ML20141N397
| ML20141N397 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Three Mile Island, McGuire, 05000000 |
| Issue date: | 02/24/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8603060325 | |
| Download: ML20141N397 (29) | |
Text
r FEB 2 41986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON JANUARY 27, 1986 - MEETING 86-03 On January 27, 1986, an Operating Reactor Events meeting (86-03) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on January 13, 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 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 assignments are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x27864) if the target completion date cannot be met.
Original Signed By:
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ enc 1:
See next page DISTRIBUTION Central Files _
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MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON JANUARY 27, 1986 - MEETING 86-03 On January 27, 1986, an Operating Reactor Events meeting (86-03) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on January 13, 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 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, x27864) if the target completion date cannot be met.
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ encl:
See next page DISTRIBUTION Central Files NRC PDR ORAB Rdg ORAB Members 010@ :t D/0 RAS DMrnoff:dm :tW Bs' man GHolahan 1 /)P/86 ,
/86 / /86
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[ g NUCLEAR REGULATORY COMMISSION i 3 E WASHINGTON. D. C. 20555
..... FEB 2 4 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation
' FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUPNARY OF THE OPERATING REACTORS EVENTS MEETING ON JANUARY 27, 1986 - MEETING 86-03 On January 27, 1986, an Operating Reactor Events meeting (86-03) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on January 13, 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 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 assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, x27864) if the target-completion date cannot be met.
h' Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As stated cc w/ encl:
See next page I
Harold R. Denton cc: D. Eisenhut D. Hood J. Taylor J. Glitter C. Heltemes G. Vissing T. Murley, Reg. I W. Paulson J. Nelson Grace, Reg. II J. Thema J. Keppler, Reg. III L. Kelly R. D. Martin, Reg. IV B. J. Youngblood J. B. Martin, Reg. V J. Stolz R. Starostecki, Reg. I R. Walker, Reg. II C. Morelius, 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 J. Knight D. Crutchfield G. Lainas ~
V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan K. Seyfrit
..)
m a -
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-03)
JANUARY 27, 1986 NAME DIVISION NAME DIVISION
, D. Eisenhut NRR J. Stolz NRR/PWR-B G. Holahan ORAS D. Humenansky OCM/Zech j l- D. Crutchfield NRR/PWR-B C. Ader OCM
- R. Singh NRR/IE F. Schroeder NRR/PWR-B
, J. Thoma NRR/PBR-6 B. Sheron NRR/DSR0 L. Kelly NRR/0 RAS R. Frahm NRR/DSRO
- W. Swenson NRR/ORAS D. Ziemann NRR/DFHT M. Caruso NRR/0 RAS J. Glitter IE/DEPER W. Regan NRR/F0B D. Tarnoff NRR/0 RAS
- V. Benaraya NRR/F0B-A i j W. Haass IE/VPB j J. Callan IE/ORPB l F. Cherny NRR/DSR0/EIB K. Eccleston NRR/TOSB A. Dromerick IE/EGCB M. Chiramal AE0D/ROAB D. Zukor AE0D/ROAB K. Seyfrit AEOD/ROAB E. Weiss IE/DEPER R. Weller NRR/PWR-B W. Paulson NRR/PWR-B R. Wright NRR/PWR-B ,
D. Hood NRR/PWR-A/ PAD 4 -
E. Jordan IE l R. Baer IE/DEPER/EGCB F. Miraglia NRR/PWR-B j S. Varga NRR/PWR-A l
t . . _ _ . _ . _ . - - . . . . _ , . _ . - - , _ . - ._ ____ -
ENCLOSURE 2 o
b
- OPERATING REACTORS EVENTS BRIEFING 86-03 JANUARY 27, 1986 l
I i
McGUIRE UNIT 1 START-UP WITH DEGRADED HPSI SYSTEM l
i ARKANSAS NUCLEAR ONE UNIT 1 DESIGN DEFICIENCY IN EMERGENCY FEEDWATER-l SYSTEM -
TMI UNIT 1 REACTOR TRIP BREAKER FAILURE TMI UNIT 1 PARTIAL LOSS OF NNI I
J i
McGUIRE UNIT 1 - START-UP WITH DEGRADED HPSI SYSTEM NOVEMBER 3, 1986 (J. GIITTER, IE)
PROBLEM: FAILURE TO REPAIR VCT ISOLATION VALVE MOTOR OPERATORS PRIOR TO START-UP WOULD HAVE PREVENTED VCT ISOLATION ON SI SIGNAL.
i SAFETY SIGNIFICANCE: HPSI MAY NOT HAVE FUNCTIONED AS REQUIRED ON A REAL DEMAND.
