ML17199F715
| ML17199F715 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Dresden, Davis Besse, Peach Bottom, Mcguire, Palo Verde, Grand Gulf, Cooper, Arkansas Nuclear, Columbia, North Anna, Turkey Point, Crystal River, Robinson, Maine Yankee, McGuire, 05000000, 05005288, Crane |
| Issue date: | 03/26/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEIN-86-019, IEIN-86-19, NUDOCS 8604070516 | |
| Download: ML17199F715 (17) | |
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J MEMORANDUM FOR:
FROM:
SUBJECT:
MAR 2 6 1986 Harold R. Denton, Director Office of Nuclear Reactor Regulation Gary M. Holahan, Director Operating Reactors Assessment Staff
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON March 24, 1986 - MEETING 86-09 On March 24, 1986, an Operating Reactor Events meeting (86-09) was held to.
brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 17, 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 arid the status of previous assignments ~re 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, x29526) if the target completion date cannot
- be met.
Enclosures:
As stated tc w/encl:
See next page
_QI.STRIBUHO~,
'Ce.ntr-al Files-*
NRC PDR ORAS Rdg ORAS Members OR~-/ *°Rf DT~9off:dm RWessman
.J 126/86 J lt?/86
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Gary M. Holahan, Director
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Operating Reactors Assessme~t Staff 1to~~*
GHolahan J /'l.7/86
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MEMORANDUM FOR:
FROM:
5UBJECT:
e e
UNITED STATES
. NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 IAR 2 6 1986 Harold R. Denton, Director Office of Nuclear Reactor Regulation Gary M. Holahan, Director Operating Reactors Assessment 5taff 5UMMARY OF THE OPERATING REACTOR5 EVENT5 MEETING ON March 24, 1986 - MEETING 86-09 On March 24, 1986, an Operating Reactor Events meeting (86-09) was held to*
brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 17, 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 ORA5 (D. Tarnoff, x27864) if the target completion date cannot be met.
Enclosures:
As stated cc w/encl:
5ee next page q.r7~-P-
~
Gary M. Holahan, Director
~
Operating Reactors Assessment 5taff
Harold cc:
D. Eisenhut M. Licitra J. Taylor G. Knighton
.C. Heltemes L. Engle T. Murley, Reg. I L. Rubenstein J. Nelson Grace, Reg. I I L. Kintner J. Keppler, Reg. I I I
- w. Butler R. D. Ma rt in, Reg. IV J. Stolz J. B. Martin, Reg. v H. Silver R. Starostecki, Reg. I G. Vissing R. Walker, Reg. II A. DeAgazio
- c. Norelius, Reg. I I I P. Sears E. Johnson. Reg. IV
- w..Long D. Kirsch, Reg. v R. Becker H. Thompson D. Muller F. Miraglia R. Bernero T. Speis
- w. Russell T. Novak F. Schroeder
- w. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas
- v. Benaroya
- w. Regan D. Vassallo E. Jordan E. Rossi R. 8qer E. Weiss R. Hernan
- s. Showe
- s. Rubin
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-09)
