ML20133E463
| ML20133E463 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Davis Besse, Peach Bottom, Palisades, Palo Verde, Fermi, North Anna, Haddam Neck, San Onofre, 05000000 |
| Issue date: | 10/01/1985 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8510090397 | |
| Download: ML20133E463 (27) | |
Text
.
OCT 1 1985 -
MEMORANDUM FOR:
Hugh L. Thompson, Jr., Director Division of Licensing FROM:
Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 23, 1985 - MEETING 85-17 On September 23, 1985, an Operating Reactor Events meeting (85-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 16, 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.
Ori;ic: Racj bj:
i Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
Enclosures:
DISTRIBUTION As Stated Central Files NRC POR ORAB Rdg cc w/ enc 1:
ORAB Members See next page ORAB)_;T L
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OCT l 2'
MEMORANDUM FOR:
Hugh L. Thompson, Jr., Director Divisio.1 of Licensing FROM:
Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 23, 1985 - MEETING 85-17 On September 23, 1985, an Operating Reactor Events meeting (85-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 16, 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 ttle due date.
Please be responsive and advise OPAB (D. Tarnoff, x29526) if the target completion date cannot be : ret.
O!L : '. L uj:
Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
Enclosures:
DISTRIBUTION As Stated Central Files NRC PDR ORAB Rdg cc w/ encl:
ORAB Members See next page T
TN L
SL: DRAB:DL C:0RAB:DL A
DT off:cl RWessman GHolahan DC tch 1 eld
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l FEPORANDUM FOR:
Hugh L. Thompson, Jr., Director Division of Licensing FPOM:
Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 23, 1985 - MEETING 85-17 e
On September 23, 1985, an Operating Reactor Events meeting (85-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 16, 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 presious assignments are presented in Enclosure 3.
I 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.
i
~
Dennis M. Crutchfield, sistant Director for Safety Assessment, DL
Enclosures:
As stated cc w/ encl:
See next page
_.--_-_,-...--_ _._. _,.._...__~,.-_,-_.-...~._ _,, -, ~ _,_, _ _- _,- - -.-,__,_.....--_._,-.-._
Hugh L. Thompson, Jr. cc:
H. Denton E. Rossi, IE R. Bernero R. Hernan J. Knight F. Schroeder T. Speis G. Knighton C. Heltemes D. Silver T. Novak J. Lyons W. Russell D. Brinkman J. Taylor E. Weiss E. Jordan R. Baer F. Rowsome B. J. Youngblood W. Minners F. Akstulewicz L. Shao M. Licitra T. Ippolito D. Lynch S. Varga T. Rotella J. Zwolinski J. T. Beard E. Sullivan J. Stolz D. Beckham G. Gears G. Edison D. Persinko K. Seyfrit A. DeAgazio T. Murley, R-I W. Paulson
.J. Nelson Grace, R-II R. Gilbert J. Keppler, R-III H. Bailey, IE R. D. Martin, R-IV J. B. Martin, R-V R. Starostecki, R-I R. Walker, P-II C. Norelius, R-III R. Denise, R-IV D. Kirsch, R-V G. Lainas P. Baranowski 9
-,-,-,.--,ni, w,.e.
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L ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-17)
SEPTEMBER 23, 1985 Name Division Name Division H. Denton NRR D. Persinko NRR/DFHS/LQB 4
W. Swenson NRR/DL/0RAB F. Manning RES/DRA0 i
L. P. Crocker DHFS/LQB M. Caruso NRR/DL/0RAB J. B. Henderson IE/DEPER E. Weiss IE/DEPER/EAB i
D. Crutchfield NRR/DL S. Rubin AE00 E. Licitra NRR/DL/LBe3 K. Seyfrit AEOD J. C. Stone IE/0AVT/VPB D. Lynch NRR/DL/LB#1 J. J. Zudans IE/EAB R. Freeman AE00/R0AB C. Miller NRR/DL J. T. Beard NRR/DL/0PAB G. Dick NRR/DL R. H. Wessman NRR/DL/0RAB D. B. Vassallo NRR/DL G. Holahan NRR/DL/0RAB M. Haughey NRR/DL J. Zwolinski NRR/DL/0RBd5 j
J. Lyons NRR F. J. Miraglia NRR/DL T. M. Novak NRR/DL W. Minners NRR/ DST S. Black NRR/DL J. P. Knight NRR/ DST G. Gears NRR/DL R. W. Houston NRR/DSI J. Youngblood NRR/DL G. Lainas NPR/DL G. Knighton NRR/DL/LBd3 R. Baer IE/DEPER/EGCB D. Houston ACRS E. Rossi IE/DEPER/ CAB B. W. Sheron NRR/DSI/RSB E. Jordan IE/DEPER G. Cwalina NRR/DHFS/ LOB H. Thompson NRR/DL l
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-s OPERATING REACTOR EVENTS BRIEFING (85-17)
SEPTEMBER 23, 1985 SAN ON0FRE UNIT 1 FAILURE OF AUXILIARY FEEDWA.TER PUMP TURBINE BEARINGS PALO VERDE UNIT 1 REACTOR TRIP, SAFETY INJECTION, LOSS OF PRESSURIZER AUXILIARY SPRAY SYSTEM DRESDEN UNIT 3 SCRAM SOLEN 0ID PROBLEM INDUCED l
RCS LEAKAGE PEACH BOTTOM UNIT 3 CRACK INDICATIONS ON 316-L SAFE-ENDS FERMI UNIT 2 GPERATING EXPERIENCE DAVIS-BESSE MAINTENANCE SURVEY OTHER EVENTS OP INTEREST NORTH ANNA UNIT 1 EDG ENGINE FAILURE HADDAM NECK CONTROL R0D MISALIGNMENT ANLAYSIS NOT PERFORMED PALISADES MISCALIBRATED PRESSURIZER PRESSURE CHANNELS
SAN ONOFRE 1 - FAILURE OF AUXILIARY FEEDWATER PUMP TURBINE BEARINGS SEPTEMBER 19, 1985 (HENRY BAILEY, IE)
PROBLEM - FAILURE OF AFWP TURBINE JOURNAL BEARINGS ON LOW OIL LEVEL IN SUMP, SAFETY SIGNIFICANCE - PARTIAL LOSS OF DECAY HEAT REMOVAL CAPABILITY, FAILURE WAS CAUSED BY FAULTY MAINTENANCE ON THE
- AFWP, THIS FAILURE AND OTHER FAILURES DURINC THIS EVENT INDICATE A WEAK MAINTENANCE PROGRAM, DISCUSSION EVENT INITIATED FROM 92% POWER WHEN ADDING NITROGEN TO B AUXILIARY TRANSFORMER.
