ML20137L103
| ML20137L103 | |
| Person / Time | |
|---|---|
| Issue date: | 08/02/1985 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8509120333 | |
| Download: ML20137L103 (28) | |
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AUG 2 1985 MEMORANDUM FOR:
Hugh L. Thompson, Jr., Director Division of Licensing FROM:
Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL
SUBJECT:
SUMMARY
' 0F'THEc 0P ERAT ING - REACTO RS' EVENTS MEETING 20N JULY 23',[1985Y MEETING"85212 g
On July 23, 1985, an Operating Reactor Events' meeting (85-11) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 1, 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.
Note that we have revised Enclosure 3 to facilitate computerized tracking and provide additional details regarding responsibilities and status. Each assignee should review Erclosure 3 with regard to their respective responsibilities and advise ORAB if the target completion date cannot be met.
If an assignee has any questions, please contact D. Tarnoff, x29526.
Dennis M. C'rutchfield, Assistant Director for Safety Assessment DL
Enclosures:
DISTRIBUTION As Stated Central Files NRC PDR ORAB Rdg cc w/ encl:
ORAB Members See next page
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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-11)
JULY 23, 1985 H. Deiton, NRR J. Stolz, NRR/DL/0RAB#4 M. Caruso, NRR D. Neighbors, NRR/DL/0RB#1 J. Jackson, NRR/DE/EQB G. Knighton, NRR/DL/LB#3 B. Jones, IE/DEPER/EAB H. Rood, NRC/DL/LB#3 F. Cherny, MEB/DE/NRR J. Lyons, NRR/DL W.Swenson,ORAB/DLINRR R. Bernero, NRR/DSI H. Nicolaras, NRR/DL/0RBf4 T. M. Novak, NRR/DL K. Mitchell, NRR/DL/0RAB/0RB#5 D. Beckham, NRR/DHFS J. Stone, IE/VPB R. Wessman, NRR/DL G. Bagchi, NRR/DE/EQB T. Speis, NRR/ DST J. Wilson, LBf3/DL/NRR F. Schroeder, NRR/ DST T. Alexion, LBf1/DL/NRR W. Minners, NRR/ DST L. N. 01shan, LB#1/DL/NRR S. Varga, DL P. O'Connor, LB#1/DL/NRR D. Crutchfield, DL W. J. Collins, IE/DEPER J. P. Knight, NRR/DE N. P. Kadambi, NRR/DL/LB#3 G. Lanik, IE/EAB D. Humenansky, OCM/COMM ZECH S. Schwartz, IE/DEPER T. Rotella, NRR/DL/0RB#5 H. Thompson, NRR/DL B. Sheron, NRR/DSI/RSB P. Morriette, NRR/DL B. Bosnak, NRR/DE D. Tarnoff, NRR/DL A. W. Dromerick, IE/DEPER/EGCB K. Seyfrit, AEOD/ROAB E. Weiss, IE/DEPER/EAB D. Zukor, AEOD/ROAB N. Lauben, NRR/DSI/RSB E. J. Brown, AEOD/R0AB r
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OPERATING REACTORS EVENTS BRIEFING (85-12)
JULY 23, 1985 INDIAN POINT UNIT 3 -
STEAM GENERATOR WELD INDICATIONS SEABROOK MAIN STEAM SAFETY VALVE TEST FAILURE OCONEE UNIT 2 EXTENDED BLOW DOWN FROM MAIN STEAM SAFETY VALVES WATERFORD UNIT 3 PLANT TRIPS JULY 4-7, 1985 WATERFORD/WOLFCREEK -
STARTUP EXPERIENCE COMPARISON, CALLAWAY/ CATAWBA / BYRON COMBUSTION ENGINEERING LOCA ANALYSIS ERROR i
M0JAVE GENERATING REHEAT LINE FAILURE STATION j
PALUEL UNITS 1, 2 IN-CORE INSTRUMENTATION TUBE VIBRATION
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PROBLEMS
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OTHER EVENTS OF INTEREST