March 24, 1986 NAME DIV IS ION NAME DIVISION R. Becker NRR/BWRFOB L. Engle PWR-A/NRR R. Hernan NRR/PPAS E. L icitra NRR/PBD7
- w. Haass IE/VPB M. Caruso NRR/ORAS
- w. Swenson NRR/ORAS D. Ziemann DHFT B. Clayton NRR/PWRA E. Weinkam NRR/PWR
- c. Mi 11 er NRR/BWRB D. Vass a 11 o DBL/FOB G. Plumlee PWRB/FOB F. Allenspach PWRB/FOB P. Sears NRR/PWRB G. Murphy ORNL R. Jones NRR/PWRB
- c. Thomas NRR/PWRB J. Fair IE/DEPER A. DeAgazio PB6 L. Kintner BWD4 E. Weiss IE/DEPER G. Klingler IE/Dl/ORPB
- v. Hodge IE/DEPER J. Henderson IE/DEPER E. Brown AEOD/ROAB J. Carter NRR/ORAS A. Dromerick IE/DEPER E. Jordan IE/DEPER K. Kniel NRR/DSRO T. Novak NRR/PWRA J. Stolz NRR/PWRB R. Houston NRR/DBL F. Schroeder NRR/PWRB B. Sheron NRR/DSRO R. Baer IE/DEPER J. T. Beard NRR/ORAS D. Tarnoff NRR/ORAS
}\\
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-09 MARCH 24, 1986 PALO VERDE UNIT 1 PIPE SUPPORT FAILURE NORTH ANNA CONTINUING PROBLEMS ON EDG ENGINES - UPDATE GRAND GULF UNIT 1 EXCESSIVE LEAKAGE FROM ADS CONTROL AIR SYSTEM COOPER OTHER EVENTS OF INTEREST FAILURE OF BYRON-JACKSON REACTOR COOLANT* PUMP SHAFTS UPDATE INADEQUATE CONSIDERATION OF OPERABILITY REQUIREMENTS
PALO VERDE UNIT 1 - PIPE SUPPORT FAILURE MARCH 13, 1986 (E, A. LICITRA, NRR)
PROBLEM:
INADEQUATE DESIGN WHICH RESULTED IN PIPE SUPPORT FAILURE.
SIGNIFICANCE:
0 0
0 POTENTIAL COMMON MODE FAILURE MECHANISM, POSSIBLY LEADING TO ACCIDENT BEYOND DESIGN BASIS.
DESIGN DEFICIENCY DUE TO IMPROPER CONSIDERATION OF LOCALIZED FLANGE BENDING DURING THE ORIGINAL DESIGN.
POTENTIAL FAILURES OF SUPPORTS FOR MAIN STEAM LINE, MAIN FEEDWATER LINE AND SAFETY INJECTION LINE 0
APPLICABLE TO ALL 3 PALO VERDE UNITS; POSSIBLY OTHER SITES DISCUSSION:
0 UNIT 1 IN MODE 5; UNIT 2 IN MODE 4; UNIT 3 NOT YET LICENSED 0
ON UNIT 1, BROKEN PIPE HANGER FOUND ON STEAM GENERATOR (SG) #2 0
0 0
ECONOMIZER LINE DURING ROUTINE SNUBBER SURVEILLANCE CAUSE OF THE BROKEN PIPE HANGER IDENTIFIED AS DESIGN ERROR.
REVIEW OF DRAWINGS AND ANALYSIS REVEALED 5 ADDITIONAL PIPE SUPPORTS IN EACH UNIT HAVE SAME DEFICIENCY AND REQUIRE MODIFICATION (TOTAL OF 18)
EVALUATION INDICATED THAT SUPPORTS FOR MAIN STEAM LINE, MAIN FEEDWATER LINE AND SAFETY INJECTION LINE IN EACH UNIT COULD HAVE FAILED IN NORMAL PLANT OPERATION FOLLOW-UP:
0 0
0 UNITS 1&2 WILL BE MAINTAINED IN THE EXISTING OPERATIONAL MODES UNTIL CORRECTIVE ACTIONS ARE IMPLEMENTED AND DISCUSSED WITH NRC CORRECTIVE ACTION IS TO STIFFEN SUPPORTS BY USE OF GUSSETS LICENSEE IS SUBMITTING AN EXPEDITED LER ON THIS EVENT.
NORTH ANNA - CONTINUING PROBLEMS ON EDG ENGINES UPDATE - (J, T. BEARD, NRR)
PROBLEM 0
MAJOR INSPECTION OF EMERGENCY 1 DIESEL GENERATOR (EDG) "2H" REVEALED ELONGATION OF FLOATING BUSHINGS OF WRIST PINS ON 5 PISTONS, MOSTLY UPPER PISTONS 0
0 EDG "2J" ELECTRICALLY OVERLOADED INADVERTENTLY DURING TESTING.
INSPECTION OF EDG "2J" REVEALED SEVERAL ELONGATED FLOATING BUSHINGS, SOME IN CONTACT WITH INSERT BUSHING, AT LEAST ONE INSERT BUSHING EXTRUDED.
