ML20203M943
| ML20203M943 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Pilgrim, Turkey Point, River Bend, 05000000 |
| Issue date: | 04/25/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8605020253 | |
| Download: ML20203M943 (19) | |
Text
{{#Wiki_filter:I APR k 51986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation t FROM: Gary M. Holahan, Director s Operating Reactors Assessment Staff
SUBJECT:
SUPMARY OF THE OPERATING REACTORS EVENTS MEETING ON April 21, 1986 - MEETING 86-13 On April 21, 1986, an Operating Reactor Events raceting (86-13) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting cn April 14, 1986. The list of attendees is included as Enclosure 1. The events discussed and the significant eleirents of these events are presented in Enclosure 2. In addition, the assignment of folicw-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3. Ccirpletion dates have been assigned for items in Enclosure 3. Each assignee shculd review Enclosure 3 with regard to their respective responsibilities. Note that several assignments are approaching the due date. Please be responsive and advise ORAB (D. Tarr.cff, x29526) if the target completion date cannot be met.
/v/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
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April 25, 1986 NEKORANDUM FOR: Harold R. Denton. Director - Office of Nuclear Reactor Regulation FROM: Gary fl. Holahan, Director Operating Peactors Assessment Staff '{
SUBJECT:
SUMfiARY OF THE OPERATING REACTORS EVENTS MEETING ON April 21, 1986 - MEETING 86-13 f: On April 21, 1986, an Operating Peactcr Events meeting (86-13) was held to . brief the Office Director, the Division Directors and their representatives on] events which occurred since our last meeting on April 14, 1986. The list of 1M attendees is included as Enclosure 1. The events discussed and the significant elements of these events are presen in Enclosure 2. In addition, the assignment of follow-up review responsibili was discussed. The assignments made during this meeting and the status of ' previous assignments are presented in Enclosure 3. Each assignee Completion dates have been assigned for itens in Enclosure 3. should review Enclosure 3 with regard to their respective responsibilities. ;' t!cte that several assignments are approaching the due date. Please be res and advise ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.
' a') y )" ,
Gary M/ . Ho ahan, Director
, Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ encl: , See next page
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APP 2 b E86 ' Harold R. Denton cc: D. Eisenhut M. Wegner J. Thylor P. Leech C. Heltemes J. Zwolinski T. Murley, Reg. I S. Stern-J. Nelson Grace, Reg. 11 W. Butler J. Keppler, Reg. III G. Gears R. D. Martin, Reg. IV E. Weiss J. B.11artin, Reg. V D. Muller R. Starostecki, Reg. I D. Mcdonald ; R. Walker, Reg. II L. Rubenstein
'C. florelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Berrero T. Speis W. Russell T. I;ovak F. Schroeder W. Houston B. Sheron D. 7iemann D. Crutchfield G. Laines V. Benarcya W. Regan D. Vassallo E. Jorden E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin