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MILLSTONE UNIT 2 -
PRESSURIZER SPRAY VALVE FAILURES LASALLE UNIT 1 RHR FLOW SWITCHES IMPROPERLY INSTALLED FERMI UNIT 2 INADVERTENT CRITICALITY TURKEY POINT UNIT 3 -
REACTOR TRIP AND AFW VALVE FAILURE
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INDIAN POINT 3 - SG WELD INDICATIONS JUNE 27, 1985 (D, NEIGHBORS, NRR)
PLANT IN REFUELING STATUS T.S. REQUIRES INSPECTIONS OF SG TRANSITION ZONE UPPER GIRTH WELDS INDICATIONS FOUND BY UT:
SG 31
-I SG 32 - 2
'SG 33 - 0 SG 34 - 23 SG-34 HAD WELD REPAIR OF LEAK FOUND IN 1983 MT ON SG-34 SHOWED CLEAN ON 16 0F 23 INDICATIONS REMAINING 7 WELD INDICATIONS ON 34, AND 3 ON 31 AND 32 WERE FOUND TO BE CODE ACCEPTABLE BY VIRTUE OF SIZE OR BY FRACTURE MECHANICS ANALYSIS LICENSEE STILL EVALUATING NRR HAS LEAD (SINCE 7/15/85) 1 NRR & IE DEVELOPING GENERIC CORRESPONDENCE
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FIGURE 2 3-1 SERIES 51 STEAM GDERATOR i
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SEABROOK - CROSBY MAIN STEAM SAFETY VALVE FLOW DEFICIENCY - DECEMBER 1984 (G, HAMMER, NRR)
. PROBLEM - FULL FLOW TEST RESULTS INDICATE SPRING-ACTUATED MAIN STEAM SAFETY VALVES MAY NOT ACHIEVE RATED FLOW
- CAPACITY, SAFETY SIGNIFICANCE - POSSIBLE INADEQUATE OVERPRESSURE PROTECTION OF SECONDARY SYSTEM IN PWRs USING THESE VALVE!
WYLE LAB TEST RESULTS: INADEQUATE LIFT OF VALVE DISK (ABOUT 50%) WITH THE VENDOR (CROSBY) RECOMMENDED RING
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SETTING ADJUSTMENTS, TESTS WERE CONDUCTED TO DETERMINE ADEQUACY OF DISCHARGE PIPING, CORRECTIVE ACTION - RINGS READJUSTED, OBTAINED FULL LIFT ON SEABROOK VALVES ii r
GENERIC IMPLICATION - SEABROOK VALVES AND DISCHARGE PIPING SIMILAR TO OTHER PWRs.
FULL FLOW TESTS NOT NORMALLY RUN TO ADJUST RINGS.
1:'
NRC FOLLOWUP ACTION:
(1) DEVELOPING IE INFORMATION NOTICE (2) STAFF MAY PURSUE AS A GENERIC ISSUE i
(3) DISCUSSIONS WITH CROSBY BY REGION 1 AND NRR REGARDING ADEQUACY OF VENDOR GUIDANCE AND SRV RING SETTINGS, l
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'f-Page No. 4 Report No. 47447-0 2r I.
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VENT STACK DISCHARGE (P, T }
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TEMPERATURE & PRESSURE l
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TEMPERATURE & PRESSURE (P,T )
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INLET STEAM TEMPERATURE & PRESSURE (P), T )
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FIGURE 1.
INSTRUMENTATION LOCATIONS (16,18. AND 20-INCH VENT STACKS) 1
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OCONEE 2 - EXTENDED BLOWDOWN FROM MAIN STEAM SAFETY VALVES JULY 11, 1985 (H, NICOLARAS, NRR)
OCONEE UNIT 2 REACTOR TRIP FROM 94% POWER CAUSED BY PERSONNEL ERROR TWO MAIN STEAM SAFETY VALVES DID NOT RESEAT AT SETPOINT -
EXTENDED BLOWDOWN - TO ABOUT 990 PSI TO RESEAT VALVES, OPERATORS REDUCED STEAM PRESSURE THROUGH TURBINE BYPASS VALVES.