SIGNIFICANCE
° CONTINUING UNRELIABLE EMERGENCY POWER SOURCES AT THIS STATION.
0 REDUCTION OF "FAST, COLD" STARTS AND "FAST" LOADINGS DID NOT STOP ENGINE FAILURES.
0 0
ROOT CAUSE(S) OF FAILURES NOT WELL ESTABLISHED.
POTENTIAL COMMON MODE FAILURE MECHANISM.
DISCUSSION 0
MEETING WITH LICENSEE AT PLANT, MARCH 19, 1986; LICENSEE PRESENTATION ON FAILURE SEQUENCE, ROOT CAUSE, AND CORRECTIVE ACTIONS; INSPECTION OF PARTS REMOVED FROM EDG "2J".
0 0
0 LICENSEE'S FAILURE SEQUENCE:
ELONGATION OF FLOATING BUSHING ON WRIST PIN.
LOSS OF GAP (NOMINAL 0.035 INCH) BETWEEN FLOATING AND INSERT BUSHING.
EXTRUSION OF INSERT BUSHING.
PISTON SKIRT FORCED OUTWARD RADIALLY.
PJSTON SKIRT CONTACTS CYLINDER LINER.
CYLINDER LINER CRACKS, FAILS.
ENGINE TRIP ON HIGH CRANKCASE PRESSURE.
LICENSEE BELIEVES NOW THAT MOST PROBABLE ROOT CAUSE IS INADEQUATE LUBRICATION (HEAT REMOVAL) DUE TO USE OF IMPROPER LUBE OIL.
FLOATING BUSHING ON WRIST PINS OF UPPER PISTONS APPEARS TO BE THE COMPONENT MOST SENSITIVE TO "OVERLOADING" DUE TO DESIGNED-IN HIGHER STRESSES OF UPPER CRANKLINE AND HIGH TEMPERATURES.
INSERT BUSHING LOCK PIN PISTON PIN BUSHING
. illus. C:i3.
Piston and Connecting Rod Disasl!embled
DISCUSSION (CONT'D) 0 LICENSEE'S CORRECTIVE ACTIONS:
ON UNIT 1 EDG'S, REPLACE LUBE OIL (WITHIN 7 DAYS)
ON UNIT 1 EDG'S, MEASURE GAP BETWEEN FLOATING AND INSERT BUSHING (WITHIN 45 DAYS),
PRIOR TO UNIT 2 RESTART, CONFIRMATORY POWER RUN ON EOG '2H" TO DEMONSTRATE NO ELONGATION IF NEW LUBE OIL USED.
= EOG '2H" HAS HAD 52 HOURS RUN TIME SINCE INSPECTION/REBUILD IN MARCH 1986 (24 HOURS AT/ABOVE 90% LOAD) I
= PRE-RUN MEASUREMENT OF GAP BETWEEN BUSHINGS. (NOMINALLY 0.035; FOUND 0.027-0,037) I
= LOAD LIMITER SETTING REDUCED TO AVOID INADVERTENT OVERLOADING
= 120 HOURS AT/ABOVE 90% LOAD; LICENSEE STATES THAT ANY LONGER RUN WOULD DELAY PLANT RESTART.
= EVERY 12 HOURS, INCREASE TO 100% LOAD, STABILIZE; TAKE CRITICAL READINGS AND OIL SAMPLE.
= INCLUDES RE-RUN OF TECH. SPEC. SURVEILLANCE 24 HOUR POWER RUN.
= POST-RUN MEASUREMENT OF GAP BETWEEN BUSHINGS.