DISCUSSION: -
AT 0640 ON NOVEMBER 2, A LOSS OF INST. AIR (SHARED BY BOTH UNITS)
CAUSED BOTH UNITS TO TRIP AND SAFETY INJECTION IN UNIT-1.
VCT ISOL. VALVES CLOSED AS REQUIREDs HOWEVER, THE VALVE MOTOR 1
OPERATORS WERE LATER FOUND BURNED OUT BECAUSE VALVE WAS REPEATEDLY HAMMERED CLOSED BY THE VALVE OPERATOR.
PRIOR TO START-UP, OPERATORS MANUALLY OPENED VALVES, BUT DID 3 NOT REPAIR THE.M0 TOR OPERATORS.
UNIT START-UP COMMENCED AT ABOUT 0600 ON 11/3. THE UNIT WAS IN MODE 2 FOR ABOUT-6 HOURS.
TWO MAJOR CONCERNS 1) IS BORON CONC. LESS TilAN THAT ASSUMED IN SAFETY ANALYSIS? AND 2) COULD VCT COVER (H 2 AND N ) BECOME 2
ENTRAINED IN THE CHARGING PUMP SUCTION PATH RESULTING IN GAS BINDING OF PUMPS?
NRC (OP CENTER) WAS NOTIFIED AT 1218 ON 1/14/86.
i FOLLOW-UP:
VALVE OPERATOR REPAIRED.
COMPLIANCE WITH TECH SPECS REQUIREMENTS IS UNDER REVIEW, PERFORMED TEST.T0 DETERMINE TIME REQUIRED FOR OPERATOR TO CLOSE ISOLATION VALVES. TIME REQUIRED WAS 19.4 MINUTES. AT 20 MINUTES VCT LEVEL WAS AT 20%. ,
1 1
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7, 1
ARKANSAS NUCLEAR ONF-UNIT 1 - DESIGN DEFICIENCY IN FMERGENCY FEEDWATER SYSTEM (EFW)
JANUARY 14, 1986 - (W. PAULSON a G, VISSING, NRR)
PROBLEM:
DESIGN DEFICIENCY IN THE EMERGENCY FEEDWATER SYSTEM (EFW)
SIGNIFICANCE:
P0TENTIAL FOR LOSS OF ALL EFW AND BLOWDOWN OF BOTH STEAM GENERATORS, DURING STEAM LINE BREAK WITH SINGLE FAILURE OF ONE A/C BUS CIRCUMSTANCES:
DEFICIENCY DISCOVERED BY IE INSPECTION TEAM DURING POSTULATED STEAM LINE BREAK CONCURRENT WITH LOSS OF RED A/C POWERBUS,Tl)RBINEDRIVENANDMOTORDRIVENEFWPUMPSW0llLDBELOST POSSIBLE BLOWDOWN OF BOTH S/Gs DESIGN DOES NOT MEET THE SINGLE FAILURE CRITERION PLANT, AT 89% POWER AT THE TIME OF THE DISCOVERY, WENT INTO CONTROLLED SHUTDOWN DUE TO FAILURE OF EDG FOLLOWUP:
LICENSEE CONFIRMED EXISTENCE OF DESIGN DEFICIENCY LICENSEE TO INSTALL CHECK VALVES IN STEAM LINES FROM EACH OTSG BEFORE STARTUP, NRR (PEICSB) REVIEWED ISSUE AND CONCURRED WITH INSPECTION TEAM'S FINDINGS 1
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TMI UNIT 1 - REACTOR TRIP BREAKER FAILURE JANUARY 14, 1986 (J. THOMA, NRR)
PROBLEM: DNE REACTOR TRIP BREAKER (RTB) FAILED TO OPEN DURING SHUNT TRIP TEST SIGNIFICANCE: POTENTIAL FAILURE OF REACTOR PROTECTION SYSTEM CIRCUMSTANCES:
HISTORY SEPT 23, 1985 - MECHANICAL FAILURE OF RTB CB-1) -
SHUNT. RELAY BURNED OUT RTB CB-11 REPAIRED RTB CB-11 INSTALLED - TESTED WEFKLY JANUARY 14, .1986 RTB CB SHUNT TEST FAILS 0THER RTB SHUNT TRIP RELAYS TESTED SATISFACTORILY SHUNT TRIP CIRCUIT BOARD REPLACED FINDINGS RELAY ON SHUNT TRIP CIRCUIT BOARD IMPROPERLY INSTALLED IMPROPER INSTALLATION CAUSED EARLY BURNOUT OF RELAY FOLLOWUP _1 LER TO BE ISSUED f
TMI UNIT 1 - PARTIAL LOSS OF NNI JANilARY 24, 1986 (J. THOMA, NRR)