FAILURE OF CROSBY MAIN STEAM SAFETY VALVES TO PROPERLY RESEAT HAS ALSO OCCURRED REPEATEDLY AT OCONEE UNIT 1 IMPROPER RING SETTING IS A LIKELY CAUSE OF EXCESS BLOWDOWN, BUT NOT CONFIRMED, DUKE POWER COMMITTED CORRECTIVE ACTIONS TO REGION II
SUMMARY
OF PLANTS REPORTING SIMILAR BLOWDOWN PROBLEM l
PLANT KNOWN # OF EVENTS OCONEE 1, 2, 3 31 TROJAN 1
SALEM 1
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CAUSE: UNKNOWN POSTULATED PROBLEM WIT 11 RING SETTINGS CORRECTIVE ACTIONS: READJUST, RESET SETPOINT, VALVE DISASS&BLY 4 'WJT T 16) VALVES REWORED DURING EAG RERELING LICENSEE PURSUING Ell 10DS FOR GECKING BLOWD0hN SETTINGS IPPLICATIONS: RCS OVERCD0 LING CHALLENGE TO ADDITIONAL SYSTEMS POTENTIAL PRECURSOR TO STUCK OPEN VALVE OR FULL LIFT CAPACITY 4
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O WATERFORD 3 - PLANT TRIPS JULY 4-7, 1985 (J
WILSON, NRR)
WATERFORD 3 EXPERIENCED FOUR REACTOR TRIPS IN LESS THAN THREE DAYS DURING A PORTION OF THIS TIME, THE EFW TURBINE-DRIVEN PUMP WAS UNAVAILABLE DUE TO BEING INADVERTENTLY TRIPPED JULY 4 AT. 0950 !!0URS - 100% PWR - LOW SG LEVEL-HIGH VIBRATION'ON "A" MAIN FEEDWATER PUMP JULY 4 AT 2217 HOURS - 6% PWR - CPC AUXILIARY TRIP ON AXIAL SHAPE INDEX - XE OSCILLATIONS JULY 5 AT'2219 HOURS - 60% PWR - HIGH SG LEVEL DUE TO OVERFEEDI'SSGWHILEINMANUALCONTROLWITHONEMAIN N
FEEDWATER PUMP RUNNING
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s JULY 6 AT 915 HOURS - 70% PWR - EFW PUMP TERRY TURBINE
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OVERSPEED LATCH WAS FOUND TO BE TRIPPED JULY 7 AT 0121 HOURS - 90% PWR - LOW SG LEVEL - LOSS OF MAIN FEEDWATER PUMPS ON LOW SUCTION WHILE AN OPERATOR WAS AT ING TO BACKWASH A CONDENSATE POLISHING SYSTEM FILTER LPal CORRECTIVE ACTIONS:
REMOVING TRIP ON MAIN FEEDWATER PUMP VIBRATION--ALARM ONLY i
REVISING OPERATING PROCEDURES TRAINING, NIGHT ORDERS s
REGION IV-AND IE MONITORING STARTUP ACTIVITIES i_
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1 WATERFORD - 3, WOLF CREEK, CALLAWAY, CATAWBA AND BYRON -
STARTUP EXPERIENCE COMPARIS0N (W. J0NES, IE)
FACILITY FULL POWER LICENSE DATE WATERFORD - 3 (03-16-85)
WOLF CREEK (06-04-85)
CALLAWAY.
(10-18-84)
CATAWBA (01-17-85)
BYRON (02-14-85)
BASED ONLY ON 50.72 NOTIFICATIONS-- SIGNIFICANT EVENTS ONLY (I.E. NOT CONTROL ROOM ISOLATIONS ETC)
FOR 4 MONTHS FOLLOWING FULL POWER LICENSE (ADJUSTED FOR SIGNIFICANT SHUTDOWNS)
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SUMMARY
t MONTH IST 2ND 3RD 4TH WATERFORD 14 2
2 9
WOLF CREEK 9-CALLAWAY 11 2
3 1
BYRON 7
3 2
3 CATAWBA 5
0 1
5' MONTHLY AVG W/0 WATERFORD 8 WOLF CREEK 7.6 1.6 2
3
- 1 MONTH SHUTDOWN NOT INCLUDED IN PERIOD 1
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REACTOR TRIP AND FEEDWATER C0WARIS0N DETAIL SIGNIFICANT REACTOR +
IfWOLVING P0 NTH EVENT REPORTS TRIPS LOFW WATERFORD 3 1
4 4
3 2
2 2
0 3
2 2
1 4
9 8
3 SUBTOTAL 17 16 7
W0lf CEEK 1
9 5
8 CALLAWAY 1
11 6
8 2
2 2
0 3
3 3
2 4
1 1
0 17 12 10 CATAWBA 1
5 3
1 2
-0 0
0 3
1 1
1 4
. J' 2
1 11 6
3 BYRON 1
7 6
2 2
3 3
0 3
2 1
1 4
1 1
0 15 -
13 3
YAY REFLECT RETURN TO POWER AFTER SHUTDOWN
+ BASED ON AE0D & NRR STUDY FOR 1983/84, A'ERAGE NLPBER OF TRIPS FOR 4 MONTH PERIOD WAS 2.1, FOR ALL PWR's, 1
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PERSONNEL ERROR 8 E0lliffENT PROBLEMS COIPARISON DETAll SIGNIFICANT PERS EDP M) NTH EVENTS ERROR PROB OTER WATERFORD 3 1
4 3
1 0
2 2
1 1
0 3
2 1
1 0
4 9
2 6
1 17 7
9 1
WOLF CREEK 1
2 1
5 1
9 3
5 1
CALLAWAY 1
11 2
7 2
2 2
0 1
1 3
3 0
3 0
4 1
0 1
0 17 -
2 12 3
CATAWBA 1
5 3
1 1
2 0
0 0
0 3
1 1
0 0
4 E'
2 1
2 11 6
2 3
l BYRON 1
7 2
4 1
2 3
2 0
1 3
2 0
1 1
4 3
0 3
0 15 4
8 3
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CE LOCA ANALYSIS ERROR JULY 2, 1985 (H. ROOD, NRR)
NON-CONSERVATIVE ERROR FOUND IN CE LARGE-BREAK LOCA MODEL CENTER PEAK AXIAL POWER SHAPE YIELDS 34*F HIGHER PEAK CLAD TEMPERATURE (PCT) THAN PREVIOUSLY ASSUMED TOP-PEAKED SHAPE, FOR THREE CE PLANTS THAT ARE ON IST CYCLE THIS WOULD YIELD
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A PCT IN EXCESS OF THE 2200*F LIMIT OF 10 CFR 50,46.