b [ ENCLOSURE 1 LIST OF ATTENDEES 0PERATING REACT 0_RS_ EVENTS BRIEFIfiG (?6-13) April 21, 1986 } NAME DIVISION NAME DIVISION H. Denton NRR G. Gears NRR/ DBL J. Stone IE/VPB M. Caruso NRR/0 RAS L. Kelly NRR/0 RAS V. Benaroya NRR/PWR-A D. Thatcher NRR/DSR0 D. Basolekas RES/DET N. Clausen OCM C. Ader 0CM D. Vassallo NRR/F0B/ DBL D. Mcdonald. NRR/PWR-A j E. Weinkam hRR/FL'R-A ?!. Casada NOAC/0RNL D. Allison IE/EAD E. L'ciss IE/EAB P. Koutanien.i IE/EAB S. Rubin AE00 J. Henderson IE/EGCB E. Jcrdan IE/DEPER-
! D. Muller hRR/ DBL R. Baer IE/DEPER E. Rossi NRR/PliR-A F. Schroeder -NRR/PWR-B'
- F. lliraglia NRR/PWR-B ~R. Berr.erc NRR/ DBL fl. Virgilio NPR/0 RAS G. Holahan NRR/0 RAS J. Beard NRR/0 RAS D. Ziemann DHFT S. Stern NRR/BWD-4 M. Wegner IE/EGCB I
D. Tarnotf NRR/0 RAS i 1 1 I I s l l 4 i i i l 't
Enclcsura 2 4 OPERATING REACTORS EVEllTS ERIEFING 86-13
- APRIL 21, 1986 -
PILGRIM FAILURE TO ISOLATE RCS FROM RHR A.I.T. FOLLOW-UP 4 RIVER BEND CA CCNCERNS INVOLVING ARCHITECT ENGINEER i i i i : J PEACH ECTT0fi LOSS OF 0FFSITE POWER SOURCE DUE TO A i UNITS 2 AND 3 TRANSFORMER FIRE AND EDG FAILURE TURKEY POINT NON-REDUNDANT CCW FOR HHS1 PUNPS UNITS 3 AMD 4 * ' 4 y 6 1 '______.___..__m__._._._____.U________
~ PILGRIM - FAILURE TO ISOLATE RCS FROM RHR A. I. T. FOLLOW-UP (M. WEGNER, IE) { PROBLEN: CONCURRENT FAILURE OF ALL THREE ISOLATION VALVES Oli "B" , R'IR/LPCI LINE IDE SWITCH C0fiTACTS f'OT PAKING UP PROPERLY. AILURE OF MSIVs TO RE-0 PEN SIGit ICAfiCE: ~
- POTENTIAL FOR INTER-SYSTEM LOCA OUTSIDE OF CONTAlfitiENT
! INADEQUATE CORRECTIVE ACTION FOR PRECURSOR EVENTS IN EACP I PROBLEf! AREA. i 1:FhECESSARY CHALLENGES TO S/FETY SYSTEFS (FCIS, RFS) BACKGROUND: CHECK VALVE IllSIDE OF CONTAINMENT LEAKING AND A MOTOR-CFERATED ] ISOLATION VALVE CUTSIDE OF CONTAll! MENT LEAKING. i OPERATIllG I!ITH THE SECOND ISOLATION VALVE OUTSIDE OF CONTAINMENT AS THE SINGLE ISOLATION VALVE IN THE E LOOP OF LPCI. Oh AFhlL 11, 1986, THAT VALVE BEGAN TO LEAK, NECESSITATING A SHUTDOWf.'.
} A GROUP I PCIS ACTUATION (MSIVs) AND A SCRAM OCCURRED AT EEC PSIG j WITH THE FOLE ShlTCH IN STARTUP.
DIFFICULTIES IN RE0PENING THE OUTBOARD MSIVs OCCURRED DURING RECOVERY ! FOLLOW-UP: AUGMENTED INSPECTION TEAM DISPATCHED TO SITE SullDAY APRIL ]?, .1986. l RHR VALVES WERE LEAK TESTED AND THE CllECK VALVE WAS LEAKING
! 75 STP-LITERS / MINUTE (SLM), E0TH NOVS WERE LEAKING ABOUT 1.5 SLf1
) EACH. 5 GPM 119 SLN] IS CONSIDERED TO BE A GROSS LEAKAGE FE0L'IRIfiG
! IMNEDIATE ACTION.
MODE SWITCH TESTS WERE PERFORMED (DETAILED PROCEDURE WITli STRIP CHARTS ON THE LOW STEAM LINE PRESSURE SIGl!AL) tilTHOUT FINDING PROPLEM. PLAF IS TO USE FAULT TREE ANALYSIS TO DETERhlhE hhERE TO LOOK NEXT, l MSIV LEAK RATE TESTS C0f! DUCTED (5.4 SLM IS MAX ACCEPTAELE). INBOARD MSIV SH0l'ED 3t' SLP; OUTBOARD, 9 SLM. j EXCESSIVE LEAKAGE OF IfiE0ARD f1SIV CONTRIBUTED TO INABILITY OF l MSIVs TO REOPEl!. I
- MSIVs TESTS WERE PERFORMED TO DETERMINE AT WHAT POINT THE POPPET .