B AUX TRANSFORMER TRIPPED ON SUDDEN PRESSURE INCREASE AND OPENED MAIN GENERATOR OUTPUT BREAKER.
MAIN TURBINE AND REACTOR TRIPPED, AUX FEEDWATER WAS INITIATED ON LOW S/G LEVEL, POWER OPERATED RELIEF VALVES BETWEEN HIGH AND LOW PRESSURE TURBINE DID NOT OPEN TO RELIEVE STEAM PRESSURE TO LOW PRESSURE TURBINE (USED IN PLACE OF INTERCEPT VALVES),
MAIN TURBINE OVERSPED (126%),
STEAM DRIVEN AFWP STARTED AND TRIPPED ON OVERSPEED SIGNAL, AN ELECTRIC AFWP OPERATED SATISFACTORILY, FOLLOWUP POST TRIP EXAMINATION SHOWED OVERSPEED TRIP OF AFWP WAS CAUSED BY VIBRATION OF OVERSPEED TRIP DEVICE AS A RESULT OF TURBINE BEARING DAMAGE THAT WAS CAUSED BY LOW OIL IN SUMP, FAILURE OF BEARING WITH LOW OIL IN SUMP CAUSED THE FAILURE OF THE BEARING ON OPPOSITE SIDE OF TURBINE, LOW OIL IN SUMP CAUSED BY FAULTY SIGHTGLASS INDICATION,
. AN EAR PLUG HAD BEEN USED FOR A GASKET IN ONE OF THE SIGHTGLASSES TO STOP A LEAK AliO THE EAR PLUG HAD PLUGGED THE SIGHTGLASS, BOTH AFWP TURBINE SIGHTGLASSES HAD DEFICIENCY TAGS ON THEM BECAUSE OF NOTED LEAKS, FOLLOWUP i
1.
LICENSEE l
MODIFIED SIGHTGLASS; BETTER VENT; SCRIBE MARKS, REVISED PROCEDURES FOR ADDING OIL.
DRAIN AND FILL SUMP WEEKLY, LOOK AT ALL SAFETY RELATED PUMPS, 2.
REGION FOLLOWING LICENSEE ACTIONS, O
l
PALO VERDE UNIT 1 - REACTOR TRIP, SAFETY INJECTION, LOSS OF PRESSURIZER AUXILIARY SPRAY SYSTEM SEPTEMBER 12, 1985 (E. A. LICITRA, NRR)
PROBLEM - DURING LOSS OF LOAD TEST, PLANT EXPERIENCED TURBINE TRIP, REACTOR TRIP, SAFETY INJECTION, CONTAINMENT ISOLATION AND GAS BINDING 10F ALL CHARGING PUMPS.
SAFETY SIGNIFICANCE - THE PRESSURIZER AUXILIARY SPRAY SYSTEM WOULD NOT HAVE 'BEEN AVAILABLE, IF REQUIRED, FOR RAPID DEPRESSURIZATION OF REACTOR COOLANT SYSTEM (PLANT DOES NOT HAVE PORVS).
SYSTEM NOT INSTALLED TO SAME SAFETY GRADE AS LICENSING BASIS.
GENERAL CONCERNS TURBINE CONTROLS DESIGN FAULTY (RUNBACK).
PLANNING FOR TEST INADEQUATE (TRANSFER).
INSTRUMENTATION PROBLEM (VCT LEVEL).
ELECTRICAL DESIGN FLAW (SHEDDING MCC-72),
i E0PS WEAK.
REPORTING INCOMPLETE.
~
POST-TRIP REVIEW WEAK, CORRECTIVE ACTIONS PLANT SHUTDOWN ON SEPTEMBER 16, 1985 (CONFIRMATORY ACTION LETTER ON SEPTEMBER 17, 1985).
SHORT TERM COMPENSATORY MEASURES ESTABLISHED FOR CONTINUED OPERATION:
DAILY CHECK OF VCT LEVEL INSTRUMENTATION REVISE PROCEDURES FOR MANUAL ALIGNMENT OF RWT TO CHARGING PUMPS UPON LOSS OF OFFSITE POWER.