PLANTS ARE:
PALO VERDE I SAN ON0FRE 3 WATERFORD 3 BASED ON CE REANALYSIS, OTHER FACTORS IN LARGE-BREAK LOCA MODEL WILL REDUCE PCT TO BELOW 2200*F.
LETTERS FROM THESE 3 LICENSEES BEING SUBMITTED GIVING BASIS FOR CONTINUED OPERATION, OTHER CE LICENSEES BEYOND CYCLE 1 AND (EVEN WHEN OTHER FACTORS NOT INCLUDED) HIGHER PCT DOES NOT REACH 2200*F LIMIT,
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M0HAVE GENERATING STATION -' REHEAT LINE FAILURE JUNE 9, 1985 (R, B0SNAK, NRR)
FAILURE OCCURRED JUNE 9, 1985 WHEN A 30" REHEAT LINE SUDDENLY SPLIT LONGITUDINALLY r
FRACTURE WAS FISH MOUTH RUPTURE APPR0XIMATELY I
20' x 6' FIG 1A 8B SAFETY SIGNIFICANCE 4
1 FOSSIL PLANTS OF SIMILAR VINTAGE NUCLEAR PLANTS i
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REHEAT LINE - VITAL STATISTICS DESIGNED TO B31.1 CODE FOR STEAM CONDITIONS OF 1000*F AND 600 PSIG l
COMMENCED OPERATION 1971 CONSTRUCTION LATE 1960's FAILURE IN A HORIZONTAL SPOOL 30"-DIAMETER ROLLED AND i
WELDED OF A-378C PLATE (1 1/4 CR-1/2 M0) TO MEET A-155 i
WELDED PIPE COMPARIS0N WITH LWR PIPING l
t MATERIAL NOT USUALLY USED IN LWR UPPER TEMPERATURE NOT IN CREEP RUPTURE AND CREEP FATIGUE RANGE IN LWR
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FABRICATION CONTROLS INCLUDING NDE SUPERIOR IN LWR LEAK DETECTION REQUIREMENTS IN LWR
'I, INSERVICE INSPECTION IN LWR P
FAILURE ANALYSIS RESULTS EXPECTED FROM SCE BY EARLY AUGUST
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o PALUEL 1 8 2. IN-CORE INSTRUMENTATION TUBE VIBRATION PROBLEMS MARCH 29, 19R5 (P. MORIETTE, NRR)
INITIAL EVENT: MARCH 29, 1985, PALUEL 1 IN COLD SHUTDOWN, LEAK DETECTED ON ONE THIMBLE TUBE, WHILE LEAK TESTING IN-CORE INSTRUMENTATION SYSTEM, SUBSEQUENT FINDINGS:
APRIL 5:
MECHANICAL WEAR (WITHOUT LEAK) ON 4 OTHER THIMBLES.
APRIL 16: A PROBE CANNOT BE COMPLETELY INSERTED IN ONE THIMBLE (PALUEL 1).
MAY-JUNE: 2 LEAKS ON PALUEL 2, ANOTHER LEAK ON PALUEL 1 SAFETY SIGNIFICANCE: REACTOR COOLANT LEAKS, OR: NO FLUX i
MAPS.
POSSIBILITY OF MIGRANT OBJECTS.
