEW ADEQUACY OF 60VERNOR 01/05/86 OPEN / /

C/13/25 W / POST-TRIP / DESIGN ON TURBINE DRIVEN AFW 10/13/85 LOSS OF AFW PUMPS //

B5-14 'SEQUDYAH DL ,STAHL C INITIATE STAFF REVIEW 0F TVA 12/30/85 OPEN / /

08/26/25 W / UNITS 1 & 2 / SulMITTALS 09/30/85 VOLUNTARY //

SHUTDOWN BY TVA.

BECAUSE OF ED INADEDUAC!ES 85-15 PEACH BOTTOM 3 DE /LIAW B D DETERMINE WHAT FUTURE ACTION  !!/30/85 CLOSED 12/05/85 09/09/E5 / NEW P!FE DE /HA!ELTON W NEEDED ON SENERIC BASIS 10/15/E5 DEC.5,1985 MEM0 CRACK // B.D.LIAW TD

-INDICATIONS 6.HOLAHAN 85-21 TROJAN DS! /WERMIEL J REE! AMINE NEED FOR THIS 01/31/26 OPEN / /

10/28/85 / !NCORRECT / INSTALLATICN AND GENERIC / /

SETP0!NTSFOR APPLICABILITY //

TRIPOFAFW PUMPSONLOW SUCTIONPRESSURE B5-22 GRAND 6ULF DE /HAZELTON W FOLLCWUP REGARDING 6ENERIC 12/04/65 CLOSED 12/05/65 11/04I85 / / IMPLICAi!0NS AND ADEQUACY OF / / DEC.5,1925 MEMO RECIRCULATION IHS1 // B.D.LIAW TO 6.

P!FE CRACK HOLAHAh L

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' pge Ns, - 2 OfERATIN6 REACTORS EVENTS MEETIN6 FOLLONUP !TEMS 0 AS 0F MEETING 85-25 ON DECEMBER 2 ,1985 (IN ASCENDING MEETIN6 DATE, NSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESPONSIBLE- TASK DESCRIPTION SCHEDULE CLOSED BATE COMMENTS NUMBER / NSES VENDCRI DIVIS!CN/ COMPLET. BY DCCUMENT, MEETING EVENT M SCRIP. INDIVIDUAL DATE(S) MEETIN6,ETC.

DATE

.35-22 MC SUIRE 1 & 2 IE /R SINGH' CONSIDER ISSUANCE OF AN IE 12/20/85 DPEN / /

!!/04/85 / DUAL UNIT / NOTICE  !!/20/85 TRIP DN LOSS OF //

INSTRUMENT AIR 85-23 BRONNS FERRY IE /F KANTCR DISCUSS WITH FEMA NRC POSITION 12/18/85 DPEN / /

~!!/18/95 / OFFSITE / N!TH RC6ARD TO EMER6ENCY PLAN //

CONTAM!N. EIERCISE / /

INCIDENT DURING

'EMEF6EN:VFLAN EXERCISE t

b.