= IF RESULTS NOT COMPLETELY CONCLUSIVE, EXTEND RUN FOR ADDITIONAL 100 HOURS AT/ABOVE 90%,
= POWER RUN BEGAN MARCH 21, 1986, ENGINEERING JUSTIFICATION TO SUPPORT ROOT CAUSE DETERMINATION (IMPROPER LUBE OIL) AND TO RULE OUT OTHER POSSIBLE CAUSES (E.G. INADEQUATE BUSHING MATERIAL DUE TO INCREASED RATING ON ENGINE); INITIAL REPORT DUE IN 90 DAYS.
EXPANSION OF RELIABILITY IMPROVEMENT PROGRAM TO PROVIDE CONTINUING PERIODIC PHYSICAL MEASUREMENTS OF GAPS (EVERY 6 MONTHS) TO CONFIRM NO CONTINUING PROBLEM.
FOLLOW-UP 0
REGION II HAS LEAD RESPONSIBILITY.
0 NRR PROJECT MANAGER AND TECH. REVIEWERS CONTRIBUTING.
0 NRC TO REVIEW ACCEPTANCE CRITERIA AND RESULTS OF CONFIRMATORY POWER RUN PRIOR TO RESTART OF UNIT 2.
0 UPDATE PRESENTATION TO ACRS.
. GRAND GULF, UNIT 1 - EXCESSIVE LEAKAGE FROM ADS CONTROL AIR SYSTEM MARCH 19, 1986 (L. KINTNER, NRR)
PROBLEM:
LEAKAGE FROM ADS CONTROL AIR SYSTEM WAS GREATER THAN LEAKAGE SPECIFIED IN fSAR SIGNIFICANCE:
PLANT COULD NOT HAVE MET POST-ACCIDENT REQUIR-MENT (TMI ITEM II.K.3.28) OF TWO ACTUATIONS FOR EACH OF 5 SAFETY RELIEF VALVES AND HOLDING THEM OPEN FOR 5 DAYS DISCUSSION:
0 AIR COMPRESSOR REBUILT; THEN REALIZED PROBLEM WAS LEAKAGE
° CALCULATED SYSTEM LEAKAGE RATE 7-14 SCFM: FSAR/DESIGN IS l SCFH PER VALVE (10 VALVES/SYSTEM) OR 0.167 SCFM FOR SYSTEM 0
0 0
0 LICENSEE DECLARED ADS VALVES INOPERABLE AND ENTERED T.S.-LCO REQUIRING SHUTDOWN WITHIN 12 HOURS FOUND 3 AIR SYSTEM RELIEF VALVES WEEPING AND l VALVE OPEN; LEAKING VALVES WERE INSIDE DRYWELL AIR RELIEF VALVES REMOVED, REPAIRED, TESTED, AND REINSTALLED.
PLAN TO OPERATE AT LOWER AIR (CONTROL) SYSTEM PRESSURE TO GIVE GREATER MARGIN TO RELIEF VALVE SETPOINTS FOLLOWUP:
0 RESIDENT INSPECTOR WILL FOLLOWUP
OTHER EVENTS OF INTEREST FAILURE OF BYRON-JACKSON REACTOR COOLANT PUMP SHAFTS, UPDATE MARCH 16, 1986 (M, CARUSO, NRR)
SIGNIFICANCE 0
INCREASED LIKELIHOOD FOR REACTOR COOLANT PUMP <RCP) SHAFT FAILURE IN PLANTS CURRENTLY OPERATING 0
0 IF COMPLICATIONS SHOULD OCCUR (E.G. DELAYED REACTOR TRIP),
FUEL DAMAGE MIGHT OCCUR.
GENERIC APPLICABILITY CIRCUMSTANCES 0
RCP SHAFT FAILURE AND CRACKS IN OTHER RCP SHAFTS AT CRYSTAL RIVER (l/l/86) 0 CRACK INDICATIONS IN SIMILAR LOCATION IDENTIFIED WITH UT IN THREE RCP SHAFTS AT DAVIS-BESSE (3/19/86)
SOME 0
AN0-1 AND MAINE YANKEE RCPs NEARLY IDENTICAL TO THOSE USED AT CRYSTAL RIVER AND DAVIS-BESSE.