MAJOR POINTS:
DEFECTS (OR LEAKS) LOCATED AT DISCONTINUITY IN GUIDING STRUCTURE CAUSE THOUGHT TO BE HYDRAULIC j
EXCITATION DUE TO TURBULENCE IN THE l
CORE SUPPORT PLATE - BOTTOM 0F FUEL ASSEMBLY REGION, DIFFERENCES (FROM 900MWE SERIES) IN LOWER l
INTERNALS DESIGN AND MEASURED FLOW PARAMETERS SUPPORT THIS HYPOTHESIS, LOWER INTERNALS W DESIGN, CORE INSTRU-MENTATION SYSTEM (0UTSIDE VESSEL)
FRAMATOME DESIGN, GENERIC IMPLICATIONS:
ALL 1300MWE-SERIES REACTORS AFFECTED IN FRANCE L
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~2-LICENSEE CORRECTIVE ACTIONS:
SHORT TERM:
JUSTIFY OPERATION 1.'!THOUT IN-CORE INSTRUMENT 4 TION FOR 1 1/2 MONTH, LONG TERM:
MODIFY THIMBLE GUIDING PIECES ON TOP OF CORE SUPPORT PLATE FOR BETTER PROTECTION, REDUCE TURBULENT FLOW AROUND THIMBLES, ONLY AFFECTED US FACILITY:
SOUTH TEXAS PROJECT 1 & 2 1
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MILLSTONE UNIT 2 - FAILURE OF PRESSURIZER SPRAY VALVES TO SHUT JULY 15, 1985 (D. 0SBORNE, NRR)
RETURNED TO 100% POWER ON 7/11/85 AFTER 135 DAY REFUELING OUTAGE REACTOR TRIPPED ON JULY 15 PRESSURESETPOINT(2130 PSI)1985ONTHERMALMARGIN/ LOW PRESSURE DROP HALTED AT 1725 PSI TRIP ATTRIBUTED TO FAILURE OF BOTH PRESSURIZER SPRAY VALVES TO SHUT FISHER CONTROL AIR OPERATED 3 INCH ANGLE VALVES ONE MISADJUSTED - (WOULD NOT FULLY CLOSE)
OTHER HAS ME'HANICAL BINDING (PRELIMINARY)
C DURING INVESTIGATION DISCOVERED SPRAY VALVES WIRED TO WRONG CONTROLLER, AS SPECIFIED IN THE OUTAGE DESIGN CHANGE (NOT CAUSE OF FAILURE)
LICENSEE HAS REVIEWED OTHER REFUELING OUTAGE DESIGN CHANGES AND TESTING CORRECTIVE ACTIONS: ONE VALVE WAS READJUSTED TO FULLY CLOSE OTHER VALVE WAS REPACKED AND REBUILT REGION REVIEWED PRIOR TO STARTUP PLANT RESTARTED ON JULY 20, 1985 I
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I FERMI 2 - INADVERTENT CRITICALITY JULY 2, 1985 (D. LYNCH, NRR) l l
T INADVERTENT CRITICALITY JULY 2,1985, DE f
PROBLEM TO OPERATOR ERROR i
SAFETY SIGNIFICANCE -
PLANT WAS IN ANALYZED CONDITION AND NEVER EXCEEDED SOURCE RANGE.
REACTOR OPERATOR PULLED ROD BANK (ABOUT 8 To 10 RODS) FULL OUT (NOTOi 48) RATER THAN NOTCH 4, AS SPECIFIED, JULY 2 INADVERTENT CRITICALITY DECLARED BY OPERATOR AND RODS EINSERTED SHIFT SUPERVISOR REVIEWEDOPERATORAdTIONSANDDETERMINEDTHAT INADVERTFNT CRITICALITY HAD NOT OCCURRED, NORMAL STARTUP C0WlfiED, i
POSSIBLE LACK OF EFFECTIVE ASSISTANCE OR OBSERVATION BY SR0 SHIFT TECHNICAL ADVISOR WAS IN TRAINING f
SUBSEQUENT SE0VEN E OF EVENTS:
JULY 7 LICENSEE TECHNICAL STAFF C0 WIRED INADVERTENT CRITICALITY JULY 8 INADVERTENT CRITICALITY ECOWIffED INDEPENDENTLY BY LICENSEE JULY 10 CO MISSION BRIEFING ON FULL POWER LICENSE JULY 15 EGION III NOTIFIED BY LICENSEE (1:30 PM CDT) l JULY 15 FULL POWER LICENSE ISSUED BY NRC (3:15 PM EDT)
EGION III ISSUED CONFIRMATORY ACTION LETTER LIMITING FERMI 2 TO 5 PERCENT POWER EWORINNT CONFERENCE SCHEDULED FOR JULY 23 INVESTIGATION CONTINUING 1
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LA SALLE UNIT 1 - RHP FLOW SWITCHES IWROPERLY INSTALLED JULY 17, 1985 (R, CARUS 0, NRR)
PROBLEM FOUR RHR FLOW ISOLATION SWITCHES FOUND TO E PIPED BACKWARDS SINCE MARCH 1%5 EQ UPGRADE, AS A RESULT OF BREAKDOWN IN MANAGEE NT CONTROL AND QA EVENT IS A REPEAT OF PROBLEM WITH UNIT 2 ECCS AND RHR SWITCHES IDENTIFIED ON 6/10/85 SAFETY SIGNIFICANT - RHR S4' 1TCHES SERVE DIVERSE AND REDUNDANT FUNCTION TO ISOLATE RHR IN CASE OF BREAK - MINOR SIGNIFICANCE.