INSTITUTE PROCEDURAL CAUTIONS ON RESTART OF CHARGING PUMPS.
1 i
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j i RE-EXAMINE POST-TRIP REVIEW PROCESS.
FOR REMAINING TEST PROGRAM, EXAMINE PROCESS FOR VENDOR REVIEWS.
REVIEW SHIFT COMPLEMENT FOR PEMAINING TEST-PROGRAM.
l RELEASED FOR RESTART SEPTEMBER 20, 1985 g
(NRR/R-V LETTER).
i t
LONGER TERM ACTIONS BY LICENSEE INCLUDE REVIEW OF AUXILIARY SPRAY SYSTEM TO DETERMINE:
J j
WHETHER SYSTEM NEEDS TO BE SAFETY GRADE.
WHAT CHANGES ARE REQUIRED TO MAKE IT 4
1 i
SAFETY GRADE.
STAFF PREPARING 50.54(F) LETTER CONCERNING RELIABILITY i
0F AUXILIARY SPRAY SYSTEM k
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DRESDEN 3 - SCRAM SOLEN 0ID PROBLEM INDUCED RCS LEAKAGE SEPTEMBER 19, 1985 (ERIC WEISS, IE)
PROBLEM - RCS LEAKAGE TO REACTOR BUILDING VIA LEAKING SCRAM S0LEN0 IDS AND SCRAM DISCHARGE VOLUME VENT AND DRAIN AND INTO VENT SYSTEM, SAFETY SIGNIFICANCE - INTERMEDIATE AIR PRESSURE CAUSES PROBLEMS WITH SCRAM SYSTEM VALVES.
POTENTIAL DEFICIENCY IN MODE SWITCH, SEQUENCE OF EVENTS REACTOR OPERATING AT 80% POWER TURBINE CONTROL VALVE FAST CLOSURE CAUSED BY INSTRUMENT TECH PRESSURE SPIKE CAUSES SCRAM ON APRM HI OPERATORS ATTEMPT TO RESET SCRAM BUT ONLY CHANNEL A RESETS (RESETTING CHANNEL A CAUSES SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TO OPEN)
LEAKING SOLEN 0ID VALVES CAUSE LOW AIR RESULTING IN PARTIALLY OPEN SCRAM OUTLET VALVE AND SDV VENT AND DRAIN VALVES STEAM IN REACTOR BUILDING AND RAD ALARMS ACTIVATE OPERATORS MANUALLY CLOSED SDV VENT ~AND DRAIN VALVES 3 INDIVIDUALS CONTAMINATED DURING EVENT i
CAUSES MODE SWITCH NOT MOVED ALL THE WAY T0 " REFUEL" (THIS PREVENTED RESETTING CHANNEL B) 51 SCRAM SOLEN 0 IDS LEAKED (LEAKAGE PATH WOULD HAVE BEEN BLOCKED IF CHANNEL B HAD RESET) 1 I
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LEAKAGE PATH FROM VESSEL THRU LEAKING SCRAM SOLEN 0ID VALVES T0 SCRAM DISCHARGE INSTRUMENT VOLUME LEAK LASTED FOR 23 MINUTES FOLLOWUP ACTION PLANT SHUTDOWN LICENSEE EVALUATING PROBLEM AND REPLACING SELECTED VALVES REGION FOLLOWING O
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PEACH BOTTOM UNIT 3 - CRACK INDICATIONS ON 3]6-L SAFE-ENDS I
SEPTEMBER 19, 1985 (G. GEARS, NRR) i PROBLEM - CRACK INDICATIONS FOUND IN 316-L SAFE-ENDS.
SAFETY SIGNIFICANCE - CRACKS NOT PREVIOUSLY IDENTIFIED I
IN THIS AREA.
i DISCUSSION CURRENT GENERIC LETTER 84-11 INSPECTIONS FOUND CRACKS IN THE 28" RECIRCULATION SAFE-END TO PIPE WELD, AS WELL AS CRACKS IN 12" SAFE-END TO THERMAL SLEEVE LOCATION I
(LIKE PEACH BOTTOM UNIT 2).
28" SAFE-ENDS WERE REPLACED WITH 316-L (.019 CARBON)
PRIOR TO START OF COMMERCIAL OPERATION (1974),
SAMPLES HAVE BEEN TAKEN TO DETERMINE REASONS FOR i
CRACKING.
316-L IS SOMEWHAT MORE LIKELY TO BE SENSITIZED BY j
WELDING THAN 316-NG, BUT CLEARLY BOTH CAN BE i
SENSITIZED IF ENOUGH HEAT IS APPLIED, SUCH AS BY REPEATED WELD REPAIRS.
STAFF POSITION IS THAT'THE L GRADES, AND EVEN THE NG GRADES, CAN BE SENSITIZED AND MADE SUSCEPTIBLE To IGSCC IF THEY ARE MISTREATED.
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NRR FOLLOWING AND WILL MEET WITH LICENSEE.