PROBLFM: PARTIAL LOSS OF NNI SIGNIFICANCE: POTENTIAL FOR FLANT TRANSIENTS CIRCllMSTANCES:
CONDUCTING MAINTENANCE ON FEEDWATER FLOW TRANSMITTER ABOUT 11:24 A.M. - RE-ENERGIZED FEEDWATER FLOW TRANSMITTER ICS SUBFEED BREAKER TRIPPED ALARMS / INDICATIONS IN CONTROL ROOM ALERTED GPERATORS MANUAL CONTROL ESTABLISHED FOR AFFECTED SYSTEMS REACTOR POWER CHANGE WAS LESS THAN 2%
ABOUT 12:37 P.M. - RESTORED POWER TO ICS '
LAST PARTIAL LOSS OF NNI AT TMI OCCURRED AUGUST 21,1985 FOLLOWUP:
LICENSEE TROUBLE SHOOTING FEEDWATER FLOW TRANSMITTER MODULE, BUT NO CAUSE OF PROBLEM FOUND MODULE RE-INSTALLED, WORKING SATISFACTORILY REGION I FOLLOWING UP ON LICENSEE'S INVESTIGATION I
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13a Enclosure i
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YEAR NO. OF PLANTS AUTO. MANUAL TOTAL t
1983 77 5.6 .9 6.5 l 1984 83 5.7 .7 5.9 1
1985 92.* 5.3 .6 5.9 i
AVERAGE PER PLANT ANNUAL FREQUENCY ESSENTIALLY SAME AS 1984; EVALUATION OF CAUSES UNDERWAY.
DETAILED ANALYSIS OF TRENDS AND PATTERNS IN TRIP FREQUENCY IN j PROGRESS f
' PLANTS WITH FULL POWER LICENSE WHICH OPERATED DURING 1985 he I
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REACTOR SCRAM
SUMMARY
WEEK ENDING 01/19/86 I. PLANT SPECIFIC DATA t
DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD CATIONS TOTAL 01/13/86 INDIAN POINT 2 100 A EQUIP /MFWP TRP NO 1 01/15/86 RIVER BEND 1 17 A EQUIP /FD RG VLV NO 2 01/15/86 ROBINSON 2 100 A PERSONNEL / TEST NO 1 01/15/86 MCGUIRE 2 100 A EQUIP /MFWP TRP NO 1 01/15/86 SUSQUEHANNA 2 70 M EQUIP /TRNSF LK NO 1 01/16/86 BYRON 1 98 M PERSONNEL / TEST NO 1 01/16/86 SALEM i 100 A EQUIP /ELEC YES 1 01/16/86 PILGRIM 1 100 A PERSONNEL /MAINT NO 2 01/17/06 FARLEY 2 75 A EQUIP /MFWP TRP NO 1 01/19/86 NORTH ANNA 1 5A PERSONNEL / TEST NO 1 01/19/86 HATCH 2 2A EQUIP / MODE SW YES 1 01/19/86 SURRY 1 60 M PERSONNEL / TEST NO 1 01/19/06 CATAWBA 1 91 A EQUIP /HTR DRAIN NO 1
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS SALEM '
1 LOST ONE AFW PMP HATCH 2 RCIC FAILURE
- * ----- --~
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 01/19/86
, i s
SCRAM CAUSE POWER NUMBER NUMBER 1984 OF NORMALIZED (6) WEEKLY SCRAMS (5) TO 1984 AVERAGE-(3)(4)
- POWER >15%
EQUIP. RELATED >15% 7 6.3 3.9 (60%)
i PERS. RELATED(7) >15% 4 3.6 1.8 (28%)
OTHER(8) >15% 0 0.0 0.8 (12%)
- Subtotal **
11 9.9 6.5
- POWER <15%
EQUIP. RELATED <15% 1 0.9 1.4 (46%)
PERS. RELATED <15% .), 0.9 1.4 (46%)
OTHER <15% 0 0.0 0.2 (8%)
- Subtotal **
2 1.8 3.0
- Total ***
_ 13 11.7 9.5 s
MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER 1984
' OF NORMALIZED WEEKLY i
SCRAMS TO 1984 AVERAGE MANUAL SCRAMS (9) 3 2.7 1.1
- AUTOMATIC SCRAMS (9) 10- 9.0 B.4 4
i 1
f