LICENSEE WAITED FROM JUNE 10 TO JULY 17 TO TEST INSTALLATI0t', SINCE PLANT SHUTDOWN FOR UNREl.AiTD ACTIVITY, i
CORRECTIVE ACTION - EGION 111 REVIEWING Ll&NSEE PLANS TO EVIEW P0DIFICATION CONTROL SYSTEM, DRAWING CHANGES TO BE E-REVIEWED, BOTH UNITS TO REPAIN SHUTDOWN UNTil R./IEW C0&LETE.
ESCALATED ENFORCEENT ACTION BEING CONSIDERED, 1
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TURKEY POINT 3 - REACTOR TRIP AND AFW VALVE FAILURE JULY 21, 1985 AND JULY 22, 1985 (T
ROTELLA, NRR)
LICENSEE: FLORIDA POWER & LIGHT iCILITY: TURKEY POINT UNIT - 3 t
VENDOR:
WESTINGHOUSE INITIAL CONDITIONS: 100% POWER; STEADY STATE CURRENT CONDITIONS: PLANT IN COLD SHUTDOWN EVENT SEQUENCE:
EVENT hrs DATE TIME U-.
7721/85 23T41 LIGHTNING STRIKE IN OR NEAR t
PLANT REACTOR TRIP FROM 100% POWER FIRST-0VT ANNUNCIATOR: TURBINE TRIP (CAUSE UNVER INVESTIGATION)
+1 7/22/85 00:40 LO-LO LVL S/G #3B DUE MFW BYPASS VALVE FAILURE TO OPEN UPON OPERATOR INITIATION (CAUSE UNDER INVESTLGATION)
AFW PUMPS AU"O STARTED PROPERLY HOWEVER THE A&C PUMPS TRIPPED ON MECHANICAL OVERSPEED (CAUSE UNDER INVESTIGATION)
+3.5 7/22/85 ' 04:05 MFW PUMP TRIP DUE TO HI LVL S/G #3C (CAUSE WAS DUE TO LEAKING MFW BYPASS REGULATING VALVE)
ALL 3 AFW PUMPS SUCCESS-FULLY STARTED AND RAN
+5.5 7/22/85 06:04 HgTS/Dg0 COLDS /DP ANT BE IN C00LDOWN AFW FLOW CONTROL VALVE FAILED TO CLOSE (AFW r
V-2833TOS/G#3C)CAUSE r
UNDER INVESTIGATION) i
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UNPLANNED REACTOR TRIPS
- AVERAGE WEEKLY TRIP FREQUENCY FOR PAST 71 WEEKS IS APPR0X'"ATELY 10 TRIPS / WEEK, WHICH IS NEAR AVERAGE BREAKDOWN OF REPORTED CAUSES 1
AUTOMATIC
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EQUIPMENT FAILURES 52%
PERSONNEL ACTIVITIES 40%
MANUAL 8%
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- BASED ON 10 CFR 50.72 REPORTS FOR PLANTS WITH LICENSES FOR FULL POWER OPERATION
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Page ha., !
v Enclosura 3 v
07/29/85 OPERATINS REACTORS' EVENTS MEETINS FOLLONUP ITEMS AS OF MEEilNG 85-12 DN JULY 23,1985 (ORDERED BY ASCECING MEETING DATES, NSSS VD DORS, FACILITY)
EETI~3 FACILITY RESPONSIBLE TASK DESCRIPT10N SCHEDULE CLOSED DATE COMMENTS NUMBER /
NSSS VE CCR/
DIVISION /
COMPLET. BY DOCUMENTI EETIN6 EVENT DESCRIP.
INDIVIDUAL DATEtS)
EITING,ETC.