WOULD LIFT. ON THE "A" f1SIV (WORST CASE), THE STEM WAS LIFTED ABOUT ]/2" BEF0FE THE POPPET WOULD ACTUATE. e.-
SIMPLIFIED RHR DIAGRAMS 450 psig n 1 f -r I : YO o 4 L - - - 1250 psig 100128B
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RIVER BEFD - PA CONCERNS INVOLVING ARCHITECT ENGINEER I (S. STERN, NRR) 1
- PROBLEM
- THREE INCIDENTS INVCLVING DEFICIENCIES Ifl STONE & WEESTER (SWEC) SCOPE. ,
5 SIGNIFICANCE: : 1 TAKEll AS A liHOLE - CONCEPNS OVER POTENTIAL DA PROELENS, OTHER ! PLANT SYSTEMS, POSSIBLY OTHER SWEC PLANTS,
- DISCRSLION
- :
3/13/86 - LICENSEE IDENTIFIES DISCPEPANCY ON STARTING VOLTAGES OF l MOTORS FOR MOVs 8. DAMPERS. l FSAR/SER STATES CAPABLE OF STARTING AT 70% VOLTAGE, 4 SWEC DESIGN BASED ON 70%.
! SWEC PROCURED MOTORS WITH 80% CAPAEILITY. -
l - PLANT DPAWINGS/FSAR NOT REVISED, j 4/4/86 - LICENSEE IDEUTIFIES 28 OUT OF 32 TRANSFORIiER TAPS SETTING ~ INCORRECT. CLASS IE CIRCUITS AND EUSES l UNC0VERED DURING SYSTEM VOLTAGE VERIFICATIP" ~ESTS j (CE0VIRED BY LICENSE) LICENSEE RE-SET TRANSFORMER TAPS. 3 4/14/86 - DURING REVIEW OF STARTUP TESTS, LICi DISCOVERED ERRORS IN FROCESS C0f1PUTER PROGRAM, TRANSVERSE INCORE PROEE (TIP) LOCATION INCORRECTLY SPECIFIED IN SOFTWARE (MIRROR IMAGE), COPE SYMMETRIC - NO IMPACT TO DATE.. , i - SWEC ATTEMPTED CHANGE IN TIP LOCATION (HARDWARE), PRIOR TO LICENSIt!G, SOFTWARE DEVELOPED FOR REVISED I.0 CATION: CHANGE l REJECTED BY NSSS; SWEC FAILED TO REVISE SOFTWARE,
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l RIVER BEND 1 FOLLOPL'P: l LICENSEE: TRANSFORMER TAPS, COMPUTER SOFTWARE PROELEMS. CORRECTED. STARTillG VOLTAGE DISCREPANCY FOUND ACCEPTABLE W/0 CHANGE. REQUEST ShEC VERIFICATI0fl. SkEC: VERIFIED ALL TECH SPEC-RELATED ELECTRICAL CALCULATI0fiS AND SETTINGS AGAINST AS-BUILT CONFIGUPATI0t'S, ALL VERIFIED EXCEPT A BATTERY PROFILE, FOUND TO BE CONSERVATIVE CURRENTLY VERIFYING ALL OTHER FSAR ELECTRICAL CALCULATI0llS.
~ -
PART 21 Ofi TRANSFORMER TAPS IN FREFAFATI0f-!. NINE MILE POINT 2 ( ALSO SWEC) f!0T IMPACTED. PM:
- RECOMMENDING OA 8 VENDOR INSPECTION BY IEE.
I
' PEACH POTTOM 2 AND 3: LOSS OF 0FFSITE POWER SOURCE DUE TO A TRANSFORf'ER
[ FIRE AND EDG FAILURE - APRIL 13, 1986 (ERIC WEISS, IE) ! i , PROBLEfi: ONE OF TWO 0FFSITE POWER SOURCES TO ECTH UNITS WAS LOST DUE TO
- A TRANSFORMER FIRE. SUESEGUENTLY ONE EDG WHICH HAD BEEP STARTED TG j j POWER Of.'E OF THE l' KV PL'SES FOR EACH UNIT BFCAl'E IMCPERAELE.