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FERMI OPERATING EXPERIENCE SEPTEMBER 23, 1985 (M. CARUS 0, NRR)
OPERATING EXPERIENCE FOR PAST SIX MONTHS REVIEWED LOW POWER LICENSE PERIOD (MARCH 20 - JUNE 20)
PAST THREE MONTHS (JUNE 20 - SEPTEMBER 20) d REVIEW INCLUDES PROMPT REPORTS, LERS, EVENT BRIEFINGS AVERAGE FREQUENCY OF REPORTABLE EVENTS IS 10/ MONTH; SIMILAR TO LIMERICK AND GRAND GULF IN COMPARABLE PERIODS MAJORITY OF EVENTS ARE OF LOW SIGNIFICANCE INDIVIDUALLY AND CONCERN THE FOLLOWING:
INADVERTENT RPS/EFS ACTUATIONS ENTRY OF TECH SPEC ACTION STATEMENTS MINOR TECH SPEC VIOLATIONS SEVERAL SIGNIFICANT EVENTS IN PAST THREE MONTHS:
INADVERTENT CRITICALITY JULY 2, 1985 I
INOPERABILITY OF ALL Div. I ECCS AND DG - JULY 22, 1985 RECIRCULATION PUMP OVERSPEED/ REACTOR POWER TRANSIENT - AUGUST 25, 1985 UNDETECTED BREACH OF PRIMARY CONTAINMENT -
SEPTEMBEP 9, 1985 RECENT EVENTS OPERATOR ERROR DURING CONTROL ROD WITHDRAWAL -
SEPTEMBER 13, 1985 CRACKS DETECTED IN MAIN STEAM BYPASS LINES -
SEPTEMBER 17, 1985 i
l l
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DAVIS-BESSE - MAINTENANCE SURVEY SEPTEMBER 16-20, 1985 (D, PERSINK0, NRR) i E
PURPOSE OF SITE VISIT 1
CONDUCT MAINTENANCE SURVEY IN ACCORDANCE WITH MAINTENANCE / SURVEILLANCE PROGRAM PLAN TO GATHER l
INF0PMATION REGARDING MAINTENANCE PRACTICES PRIOR TO l
}
JUNE 9, 1985 EVENT.
OBTAIN INFORMATION ABOUT PROPOSED CHANGES AFFECTING j
THE PERFORMANCE OF MAINTENANCE, DEFINE ANY DEFICIENCIES OR OMISSIONS.
MAJOR OBSERVATIONS BY NRC TEAM REGARDING MAINTENANCE PRIOR j
TO JUNE 9, 1985 EVENT, i
LACK OF CORPORATE SUPPORT i
LACK OF PROCEDURAL DEPTH /0VER-RELIANCE ON SKILL l
OF CRAFT, INSUFFICIENT NUMBER OF SUPERVISORS / FOREMEN l
OVERBURDENED,
{
COMMUNICATIONS,
{
LACK OF CLEAR CUT RESPONSIBILITIES.
TRAINING DEFICIENCIES, EXCESS MAINTENANCE BACKLOG PREVENTIVE MAINTENANCE DEFICIENCIES.
l SPARE PARTS AND MATERIAL READINESS WEAKNESSES,
)
LICENSEE HAS IDENTIFIED MANY DEFICIENCIES REGARDING MAINTENANCE PRIOR TO JUNE 9, 1985 EVENT AND HAS TAKEN STEPS TO RECTIFY, 1
1 TOO EARLY TO DETERMINE THE EFFECTIVENESS OF THESE CHANGES.
STAFF PREPARING SAFETY EVALUATION REPORT, 4
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_ =. _.. _. _ _ _. _ _ _ _ _ _ _ _. _ _.
NORTH ANNA UNIT 1 - EDG ENGINE FAILURE SEPTEMBER 18, 1985 (J. T. BEARD, NRR)
I PROBLEM - EDG "1J" CYLINDER FAILED DURING SCHEDULED TEST!MG, i
SAFETY SIGNIFICANCE t
NORTH ANNA HAS HISTORY OF EDG FAILURES.
l THIS MAY BE A NEW FAILURE MECHANISM.
DISCUSSION ENGINE TRIPPED ON HIGH CRANKCASE PRESSURE SUBSEQUENT
{
TO SCHEDULED MAINTENANCE.
LICENSEE INSPECTION REVEALED THAT:
- 10 CYLINDER LINER SEVERELY CRACKED (ALL TESTED).
- 10 PISTON " WOBBLY" ON WRIST PIN; OTHER l
OUESTIONABLE.
MOUNTING BOLTS FOR ALL CYLINDER LINERS FOUND LOOSE; CYLINDERS #9, 10, 11, 12 BOLT HOLES
- STRIPPED, BOLTS NOT ON MANUFACTURER'S INSPECTION LIST.
LICENSEE SAYS NEW FAILURE MECHANISM, DUE TO SOME TYPE OF OVERLOAD, SUCH AS FAST STARTS; THERMAL CYCL!NG OF l
BOLTS.
PREVIOUS FAILURES ON UNIT 2 AND ENGINE lH.
4 i
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FOLLOWUP MANUFACTURER REPRESENTATIVE ON-SITE.
RECOMMENDED REPLACEMENT OF ALL PISTONS AND 24-HOUR BREAK-IN RUN, SEPTEMBER 21, 1985 (0710 HOURS) PLANT SHUTDOWN INITIATED: TS ACTION STATEMENT EXPIRED, WENT TO COLD SHUTDOWN (SEPTEMBER 22, 1985, 1805 HOURS).
EDG REPA!RS COMPLETED; PLANT WAS BACK INTO HOT SHUTDOWN AT 1100 HOURS, SEPTEMBER 23, 1985.