DATE RANCHO SECO I DL /VISSIN6 SUMMARIZE R&W LIC. RESPONSES TO 08/30/85 OPEN
/ /
STAFF REVIEN OF 44/10/84 Bu / MAIN BEN
/
GUESTIDMS SUBSEQUENT TO RANCHO 07/30/85 R&W OWNERS GROUP NYDR36EN SECO LDSS OF NN! EVENT A C
/ /
SUBM! ITAL OF EIPLDSION -
PRESEhi AT FOLLOW-UP OR EVENTS 1/11/85 15 IN PARf!AL LOSS OF 3RIEFING PROGRESS (THIS NN!3/19/84 REACTIVATED-CRYS.RIV. 3)
SALEM 2 il /FISCHER, D.
DETERMINE IF VELAN (PORV) BLOCK 08/30/85 0 FEN
//
AE00 REPORT IN C'/07/84 W / STUCK OPER
/
VALVE 90ALIFIED TO CLOSE 07/30/85 PREPARATION N!LL RELIEF VALVE /
AEAINST 7/25/84 STEAM BLO C ONN
/ /
ADDRESS THAT ECCS ACTUATION T M SIENT AT SALEM 2. CHECK ISSUE.
~
JLLY 25,1994 ElRI TEST PROGRAM RESULTS.
CRYSTAL RIVER 3 ICS8/RDSA,F.
CONSIDEP EED FOR ADDIT 10NAL 09/30/85 DPD
/ /
ICS8 IS 01/43/85 lu / TEMP. LDSS
/
REQUIREMENTS ON ALARMS /
07/30/85 CONSIDER!N6 OCONEE OF NN! 12/28/84 AugUNCIATORS
/ /
I LOSS OF ANNUNCIA.
(4/25/84) IN ANAL.
OF REGUIREMENTS.
CATAWSA 2 il /JABBOUR, K.
FOLLOW UP BRIEFING AFTER EVAL.
09/30/85 OPD
/ /
PRELIM. REPORT 05/07/85 N / BOTH RHR
/
OF DVERPRESS. EFFECTS ON 08/01/85 REC'D. ADD'L INFD.
TRAINS VARIOUS SYSTEMS AND CORRECTIVE 08/07/85 REQUESTED FROM OVERPRESSURIZD ACTIONS.
LICENSEE.
4/19/85 RESOLUTION PENDINS REVIEW BY NRR &
R!l.
MILLSTONE 2 ORAL / MURPHY,E.
REVIEW $506 LETTER ON EDDY 10/01/85 OPEN
/ /
ORNL CONTRACTED TO 05/07/85 CE / DDY DE /CONRAD, H.
CURRENT TESilN6 ISSUE, IN VIEW 38/01/85 EVALUATE EFFECT OF CURRENT TEST OF OF MILLSTONE 2 FINDINGS.
08/07/85 COPPER DN EDDY STEAMS 3.
CURRENT TESTINS TULES,4/10/85 85-10 DAVIS BESSE i DST /SPEIS,T.
DETERMINE STATUS OF 08/30/85 DPEN
/ /
REMAININS 2 ISSUES 06/12185 fu / LOSS OF ALL DL /DEASA!!D, A.
IMPLEMENTA110N OF TM1 ITEMS, 06/19/85 STATUS OF (GENERIC & MPAs)
MAIN AC AUI.
SENERIC ISSUES, MPAs AT DAVIS
/ /
IMPLEENT. OF' INFWOGRESS.IIT FEEDWATER 6/9/85 DESSE THAT MAY BE RELATED TO TMI ISSUES REPORT UCER 6/9/85 EVENT.
~
CLOSED-N.
REVIEW THOMPSON TO H.
DENTON MEMO OF 6/20/85.
35-10 DAVIS DESSE 1 BSI/PARR,O.
RE-EIAMINE STAFF REVIEW OF 08/30/85 OPEN
/ /
!!T REPORT UCER 06/12/85 BW / LOSS OF ALL DL /DEAGA!!O,A. ACCEPTABILITY / D!?ERSITY OF 06/19/85 REVIEW MAIN AC AUI.
DAVIS BESSE AFu SYSTEM.
/ /
FEEDuATER6/9/95
n Pap No.. 2
()
O 07/29/85 DPERATINS REACTORS' EVENTS MEETING FOLLDNUP ITEMS AS OF EETING 85-12 DN JULY 23,1985 (ORDERED BY ASCECINS MEETING DATES, NSSS VENDORS, FACILITV)
EET!]
FAtlLITY RESPONSIBLE TASK DESCRIPT!DN SCHEDULE CLOSED M TE COMMENTS NUMBERI NSSS VEN00RI DIVISION /
COMPLET. BY DOCUMENTI MEETI3 EVENT DESCRIP.