SAFETY SIGNIFICANCE: RELIABILITYOF0FFSITEAfiDOflSITEPOWERWAS
- AFFECTED.
i i CIRCL'MSTANCES : UNIT 2 AT 75%; UNIT 3 SHUTLOWN [ EXPLOSION AND FIRE OCCURRED IN //1 TRANSFORf',ER AT 11:07 A.M. DUE TO ) j APPARENT INTERNAL ELECTRICAL FAULT j ONSITE FIRE BRIGADE AND SIX OFFSITE FIRE COMPAFIES RESPONDED. l . , TRANSF0Pf/ER LOSS CAUSED LOSS OF #3 STARTUP OFFSITE POWER SOURCE l WHICH CAUSED FAST TRAPSFER CF IL KV BUSES TO UNIT 2 STARTl'P SCl'PCE, i EREAKER SUITCHING IN YARD TO SUPPORT FIRE FIGHTING WAS MADE DIFFICULT DUE TO FIRE DAMAGE TO COUTROL CAELES (EXPOSED CABLES i It' TP.ENCH) . t ! E-2 EDG WAS MANUALLY STARTED TO SUPPLY E-22 AND E-23.(INDEPENDEtiT i RPS POWER SUPPLY CONSIDERATIONS, FOR ENHANCED UNIT AVAILABILITY). j FIRE NAS OUT AT 1:02 P.M. AT 6:30 P.M. TPE E-2 EPC WAS l'AhlALLY TRIPPED DUE.T0 FLilCTUATING i ! INDICATIONS. , j E-22 AfdD E-23 WERE RE-ENERGIZED FR0f1 #2 STARTUP SOURCE, t ! UNIT 2 CONTINUED OPERATION; REDUCED TO 50% TO EhHANCE GRID STABILITY. ENTERED 7-DAY LCO FOR ILOPERAELE STARTUP SOURCE AfiD IN0 PEE /.FLF FDG. j #3 STARTUP SOURCE "AVAILAELE" AFTER 2 DAYS, 7 HOURS. j E-2 EPE OPEPAPLE AFTER 3 DAYS, 10 HOURS. FOLLOWUP: )
- SRI RESPONDED TO EVENT ONSITE. ,
2 FEGI0flAL HAHAGEMENT PLACED ON CONFERENCE CALL WITH SITE.. ; j TECH SPEC CONCERN RAISED (ALLOWED'OUT-OF-SERVICE TIME; i ! STS ALLOWS 12 HOURS). { i , i
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_ TURKEY POINT 3 AND 4 - NON-REDUNDAFT CCW FOR HHSI PUMPS APRIL 15, 1986 (D. MCDONALD, NRR) P PROBLEM: TECH SPECS AND FRGCEDURAL INADEGUACIES PEGAPDING ALIGNMENT OF SUPPORT SYSTEMS (E.C.. CCW) FOR HIGH-HEAD SAFETY INJECTICP (Fl!SI) i PUMPS. PIPIf!G REVERSAL Ih bhlT 4 CCW SYSTEfi T0 f!HFI Pl'MPS RESULTS IN FALSE FLOW INDICATION AND ALARf1 REVERSE FL0li THR0!!GH THE SEAL COOLERS AND THRUST BEAPIFGS AaB CCW INPUT HEADERS CROSS CONNECTED (LOST REDUNDANCY; VULI!ERAELE TO PASSIVE PIPE FAILURE) } SAFETY SIGNIFICANCE: i POTENTIAL FOR MAJOR DEGRADATI0f! 0F FHSI (INADEQUATE PUMP C00LINC)
. . SINCE ORIGINAL PLANT START-UP DISCUSSION:
PART 21 REPORT (APRIL 15, 1986) N0f' REDUl!DAllT UNIT 3 CCW RELIED ON WHEN UNIT 4 AT POWER AND UhlT 3 SHUTL0hN P8 ids AND PIPING IS0FETRIC CORRECT, CROSS CONMECTION DUE TO C0llSTRUCTION ERROR CCW TO HHSI PUPPS ALIGNED TO UNIT 3 UllTIL CORRECTED l 1 EOLLOW-UP: i MOST RESTRICTIVE TECHNICAL SPECIFICATION FOR UNIT 3 CR 4 , i CCU SYSTEM TO HHSI PUMPS BASED Of' OPERATING UlilT UPDATED PROCEDURES FOR ALIGilfiENT OF CCW TO PPSI PUPP CORRECT PIPING CROSS CONNECTIONS PRIOR TO Ut!IT 4 STARTUP f I I
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SUMMARY
- WEEK ENDING 04/20/86 . .
I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD- , CATIONS ' TOTAL i . .