_____ _~:_~ _~__~ ~_T- _ ~_~ ~ ~_~ ~ r - ~2 * :- - -- - _ - - - - - - - - - - - - - - - -
l I
' REACTOR SCRAM
SUMMARY
l WEEK ENDING 01/26/06 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- Y TD GATIONS TOTAL 01/21/86 SUSOUEHANNA 2' 1 A EQUIP /STM BYP NO 2 01/21/86 ROBINSON 2 72 A PERSONNEL NO 2 01/21/86 DRESDEN 2 44 A PERSONNEL /S TST NO 1 01/22/86 GRAND GULF 1 60 A EQUIP / LOAD REJ NO 1 01/22/86 ROBINSON 2 33 A PERSONNEL /S TST NO 3 01/22/86 WATERFORD 3 100 A EQUIP /DRP ROD NO 1 01/23/86 CALVERT CLIFFS 1 100 A PERSONNEL /S TST NO 1 -
01/23/86 MCGUIRE 2 10 A EQUIP /IRN SPK NO 2 01/24/86 PEACH BOTTOM 2 95 A EQUIP /MSIVS NO 2 01/24/86 SURRY 1 42 M EQUIP /ELEC GEN NO 2 m
9 O
O O
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 01/26/86 SCRAM CAUSE POWER NUMBER NUMBER 1984 OF NORMALIZED (6) g WEEKLY SCRAMS (5) TO 1984 AVERAGE (3) (4)
- POWER >15%
EQUIP. RELATED >15% 4 3.6 3.9 (60%)
PERS. RELATED(7) >15%
4 3.6 1.8 (28%)
OTHER(8) >15% 0 0.0 0.8 (12%)
- Subtotal ** .
8 7.2 6.5
- POWER <15%
EQUIP. RELATED <15% 2 1.8 1.4 (46%)
PERS. RELATED <15% O O.0 1.4 (46%)
OTHER <15% 0 0.0 0.2 (8%)
- Subtotal **
2 1.8 3.0
- Total ***
10 9.0 9.5 MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER 1984 OF NORMALIZED WEEKLY SCRAMS TO 1984 AVERAGE MANUAL SCRAMS (9) 1 0.9 1.1 AUTOMATIC SCRAMS (9) 9 8.1 8.4 l
-___~_~_~T~~~~~_~_~~~~T~~_~~~~~~~~~--*
. . . l" 1
l NOTES (1) PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD TS MIDNIGHT SUN. THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED A5 REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS
] PART OF PLiNNED SHUTDOWN IN ACCORDANCE WITH.A PLANT PROCEDURE.
j (?) RECOVERY COMPLICATED BY E0VIPMENT FAILURES OR PERSONNEL ERRORS [
j llNRELATED 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 ,
j 2.0-2, 2.1-4, AND 2.2-1) WEEKLY DATA DETERMINED BY'TAKING TOTAL I l -TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR. j l
l ,(4) IE 1984, THERE WERE A TOTAL OF 492 AUTOMATIC AND MAPUAL REACTOR l $ TRIPS AT 83 REACTORC (HOLDING FULL POWER LICENSES).- THIS YIELDS l AN. AVERAGE RATE OF 5.9 TRIPS PER REACTOR PER YFAR AND AN AVERAGE j RATE OF 9.5 TRIPS PER WEEK FOR ALL REACTORS, i
l (5) BASED OF 9? REACTORS HOLDING A FULL POWER LICENSE, AS OF 11/30/85.
I t
(6) FORMALIZED VALUES ALLOW COMPARISON TO 1984 DATA BY Fl!LTIFLYING ;
ACTUAL 1985 VAI.IIE BY: (83 PEACTORS IN 19Ph)= 0.90 i
(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. i l (8) "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO SOME COMDINATION 0F HARDWARE FAILURE AND HUMAN ERROR, ENVIRONMENTAL CAUSES l (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAllSE.
, (9) MANUAL SCRAMS ONLY AFD AUTOMATIC SCRAMS ONLY ARE DERTVEn FR M TOTAL AUTOMATIC AND MANUAL SCRAMS DATA PROVIDED IN TABLE 2.0-?