0 AN0-1 AND MAINE YANKEE CURRENTLY OPERATING.
FOLLOW-UP 0
IE INFORMATION NOTICE (86-19) ISSUED.
0 DISCUSSIONS HELD WITH AN0-1, MAINE YANKEE, COMBUSTION ENGINEERING<RRG)4 AND BYRON-JACKSON TO DETERMINE INDUSTRY PLANS AND SCOPE OF PROBLEM.
0 0
NRR STAFF-WILL PROPOSE LETTERS BE SENT TO AN0-1 AND MAINE YANKEE REQUESTING JUSTIFICATION FOR CONTINUED OPERATION, NRR STAFF WILL CONTINUE TECHNICAL REVIEW TO DETERMINE ROOT CAUSE OF CRACKS AND APPLICABILITY OF PROBLEM TO CE AND BWR PLANTS.
COOPER - INADEQUATE CONSIDERATION OF OPERABILITY REQUIREMENTS MARCH 18, 1986 CR. BECKER, NRR)
PROBLEM:
PLANT OPERATED FOR 3 HRS. AND 10 MINS. WITH ONLY ONE OF FOUR REACTOR BUILDING CLOSED COOLING WATER PUMPS OPERABLE WITH ONSITE EMERGENCY POWER SIGNIFICANCE:
PLANT PERSONNEL DID NOT GIVE ADEQUATE CONSIDERATION TO THE EFFECT OF TAKING EQUIPMENT OUT OF SERVICE WHILE HAVING AN INOPERABLE EMERGENCY POWER SOURCE IN THE OTHER TRAIN DISCUSSION:
0 RBCCWS SERVES RHR PUMP BEARING COOLERS AND ECCS COMPARTMENT COOLING COILS AND NON-ESSENTIAL LOADS; PLANT HAS FOUR PUMPS CTWO PER DIVISION)
ONE PUMP CAN SATISFY EMERGENCY SHUTDOWN REQUIREMENTS 0
0 0
0 PUMPS IN ONE LOOP <DIVISION) WERE INOPERABLE BECAUSE THE ASSOCIATED DIESEL WAS INOPERABLE.
CTHE EDG WAS DISCONNECTED FROM ITS SWITCHGEAR TO PERMIT INSPECTIONS RELATED TO FUTURE MODIFICATIONS.)
POWER FROM MAIN GEN. AND OFFSITE SOURCES WAS AVAILABLE TO THE PUMPS.
PUMPS IN OTHER DIVISION WERE TAKEN OUT OF SERVICE, ONE AT A TIME, TO REPLACE VENT PLUGS WITH VENT VALVES LCO REQUIRES ONE PUMP IN EACH LOOP TO BE OPERABLE; LCO NOT VIOLATED RIVER WATER BACKUP TO RBCCW SYSTEM AVAILABLE FOLLOW-UP:
0 INSPECTOR IS LOOKING FOR POSSIBLE PROCEDURAL VIOLATION
REACTOR SCRAM
SUMMARY
WEEK ENDING 03/23/86 I. PLANT SPECIFIC Dt'::iTA DATE SITE UNIT F'Oli.JEF: RPS CAUSE COMPLI-YTD CATIONS TOTf:.)L 03/17/86 WNP 2
1 A PERSONNEL NO 2
03/18/86 PEACH BOTTOM 3
0 M PERSONNEL NO 03/20/86 MILLSTONE
~
10 A PERSONNEL NO 6
03/22/86 ROBINSON 13 A PERSONNEL NO 5
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAM Cf~USE Pmi.JER
- POl>JER >15'%.
EQUIP. RELATED
>15/.