~
- 04/16/86 NORTH ANNA 2 5A EQUIP / TURBINE NO 2 i 04/16/86 CALLAWAY 1 OA EQUIP / INVERTER NO 1 l 04/16/86 SALEM 2 50 A' EQUIP /FW CONTRL NO 1 i
i 04/17/86 NAINE YANKEE 1 57 A PERSrWNEL/FW OP NO 2 i 04/17/86 KEWAUNEE 1 OA PCHSONNEL/I+C NO 1 , 04/19/86 CALLAWAY 1 17 A PERSONNEL NO- 2 ' 04/19/86 CATAWBA 1 100 A PERSONNEL /I+C NO 2 04/20/86 HATCH 2 77 A EQUIP / TURBINE NO '2 j 04/20/86 KEWAUNEE 1 15 A EQUIP /FD RG VLV NO 2 ! 04/20/86 CATAWBA 1 OA PERSONNEL .NO 3 ' l4
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I ,. II. COMPARISON OF WEEKLY-STATISTICS WITH INDUSTRY AVERAGES i . SCRAMS FOR WEEK ENDING 04/20/86 SCRAM CAUSE POWER NUMBER NUMBER 1985 ; OF NORMALIZED (6) WEEKLY SCRAMS (5) TO 1985 AVERAGE (3)(4)
- ** POWER >15%
l EQUIP. RELATED >15% 3 3.0 5.4 (68%) PERS. RELATED(7) >15% 3 3.0 2.0 (25%) OTHER(8) >15% 0 0.0 0.6 ( 7%)
** Subtotal **
i 6 6.0 0.0 j ** POWER <15% 3 . . EQUIP. RELATED <15% 2 2.0 1.3 (54%) ] PERS. RELATED <15% 2 2.0 0. 9 (38%)
- OTHER <15% 0 0.0 0.2 ( 8%) -
** Subtotal ** l 4 4.0 2.4.
i *** Total *** j 10 10.0 10.4 l , I ~ MANUAL VS AUTO SCRAMS l j TYPE NUMBER NUMBER 19Q5 OF- NORMALIZED WEEKLY SCRAMS TO 1985 AVERAGE
- i i
1
; MANUAL SCRAMS O O.0 1.0 t
AUTOMATIC SCRAMS 10 10.0 9.4 i } i i 1 . i 4 e i
lo - NOTES ,
- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS '
- FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUN THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE t
ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED ; TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. i
) 2. REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM ,
i l 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 a DIVIDING BY 52 WEEKS / YEAR
- 4. IN 1985, THERE WERE AN ESTIMATED TOTAL 0F 541 AUTOMATIC 2 1
MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR & AN AVERAGE RATE OF 10.4 TRIPS PER WEEK ! FOR ALL REACTORS. I
! - 5. BASED ON 93 REACTORS HOLDING A FULL POWER LICENSE, AS OF 2/1/86
- 6. NORMALIZED VALUES ALLOW COMPARISON TO 1985 DATA BY MULTIPLYING ACTUAL 1986 VALUE BY: 93 REACTORS IN 1985
; NUMBER OF REACTORS REPORTING .
- 7. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL j DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVZL CONTROL PROBLEMS
- 8. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBU'ED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKN'WN CAUSE.
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,Page No. !
04/23/06 OPERATINS REACTORS EVENTS MEETIN6 FOLLOWUP ITEMS AS OF MEETING 86-13 DN APRIL 21 , 1966 (IN ASCENDING MEETING CATE, NSSS VENDOR, FACILITY ORDER) MEETING FACILITV RESPONS!!LE TASK DESCRIPT!DN SCHEDULE CLOSEDDATE COMMENTS NUMBER / NSSS VENDOR / DIVISION / COMPLET. BY DOCIAENT, MEETING EVENT DESCRIP. INDIVIDUAL DAIE(S) MEET!NS,ETC. DATE 85-13 TURKEY POINT 3 PSB /MILH0AN J . REVIEW ADEQUACY OF GOVERNOR 04/22/86 CLOSED 04/21/86 08/13/85 W / POST-TRIP / DES!6N ON TURBINE DRIVEN AFV 01/0:i/E6 APRIL 15, 1986 LOSS OF AFW PUMPS 10/13/S5 MEMO E. ROSSI TO 6. HOLAHAN ,
't .