PLAN TO RETURN TO POWER SEPTEMBER 23, 1985, REGION II, ORAB FOLLOWING REGARDING ROOT CAUSE 1
AND GENERIC IMPLICATIONS, 11 9
HADDAM NECK CONTROL ROD MISALIGNMENT ANALYSIS NOT PERFORMED SEPTEMBER 16, 1985 (F, AKSTULEWICZ, NRR) 4 PROBLEM:
CONTROL R0D MISALIGNMENT ANALYSIS WAS NOT PERFORMED FOR CYCLES 10, 11, 12 AND 13 AS REQUIRED BY TECHNICAL SPECIFICATION 3,17, SAFETY SIGNIFICANCE:
UNAVAILABILITY OF ANALYSIS COULD HAVE RESULTED IN CORE PEAKING FACTORS OUTSIDE THE DESIGN BASES, DISCUSSION:
CONTROL R0D MISALIGNMENT ANALYSES ARE PERFORMED TO DETERMINE THE LIMITS FOR THE POWER PEAKING FACTORS IN THE CORE, REQUIRED ANALYSES PERFORMED FOR CYCLE 9 RELOAD BY i
BABC0CK & WILC0X ESTABLISHED A GENERIC PENALTY FACTOR OF 5% AXIAL 0FFSET TO ACCOUNT FOR R0D MISALIGNMENT OF
!40 STEPS, CYCLES 10 AND 11 INVOLVED NO CORE MODIFICATIONS, 1
5% AXIAL OFFSTE PENALTY TAKEN FOR AXIAL OFFSET -
N0 NEW ANALYSIS DEEMED NECESSARY BY LICENSEE, CYCLE 12 INVOLVED A FUEL DESIGN CHANGE AND A j
SUBSEQUENT CHANGE IN LINEAR HEAT GENERATION RATE, NEW AXIAL OFFSET LIMIT CURVES CALCULATED AND ACCEPTED BY NRC, NO PENALTY FACTOR USED IN ANALYSIS FOR AXIAL OFFSET CURVES TO ACCOUNT FOR R0D MISALIGNMENT OF ! 40 STEPS, l
a
' CYCLE 13 (CURRENT CYCLE) - NO CORE OR FUEL MODIFICATIONS
)
FROM CYCLE 12 - NO TS CHANGES - ANALYSIS FOR CYCLE 12 ASSUMED TO BE VALID, DURING OPERATION IN CYCLE 12 & 13 LICENSEE NEVER APPROACHED LIMITS OF AXIAL OFFSET CURVES: PRIMARY l
COOLANT ACTIVITY LEVELS WERE NORMAL.
}
B&W HAS CONFIRMED THAT FOR A LOCA a 100% POWER WITH A 40 STEP CONTROL R0D MISALIGNMENT, THE CURRENT AXIAL OFFSET CURVES WOULD LIMIT THE LOCAL POWER PEAKING FACTORS TO LESS THAN THE DESIGN BASES (PEAK CLAD l
TEMPERATURE LESS THAN 2300*F),
FOLLOWUP
-i LICENSEE INITIATED REMEDIAL ACTIONS TO LIMIT CORE PEAKING FACTORS (AXIAL OFFSET) UNTIL COMPLETE VERIFICATION. ANALYSES CAN BE PERFORMED AND TO REDUCE l
THE AMOUNT WHICH A CONTROL R0D CAN BE OUT OF ALIGNMENT, c
i LICENSEE ALSO REVERIFYING ALL TRANSIENT ANALYSES USING THE 5% PENALTY, j
{;
B&W PERFORMING ANALYSES FOR VERIFICATION THAT CURRENT 3
AXIAL OFFSET CURVES FOR ALL OF CYCLE 13 WERE B0UNDING, NRR WILL REVIEW THE RESULTS OF THE VERIFICATION ANALYSES
}
SUBMITTED BY THE LICENSEE,
{
REGION 1 WILL FOLLOWUP ON 30 DAY LICENSEE EVENT REPORT,
}
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PALISADES - MISCALIBRATED PRESSURIZER PRESSURE CHANNELS SEPTEMBEh 14, 1985 (T WAMBACH, NRR)
PROBLEM - ALL FOUR PRESSURIZER PRESSURE TRANSMITTERS THAT l
FEED THE REACTOR PROTECTION SYSTEM WERE CAllBRATED.
APPROXIMATELY 35 PSI LOW (REACTOR TRIP AT 2290 PSIA VICE 2255 PSIA).
SAFETY SIGNIFICANCE - COMMON MODE FAILURE CAUSED BY INSTRUMENT CALIBRATION ERROR.