PERS. RELATEDC7)
>15'%.
OTHER
>15/.
- Subtotal **
- POWER < 15'%.
EQUIP. RELATED*
<15/.
PERS. RELATED
<15/.
OTHER
<15/.
- Subtotal **
- Total ***
TYPE MANUAL SCRAMS AUTOMATIC SCRAMS SCRAMS FOR WEEK ENDING 03/23/86 NUMBER NUMBER OF NORMALIZEDC6)
SCRAMS(5)
TO 1985 0
0.0 (l
0.0 (l
0.0 (l
- 0. (l (l
- 0. (l 4
4.0 0
- o. (I 4
4.0 4
- 1. 0
~*
- 3. C) 1985 li.JEEKLY AVERAGE (3) (lj.)
- 5. 4.
- 2. (l
- o. 6
- 8. (l
- 1. 3 I). 9 0.2 2.4 10.4 1985 WEEKLY AVERAGE
- 1. 0 9.4
( 68/.)
( 25/.)
( 71.)
(54'%.)
( 38/.)
( 8/.)
NOTES
- 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
- 2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CA~.SE OF SCRAM
- 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 & DIVIDING BY.
52 WEEKS/YEAR
- 4.
IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC &
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.
- 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 DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS
- 8.
uoTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES <LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
.ENCLOSURE 3
--'-Page-No-. -1 03/25/86 OPER~TING REACTORS EVENTS MEETING FOLLOHUP ITEMS AS OF MEETING 86-09 ON MARCH 24 ! 1986 IIN ASCENDING MEETING DATE. NSSS VENDOR! FACILITY ORDERI MEETING NUMBER/
MEETING DATE 85-13 08113/85 86-03 01/27/86 FACILITY NSSS VErJDOR/
EVENT DESCRIP.
TURKEY POINT 3 w I POST-TRIP LOSS OF AFW ARKANSAS 1 BW i DESIGN DEFICIENCY IN EMERSEtlCY FEEDWATER SYSTEM 86-03 TMI 1 01/27/86 BW I PARTIAL LOSS OF NNI RES PONS IBLE DIVISION/
INDIVIDUAL PSB /MILHOAN J
- i iE
/JORDAN E 86-03 MCGUIRE DHFS/ZIEMANN D 01/27/86 W I START-UP I
WITH DEGRADED HPSI SYSTEM 86-04 DRESDEN 3 NRR /BERNERO R 02/10/86 SE I FIRE IN I
DRYWELL EXPANSION GAP 86-06 W PLANTS IE
/JORDAN E 03/03/86 W I SHIBLE I
FAILURE CF NUCLEAR INSTRUMENTATION HHERLOCK.P-10 i TASK DESCRIPTION REVIEW ADEQUACY OF GOVERNOR DESI6N ON TURBINE DRIVEN AFW PUMPS IDENTIFY WHAT IS ACTUAL DESIGN IN B&W PLANTS CONSIDER SUPPLEMENTAL IE NOTICE ON RECENT TRIP BREAKER PROBLEMS REVIEW NOVEMBER !, 1985 Mc6UIRE EVENT AND DETERMINE IF FAILURE TO REPAIR VALVE MOTOR OPERATOR PRIOR TO START-UP WAS IN VIOLATION OF TECH SPECS REQUIREMENT DISCUSS WITH BWRS OWNERS SROUP THE PROBABILITY OF POLYURETHANE l6NITIN6 DURING OPERATION AND APPENDIX R COMPLIANCE ISSUE REVIEW REPORTABILITY OF ITEMS SUCH AS SINGLE FAILURE OF P-10 HHERLOCK SCHEDULE COMPLET.
DATE(Si 03/31186 01105/86 10/13/85 03/31/86 I I I I 03/31/86 I I I I 04130/86 I
I I
I I 03/31186 I I I I 03/31/86 I I
! I CLOSED DATE BY DOCUMENT.
MEETING! ETC.
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COMMENTS