INDIVIDUAL DATE(S)
KETING,ETC.
DATE B5-10 DAVIS RESSE 1 DL /DEASA!!D,A. PROVltE H. DENTON WITH 08/30/85 OPEN
//
ITENS 2 & 3 IN 06/12/85 BW / LOSS OF ALL
/
1)COMPARISCN BETWEEN H VIS 06/19/85 ITEM l-6/20/85 PROGRESS.
MIN MD AUI.
BESSE 1 AND TMI-l CF TMI ACTION
//
MEMD H.
FEEDWATER 6/9/85 PLAN IMPLEMENTAi!DN STATUS THOMPSON TO H.
- 3) STATUS OF STARTUP FN PUMP UP6RADE.
85-!!
LASALLE 2 IE /RAER, R.
CONSIDER ISSUANCE OF IE NOTICE. 08/30/85 DPEN
//
07/01/85 GE / EE
/ ~
//
MCDIFICATION
//
PROILEMSAND LCSS OF ALL ECCS JUNE 5-10, 1985 85-11 DYSTER CREEK 1 DST /MINNERS LEAD PRESSURE ISOLATION VALVE 08/30/85 OPEN
//
07/0./85 GE /
BE /CHERNY ASSI. TESTING REG"!REMENT TO DE
//
LICCNTROLLED A: DRESSED IN CR6R l'ilEFING.
/ /
LEAKAGEOF REACTOR CCOLANT DUTSIDE CONTAIP.EX1 6/12/95 85-11 DYSTER CREEK !
DHFS/B0CHER,H.
DETERMINE EFFICACY OF EPEI 08/30/85 OPEN
//
07/s1/B5 SE /
/
OPERATORACTIONANDEICESSIVE
//
IKONTROLLED RESPCNSE TIME.
//
LEAKAGE OF REACTOR C00LANT DUTSIDE CONTA!NMENT 6/12/85 85-!!
RANCH 3 SECC 1 DL /M!NER, S.
DETERMINE STATUS OF IEB 79-14.
08/30/85 OPEN
//
THE LICENSEE IS 07/01/85 BW / RCS HIGH
/
//
COMPLETIN6 THE POINT VENT LEAK,
/ /
INSFEti!DN
&I23/B5 B5-!!
RANCHO SECO 1 DL / MINER, S.
SCHEDULE CONFERENCE CALL WITH 08/15/85 OPEN
//
EVALUAi!DNIN 07/01/85 IN / STARTUP
/
RE010N AG LICENSEE PRIOR TO 07/12/85 PROGRESS PROBLEMS-JUNE RESTART TO DETERMIME PLANT
//
1985 READINESSFOROPERATIONS.
85-12 DCONEE 2 DL INICOLARIS, H SCHEDULE CONFERENCE CALL WITH 09/30/85 OPEN
/ /
07/23/B5 BW / EliENDED
/
LICENSEETODISCUSSCROSif
//
BLONDOWN FROM VALVE PERFORMANCE
//
Page No.
- 3
- 07/29/95 OPERATIN6 REACIORs' EVENTS MEETIN6 FDLLONUP ITEMS AS OF MEETIN6 85-12 DN JULY 23,1985 (DRDERED BY ASCENDING MEETING DATES, NSSS VENDORS, FACILlif)
KEi!N6 FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED MTE COMMENTS NUMBERI NSSSVENDCRI DIVIS!CN/
ConPLET. If DOCUMENT /
MEETING EVENT M SCRIP.
INDIVIDUAL DATEtS)
KETING,ETC.
MTE B5-12 SEABROOK DSI / MARSH ANALYlE SAFETV IMPLICATIONS OF 09/30/85 OPEN
//
07/23/85 W / CROSBY MAIN
/
VALVE FLON MFICIENCY
/ /
STEAM SAFETY
//
VALVE FLON KFICIENCY 12/84 85-12 SEABROOK K /CHEREY INVEST! SATE ADEDUACY OF TESTING 09/30/85 OPEN
//
07/23/85 W / CROSEY MAIN
/
AND VALIDITY OF EITRAP0LATING
/ /
STEAR SAFETT DATA FROM SMALL TO LARSE VALVES //
VALVEFLON KFICIENCY 12/04
^
85-12 HATCH 1 DRAS/CARUSD,M.
NILL DEVELOP TIA TO COORDINATE 07/30/85 CLOSED 07/23/85 05/30/85 BE / STUCK OPEN
/
IE NOTICE AND FURTHER
/ /
TIA IN SAFETT RELIEF INVESi!6ATIVE EFFORTS.
/ /
CONCURRENCE VALVE
(
,