DISCUSSION f
REACTOR IN HOT STANDBY REPLACING PRESSURIZER PRESSURE CONTROL CHANNEL TRANSMITTER AND FOUND IT MISCALIBRATED j
CALIBRATED THREE WEEKS EARLIER ALONG WITH THE FOUR RPS PRESSURE TRANSMITTERS I
DEAD WEIGHT TESTER USED WITH ALUMINUM WEIGHTS; CONVERSION CHART USED FOR BRASS WEIGHTS j
MISUNDERSTANDING BETWEEN LAB AND SITE WEIGHTS GIVEN VALUE OF 4 PSI VICE 40 PSI SAME l&C TECH DID ALL CAllBRATIONS FOLLOWUP i
l LICENSEE EVALUATING PROBLEM AND CORRECTIVE ACTION l
CONVERSION CHART NOT AVAILABLE AS FOUND READINGS VS AS LEFT READINGS i
REGION EVALUATING CALIBRATION PROCEDURES AND TECHNICIAN TRAINING NRR SHOULD CONSIDER BROADENING IMI ITEM REGARDING INDEPENDENT OPERATOPS FOR LINE-UPS OF REDUNDANT SAFETY RELATED SYSTEMS TO INCLUDE ISC PERSONNEL i
i i
l l
=
____-_-__- _. _~_-_.____.. _.._._._ _ _ _ _____ _..__ _._,__._. _
UNPLANNED REACTOR TRIPS
- AVERAGE WEEKLY TRIP FREQUENCY FOR PAST WEEK IS APPROXIMATELY 8 TRIPS / WEEK, WHICH IS NEAR AVERAGE BREAKDOWN OF REPORTED CAUSES AUTOMATIC EQUIPMENT FAILURES 25%
PERSONNEL ACTIVITIES 50%
MANUAL 25%
- BASED ON 10 CFR 50.72 REPORTS FOR PLANTS WITH LICENSES FOR FULL POWER OPERATION i
J 3
I Face ha.
1 09/30/S5 0FERATINS REACTORS' EVENTS MEETING FOLLOWUF ITEMS AS OF MEETINS E5-17 DN SEPTEMBER 23.1985 1
(IN ASCEh In3 MEETINS DATE, NSSS VEht0R. FACILITY ORIER)
I 1
F.EETINS FACILITf RESPON$ tile TASK DESCRIFTION SCHEDULE CLOSED DATE COMENTS htMSER/
kSSS VE CC;i EIVISION/
COMFLET.
EY CCCUMENT.
}
KEETIh5 EVENT IESCRIF.
IO!VIDLAL LATEtS)
MEETINS. ETC.
i IATE i
RAN:HO SEC3 1 IC55/RCSA. F.
SUMAR!IE 11W LIC. RESFCNSES TO 10/30/95 0 FEN
/ /
STAFF REVIEW CF 04/10/54 Se / MAIN SEN
/
L ESTIONS SUBSEQUENT TO RANCH 3 09/30/85 Eli CohERS GROUF H1:F;SEN SECO LOSS OF NNI EVENT AhD 09/30/E5 SUIMITTAL GF l
EIFLOSICh -
FRESENT AT FOLLOW-UP OR EVENTS 1/11/65 IS Ik FARi!AL LOSS OF BRIEFIh5 FR06RESS (THIS i
NN! 3/19/S4 REACTIVATEL-CRYS.RIV. 31 J
CRYSTAL RIVER 3
! CSS /RDSA,F.
CCNSIDER NEED FOR ADDITIONAL 12/30/B5 CFEN
/ /
ICSB IS 01/03/65 in / TEMF LCSS
/
RE DIREMENTS ON ALARMS /
09/30/65 CONSICERINS CCCNEE l
CF hiI 12/:i/54 ANN'.h:IATORS 07/30/85 1 LOSS OF
{[
ANNUNCIA.
(4/25/94) IN ANAL.
0F REQUIREMENTS.
MILLST0hE 2-CRAS/MURPHf. E.
REVIEW $505 LETTER ON EDDY
!!/30/85 0 FEN
//
ORNL CONTRACTED TO
)
0$!07/85 CE / ELDY DE /CONRAD. H.
CURRENT TESTINS ISSUE, IN VIEW 10/01/85 EVALUATE EFFECT OF CURRENT TEST OF QF MILLSTChE 2 FINDINGS.
06/07/85 C0FFER ON ELDY STEAM.SEN.
-DELAtS IN CRNL l
TESTING j
CATAs!A 2 LL IJAIECUR, K.
FOLLOW UF BRIEFING AFTER EVAL.
10/07/85 CFEN
/ /
FOLLCW UF BRIEFINS 05/07/E5 W / B;iH RhR
/
OF CVERPRESS. EFFECTS ON 09/30/85 SCHELULED ON 1
j TRAIh5 VARIOUS SYSTEMS AND CCRRECTIVE 08/07/85 10/07!35 OVERFRESSUR!IED ACTIChS.
I 4/19/E5
}
65-10 LAVIS BESSE I LS! /FARR. D.
RE-EIARINE STAFF REVIEW OF 09/30/85 0 FEN
/ /
!!T REFCRT U GER 06/l:/65 is / LOSS OF ALL EL /CEAGAZIO,A. ACCEFTAi!LITY/ DIVERSITY OF 02/30/85 REVIEW MAIN A M Aul.
06/19/35 j
FEE;b;TEF e/9/55 1
i 55-10 LAVIS i!SSE 1 DL /DEASAII0,A. FROVILE H. LENTON WITH 09/30/85 0 FEN
/ /
ITEM 2 IN 06/12/E5 BW / LCSS OF ALL
/
1)COMPARISCh BETWEEN DAVIS 03/30/85 ITEM 1-3 FROS;ESS.
MAIN AO AUI.
BESSE 1 A C TM!-! 0F TMI ACTICN 06/19/85 COMFLETED FEEIhATER 6/9/95 PLAN IMPLEMENTATION STATUS l
TMI-!
- 3) STATUS OF STARTUP FW FUMP uFSn:E.
I l
l E5-11 RANCHO SECO 1 DL / MINER, S.
CETEFMINE STATUS OF IEB 79-14.