0F AEOD PEPORT.
OPERA?!NSREACTORSEVENTSMEE71NGFOLLOWUPITEMS ASOFMEE?lN326-03ONJANUARY 27.1986 enclosure 3 (IN ASCENDING MEET!n3 CATE, NSSS VEN:0R, FACILITY ORDER)
MEETING FACILITY RESPCNS!!LE TASK CESCRIFT10N SCHECULE CLOSEDCATE CM."ENTS NUniER/ NS55VEN3CR/ DIVIS!CN/ COMPLET. BYCOCU"ENT, MEETINS EVENTCESCRIF. IND!V! DUAL DATE(S) MEETING,ETE.
DATE 85-13 TURy!Y PCINT 3 PSB /6A" MILL. W. REVIEW ADEQ"ACY OF 60VERNCR 02/29/96 05EN //
, 08/13/25 W / POST-TRIP / DESIGN CN TURBINE tRIVEN AFW 01/05/86 LOSS OF AFW fCMFS 10/13/B5 85-21 TROJAN PSB /SHAPAKER REEIAMINE NEED FOR THIS 01/31/96 0FE4 // PE*0RANDUM IN 10/28/85 / INCORRECT / INSTALLAi!0N AND GENERIC // CONCURRE%CE SETPOINTS FOR APPLICABILITY //
TRIP OF AFW j PUMPS ON L0u SUCTION PPESSURE f
85-23 BRCWNS FERRY IE /F KANTOR D!$ CUSS WITH FEMA NRC POSITION 01/30/06 CLOSED 01/27/26 70 BE O!SCUSSE!
i
!!/18/85 / OFFS!TE / WITH RESARD TO EMEF6ENCY PLAN 12/18/85 DISCUSSED DURING NEIT
.. CONTAMIN. EXERCISE // DURINGNRC/ FEMA FEPA/hRC STEERINS INCIDENT DURINS .
MEETINGON COMMITTEE MONTHLV EMER6ENCYPLAN 01/21/96 MEETINS EIERCISE B5-29 PALO VERIE 1 NRR /CRUTCHFIELD ASSESSMENT OF STARTUP AND OP. 01/30/96 CLCSED 01/27/96 12/23/25 CE / ESFAS / EIFER!ENCEFORPALOVERDEUNITS // 01/01/84 UPDATE ACTUAi!0N,REACTO 162. / / OF PALO VERDE 1 R TRIP, AND OPERATING COMPONENT EIPER!ENCE MALFUNCTICNS l 86-03 ARKANSASI NRR /MIRASLIA F REVIEW IASIS FOR FACILITY 03/31/86 OPEN //
01/27/86 BW / DESIGN / ORIGINAL DESIGN MODIFICATICN //
KFICIENCY IN AND BASIS FOR FURTHER // .-
l EMER6ENCY MODIFICAT!DN PROPOSED BY j FEET #ATERSYSTEM LICENSEE.
B4-03 ARIAhSAS1 IE /JCRDAN E IDENT!FY UNAT IS ACTUAL E S!6N 03/31/96 0 FEN //
i 01/27/84 BW / K S!6N / IN B6u PLANTS //
KFICIEMCYIN //
4 EMERGENCY FEElHIATER SYSTEM 16-03 ARKANSAS 1 NRR /RIRA6LIA F DETERMINE SENERIC APPLICABILITY 03/31/96 DPEN //
01/27/06 BW / KS!$N / OF ARKANSAS 1 DESIGN KFICIENCY //
KFICIENCYIN / /
EMEP6ENCY i FEEDWATERSYSTEM 94-03 TM! ! !E /JCROAN E CONS!DERSUPPLEMENTALIEN0ilCE 03/31/86 OPEN //
01/27/16 lu / PARI!AL / ON RECENT TRIP BREAKER PROBLEMS //
LOSS OF M ! / /
- er *
- O -
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C'ERATIN5 K:A: TOP.5 EVENT! MEET!h6 FOLLOWJF ITETS AS CF PEETING E6-03 CN JANJ4RY 27 ,1984 I!N ASCE%D!kB MEEi!%S DATE, RSSS V!n:CR, FACILiiY C' DER)
MEETING FA !LITY RE580%S! ELE TASP IESCRIPTION NUf!ER/ N!!! VEN:0R/ DIVI 5!C%-
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