66-03 MCGUIRE DHFS/ZIEMANN D REVIEW NOVEMBER 1, 1985 Mc6UIRE 04/30/86 0 FEN / / 01/27/86 W / START-UP / EVENT AND DETERMINE IF FAILURE // < WITH DEGRALED TO REPA!R VALVE MOTOR OPERATOR !/
- HPSI SYSTEM FRIOR TO START-UP WAS IN VIOLATION CF TECH SFECS
, REQUIREMENT 86-06 W FLANTS IE IJCRDAN E REVIEW REPORTABILITY OF liEMS 04/20/86 CLOSED 44/21/86 03/03/96 W / S!h6LE / SUCH AS S!hGLE FAILURE CF P-10 03/31/86 APRIL 18,1966 FAILURE 0F INTERLOCK // MEMO D.ALLISON ! NUCLEAR TO 6. HDLAHAN i INSTRUMENTA110N INTERLOCK P-10 B6-10 DYSTER CREEK NRR /MIRABLIA F CHECK ON TM! FOR USE OF SIMILAR 05/01/86 OPEN / / ! 03/31/96 GE / LEVEL / SWITCHES //
SWITCH SETFOINT // DRIFT , 86-10 OYSTER CREEK NRR /HOUSICN W RESOLVE THE QUESTION OF THE 06/30/86 OPEN / / REVIEWBEING 03/31/86 6E / LEVEL / ACCEPTABILITY OF PLIND SWITCHES // ACCOMPLISHED UNDER SW!iCH SETPOINT AND DELEi!0N OF DAILY CilANNEL // TAC NC 61203 DRIFT CHECK 86-10 BRAIDW:00 1 NRR /N00 NAN V REQUEST REPORT OF EVENT FROM 05/01/86 0?EN / / 03/31/86 W / WATER / LICENSEE // HAMMERliMAIN //
, STEAMLINE 8610 SRA!CWND1 IE /JORCAN E EVALUATE NEED FOR !E NOTICE 05/01/86 OPEN / /
03/31/86 W / WATER / // HAMMER IN MAIN // SIEAMLINE s 86-10 HADCAM NECK NRR /SPE!S T ASSESS THE POTENilAL FOR 05/30/86 OPEN / / 03/31/86 W / NEW SMALL / 6ENERICAPFLICABILITY // BREAKLOCA // RESULTS 86-10 HADDAM WECK NRR / GRIMES C ASSURE THAT THE CORRECilVC 05/01/86 OPEN / / 03/31/86 W / NEW SMALL / ACTIONS ARE ADEQUATE PRIOR 10 // 3REAKLOCA RESTART // RESULTS
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,04/33/96 0FERAtlN6 REACTORS EVENTS MEETING FOLLONUP ITEMS AS OF MEETING 66-13 DN APRIL 21 , 1986 (IN ASCENDING MEETIN6 DATE, NSSS VENDOR, FACILITY ORDER)
MEETIN6 FACILITY RESPONSIBLE TASK DESCRIPi!GN SCHEDULE CLOSED DATE CDPRENTS NUMlER/ NSSS VENDOR / DIVISION / COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC. DATE 86-10 HADDAM NECK NRR /ROSSI E DETERMINE IF OTHER WESTINGHOUSE 05/01/86 CLOSED 04/21/86 03/31/86 W / NEN SMALL / FWRS HAD SAME PROBLEM / / APRIL 22, 1996 BREAKLOCA / / MEMO E. ROSSI RESULTS TO 6. HOLAHAN
~
1t 86-13 PEACH B0fiCM IE / JORDAN E EVALUATE NEED FOR IE NOTICE 05/30/96 OPEN // . 04/21/06 GE / LDSS OF / / / 0FFSliEPONER // < SOURCE DUE TO A TRANSFORMERFIRE AND EDS FAILURE 86-13 RIVERBEND IE / JORDAN E CETERMINE NEED FOR VENDOR 05/30/96 OPEN // 04/21/86 W /GACCNCERNS / INSFECTION / /
- INVOLVING //
ARCHITECT ENGINEER me**" _ _ _ _ _ ___________._____-____._m_ . - _ _ _ _ _ _ - . _ . _ _ _ - . . . - _ __}}