09/30/85 CLOSED 09/30/85 THE LICENSEE IS 07/01/65 BW / RCS HISH
/
08/30/85 COMPLETED COMPLETING THE FO!NT VENT LEAK,
/ /
09/06/65
[hSFECTION l
6/23/25 l
l
Fage h:.
09/30/55 CFERATING REACTORS' EVENT 5 MEETING FULLChjf liEM5 AS CF MEETIN3 E5-17 CN EEFTEMiER :.1955 (IN ASCEN;1N5 MEETIh5 LATE. N555 VEh:CR. FACILIT) CF;ER)
FEEi!%5 FACILIT)
EE5FCN51 ELE Tait CES:RIFTION SCHECULE CLO5ED PATE COVENT5 mLMiER/
hiis VEN:C;/
- IVISICN!
CCMFLET.
if DCCL"ENT, rEETIN5 E.'ENT ;ES:!IF.
Ih;IVIDUAL CATEisi MEETIh5. ETC.
IATE E5-11 RANCHO EECO 1 lL ! MINER. 5.
5thEULE CChFEREN:E CALL h1TH 09/ 0/25 CLOSE: 09/ 0/65 E.ALUATION IN 07/01/55 in ! STARTL:
/
RESICN AND LICEh5EE FRICR TC 05/15/85 CCNFEREN:E HELL FR:5;E55 FR:ELEM5-JL%E RESTART TO LETERMIhE PLANT 07/12/B5 09/2;/55 1955 READIhESS FOR OFERATICh5.
25-!!
OYSTER CREEE 1 OmF5/CLArTCN B.
CETERMINE EFFICACY 0F EF5/
10/30/E5 0 FEN
/ /
" -07/01/55 GE /
/
OFERATCR A: TION ANC EICESSIVE 01/15 55 LN:CNTRCLLE; RE5FCh5E TIME.
05/;0/65 LEAK ABE OF FEACT:F COULANT CUT 5IEE CC%iAI4 MENT bl11/B5 85-12 SEAERD:t OSI / MAR 5H ANALVIE SAFETr IMPLICATICNS OF 09/;0/85 0 FEN
/ /
07/2;/25 h / CR055Y MAIN
/
VALVE FLCm LEFICIEhCY
/ /
STEAM SAFET)
/ /
VAL'vE FLCh IEFICIEhtr 12/54 83-12 SEAisCOL DE /CHERhEY INVE5il5 ATE ADECUACf CF TESTING 09/30/E5 CLCSED 09/30/85 07/2:135 W / CR;55t MAIN
/
A%D VALIDITY OF EliRAF0 LATINS
/ /
09/27/E5 MEND R SIElM 5AFE7/
IATA FRCM SMALL TO LARGE VALVES / /
EC5NAt TO D VfG E FLCh CRUTCHFIELL CEFICIENCY 12/E4 25-13 CALVERT CLIFFS AECD/LA% !N5. W IETERMI*.E IF RECENT GE AK-2-:5 09/30/95 CLOSED 09/30/85 0S!!!/25 CE 1 EEA;TCR
/
TRIF SAEAtER FROBLEM5 REPORTED 09/13/E5 AECD CONF?RMED TRIP EFEMER Vit hFRL5
/ /
RECEhiAK-2-25 F9:iLEM TRIF SFEAKEF FFCELEM5 KEFORTED V!A hFFDS 23-13 FEREIEN IE /FD551. E.
C:h5!LER ISSUANCE 0F IE 10/:0/55 OPEN
/ /
IE h;TICE IN L8/1;!25 hA / M ATIFLE
/
INF0FMATICN NOTICE.
09/30/65 CCN:UFFENCE FEE!htTER 09/03/85 FAILUFE5 E5-!;
FDINT BEACH IE /LCNG. 5.
DRAFT INFCFMATION NOTICE ON FT.
09/30/85 CFEN
/ /
LFAFT IE NOTICE IN 08/1 /85 W / SAFEif GRAi/CARU50. M.
EEACH EVENT. CGNSIDER TEMP.
09/13/95 NFR C;NCURRENCE INJECTICN Ih5TRUCTION FOR RES. INSFECTGR
/ /
MIN!-FLCu RECIFC RESARLIk5 CCMPLIANCE WITH AFF.
LESIGN k
IEFICIENCY
Page he.
3 09/30/85 l
OFEFATIAS REACTORS' EVENTS MEEilh6 FOLLOWUF ITEMS A5 0F MEET!h5 85-17 ON SEFTEMBER 23,1995
(!h ASCEhDIh5 MEEilh5 LATE, N555 VENDOR, FACILITV ORDER)
EETING FA !LITY RE5F0h5!BLE TAst DESCRIFTION SCHEDULE CLOSED liATE COMMENTS NZiER/
h555 VEhDDR/
DIVISION /
COMFLET.
BY LOCUMEhi, r.EET!h5 EVEhiDES:RIF.
IkMVIDUAL DATE(5)
MEETING,ETC.
CATE i
j B5-13 TGKEt FOINT 3 DL /M: DONALD,D. HAVE LICEh5EE INCORFORATE USE 10/13/85 0 FEN
/ /
05/13/85 h / POST-TRIF
/
OF M3 TOR IRIVEN AFh PUMF5 th I /
LCES OF AFh Ch EMER5EN:VFROCEDURES
//
7/21/85 25-13 T5 LEY FDINT 3 D51 /FARR, D.
REVIEW ADEQUACY OF 60VERNCR 01/05/66 0 FEN
/ /
" *05/13/E5 W / FC5T-TRIF
/
LESIGh Ch TUREINE DRIVEN AFW 10/13/25 LOSS OF AFW FUMf5
//
E5-14 CATAn5A 1 D51 /5RINIVA5An M REVIEh SEFARATION OF UNIT 1 AND 10/15/E5 0 FEN
/ /
05/26/E5 h /Eia:KDUT
/
UNIT 2 AEL MEET WITH DULE PRIOR 09/30/05 SIGNAL AhD TO LICEN5!hG OF UNIT 2
/ /
INTEu;TICh EETaEEAth!T51 AN: 2 i
. / UhlTS 1 AN:
/
Ah! STATUS OF EQ REVIEW 09/30/85 SCHEDULE BElh5 2 VE.aTARY
//
TRAttED UNDER B 5 GitCeN 11 TVA l
EECAUSE CF 60
~
ECUIPMEhi QUALIFICATICN (ED INA;EQUA lES 55-14 SEGU0VAH LL /STAHL C INITIATE STAFF REVIEW OF TVA 12/30/85 0 FEN
/ /
i l
OE/2c/E5 W / UhlT5 1 ANL
/
SUEMITTALS 09/30/E5 2 VOLUNTART
//
SHUTLCsN ti TVA j
EECAU5E CF EGulFMEhi QUALIFICATION (EQi INALECUA;1ES 55-15 FEPMI 2 DL /CARUSO M FREFAFE
SUMMARY
OF OFEMTING 10/01/05 CLOSED 09/30/85 09/09/E5
/ VIOLATICh GF
/
EVENT 5 CONTAIhMEhi
//
GFERATING INTEGRITY
/ /
REACTORS EVENT BRIEFING 09/23/65 25-15 FEACH ELTT0* 3 LE /LIAd B L LETERMikE WHAT FUTURE ACT10h10/15/25 0FEh
/ /
GWNERS GROUP 09/09/E5
/ NEW FIFE LE /HAIELTON W kEELEL GN GENERIC BASIS
/ /
CRACK MEETING SCHEDULED
/ /
10/03/85 INDICATIONS s.
L
i I
~
Page ho.
4 09/30/65 0FERATIh3 REACT 0;s' EVENTS MEET!h5 FOLLCduF ITE*5 A5 0F MEETIh5 85-17 CN SEPTEMBER 23.1985 (IN A5CEh3!NG ?EETIh5 IATE h555 VENDOR, FACILITY OFIER)
EEETIh5 FACILI!t RE5FJN51BLE TA5A CE5CRIFTICN SCHEEULE CLC5ED DATE COMMENTS n;MiEpi hiS5 iEh:CA/
IIVISICN/
CCMFLET.
BY DOCU=ENT, rEETING E' VENT IE!CRIF.
INDIVIDUAL DATE(5)
MEET!hi,ETC.
IATE 55-15 FEACH E3iiCF CE /LIAW 6 D FOLLCn-UF FEQUALIFICATICN OF 10/15/55 CFEh
/ /
CANERS GROU; 09/09/55
/ hen FIFE IE /HA!ELTCN h IN5FECTORS ISSUE
/ /
MEE!!h5 5ChE ULEL C7 '.:t
/ /
10/0:iE5 Ih:!CATICh5 E5-15 FEA:H 5:TICM 3 IE /EAER R REEIAM!hE HEED FOR AN3THER IE 10/15/55 CLC5EL 07i;0/55
-09/09/55
/ men FIFE
/
EULLETIN
/ /
IE PULLEi!N CFACt
/ /
n!LL h ! EE Ih;ICATICh5 IS5UED-!!EM CC'iERED UNDER REV 2 CF NURE6 0:13 85-16 I'VI5-5E55E IE /
C:h5!IER IE NOTICE 11/01/E5 CFEN
/ /
]9/16/55
/ STEAM
/
/ /
EEWERATCR
//
0~,ERFRE55URIZATI CN i:5-16 SLaER
- L 1EASAII0 A MAKE SURE DAVIS-5 ESSE IS AWARE 10/01/55 CLC5ED 09/30/85
--09/16/55
/ lh3TRUMENT
/
OF THIS EVENT
//
L'ICEN5EE WA5 AIR FRE55URE
/ /
INFCRMED ABOUT FEL;ilCN THIS EVENT 09/20/85 E5-17 IRE 5'Eh LL /ZhCLINSKI J DETERMINE WHY EDV 15 h3T VENTED 11/08/85 0 FEN
/ /
09/2;/85
/ SCRAM
/
TO SA5 ECUS RAD WA5TE SYSTEM
//
SJLEN:IC FRCELEM
//
Ih0JCE3 RCS LEAKAGE B5-17
/ /
09/2;/55
/ SCRAM
/
/ /
SCLEh0!LFFC5LEM
/ /
Ih;UCED FC5 LEAXAEE C5-17 FALD VERDE 1 LL /tNISHTCN 6 IETERMINE WETHER FRGBLEM 15 11/02/85 0 FEN
/ /
09/23/25
/ REACTOR
/
SEhERIC TO WATEFFCRD AND SAN
/ /
TRIF.5AFEif Ch3FFE
/ /
INZECTICN.LG55 0F FRE55URIZER AUIILIARY 5FFA Sf5 TEM