ML20206L908
| ML20206L908 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Fermi, Ginna, Farley, San Onofre, 05000000 |
| Issue date: | 08/11/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608200399 | |
| Download: ML20206L908 (16) | |
Text
.
A08111986 L
MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation i
FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff i
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON AUGUST 4, 1986 - MEETING 86-27 On August 4,1986, an Operating Reactor Events meeting (86-27) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 28, 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 followup 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.
Af/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page
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DISTRIBUTION.
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J. Keppler, Reg. III D. Hood R. D. Martin, Reg. IV J. Stone 1'J. B. Martin, Reg. V B. J. Youngblood R
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. Ebneter, Reg. I E. Adensam Rx Walker, Reg. II C.\\Norelius, Reg. III j
E. '0ohnson. Reg. IV D. Kirsch, Reg. V I
H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak
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F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan i
E. Rossi R. Baer E. Weiss R. Hernan i
S. Showe S. Rubin P. Baranowsky i
I AUG 11286 f
ENCLOSURE 1 LIST OF ATTENDEE _S.
OPERATING REACTORS EVENTS BRIEFING (86-27)
AUGUST 4, 1986 4
NAME DIVISION NAME DIVISION a
G. Holahan NRR/0 RAS W. Swenson NRR/0 RAS D. Tarnoff NRR/0 RAS S. Black NRR/PPAS B. Clayton NRR/DPLA D. Persinko NRR/DHFT W. Regan NRR/PWR-B V. Benaroya NRR/PAF0 G. Murphy ORNL/NOAC A. Kininins-ORNL/NOAC S. Rubin AE0D
.G. Lapinsky NRR/PWR-A R. Woodruff IE/EAB G. Klingler IE/DI/0RPB j
J. Stone IE/DQAVT/VPB E. Reeves NRR/ PAD #2
]
W. Paulson NRR/PWR-B T. Novak NRR/PWR-A E. Rossi NRR/PWR-A D. Humenanski OCM/LZ F. Schroeder NRR/DPLB R. Baer IE/DEPER/EGCB l
T. Colburn
'NRR/ PAD #1 F. Rowsome NRR/DHFT S. Varga NRR/PWR-A J. Clifford NRR/TOSB E. Adensam NRR/ DBL D. Lynch NRR/ DBL i
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ENCLOSURE 2 4
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OPERATING REACTOR EVENTS BRIEFING 86-27 i
AUGUST 4, 1986 4
1 l
1 SAN ONOFRE 1 STEAM PRESSURE TRANSMITTER FAILURE i
4 l
FARLEY 1 DEGRADATION OF ECCS FERMI 2 INADVERTENT ECCS ACTUATION 4
i I
0THER EVENTS OF INTEREST i
MCGUIRE 2
-FAILED EMERGENCY DIESEL GENERATOR TURBOCHARGER i
I GINNA 1 RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE f
9 i
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SAN ON0FRE 1 - STEAM PRESSURE TRANSMITTER FAILURE JULY 30, 1986 (R. DVDLEY: NRR)
PROBLEM:
FAILURE OF PRESSURE TRANSMITTER FOR PRESSURE COMPENSATION OF STEAM FLOW SIGNALS SIGNIFICANCE:
SINGLE FAILURE CAUSED FEEDWATER REDUCTION AND DISABLED STEAM FLOW / FEED FLOW MISMATCH RX TRIP i
DISCUSSION:
7:35 P.M. (7/29) 76% POWER - RAPID DECREASE IN INDICATED STEAM FLOW 4
SIGNAL; CAUSED AUTO-REDUCTION OF FEEDWATER FLOW 4
5% SG LEVEL CAUSES AFW AUT0-INITIATION MANUAL FW CONTROL RESTORED SG LEVEL STEAM FLOW INDICATION RETURNED TO NORMAL j
FEEDWATER CONTROL RETURNED TO AUT0, POWER REDUCED (63%), OPERATOR i
ASSIGNED DURING TRANSIENT, STEAM FLOW THOUGHT TO HAVE EXCEEDED FEED FLOW BY j
25% WITH NO REACTOR TRIP j
1 P.M. (7/30) - STEAM FLOW SPIKED LOW; OPERATOR TOOK MANUAL
)
FEEDWATER CONTROL j
2 A.M. HR LC0 EXPIRED; T.S. REQUIRED RX SHUTDOWN BEGUN j
3:50 A.M. - (31% POWER) AMPLIFIER CARD REPLACED: TRIP FUNCTION RESTORED; POWER INCREASED LATER l
FOLLOW-UP:
VERIFY ACTUAL STEAM FLOW / FEED FLOW DURING TRANSIENT & RPS RESPONSE l
LICENSEE CONFIRMED THAT LOFW AND FWLB ANALYSES ASSUME l
STEAM FLOW /FEEDWATER FLOW MISMATCH TRIP f
DEDICATED OPERATOR STATIONED AT PANEL l
ANALYSES WERE RERUN WITH OTHER TRIP SIGNALS i
l RE-ANALYSIS RESULTS i
FEEDWATER LINE BREAK:
l TRIP ON VARIABLE LOW PRESSURE (14 SEC. vs 5 SEC.)
PRIMARY PRESSURE < 110%
i LOSS OF FEEDWATER:
TRIP ON PRESSURIZER HIGH LEVEL PRESSURIZER LEVEL TRIP CHANGED (70% --> 50%)
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FARLEY 1 - DEGRADATION OF ECCS AUGUST 1, 1986 (R
WOODRUFF, IE) i i
PROBLEM:
SILT IN SERVICE WATER SYSTEM CAUSED DEGRADATION OF TWO CHARGING PUMPS WHILE THIRD PUMP WAS IN0PERABLE j
SIGNIFICANCE:
l POTENTIAL LOSS OF ALL CHARGING PUMPS (CP)
ONLY OTHER ECCS PUMPS ARE RHR PUMPS i
CIRCUMSTANCES:
CP "A" WAS'00T OF SERVICE FOR MAINTENANCE AND EXPECTED TO BE IN0PERABLE FOR 2 OR 3 DAYS l
CP "B" WAS OPERATING AND WAS SECURED WHEN GEARB0X TEMPERATURE j
EXCEEDED 155'F
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VENDOR SUGGESTS OPERATING WITH CAUTION AB0VE 140*F AND.N0T OPERATING AB0VE 155'F CP "C" WAS OPERATING AT 148'F AND TEMPERATURE WAS INCREASING l
CAUSE - SILT IN LUBE OIL COOLERS j
CP "C" STABILIZED AT 145'F AFTER ADDITIONAL COOLING WAS PROVIDED j
CP "B" LUBE OIL COOLERS WERE FLUSHED TWICE AND PUMP WAS RETURNED j
TO SERVICE l
CP "C" WAS FLUSHED l
FOLLOWUP:
j REGION 11 AND IE ARE FOLLOWING-UP j
INCREASED PREVENTIVE MAINTENANCE FOR SILT REMOVAL FROM SERVICE j
WATER SYSTEM IS INDICATED i
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_ _,_ _ _ - - -.. _ _ _ __ ___- _ _ ~,_ -. _,
FERMI 2 - INADVERTENT ECCS ACTUATION JULY 15, 1986 (NRR/ LYNCH)-
PROBLEM:
INVALID LOW LEVEL 1, 2, 3 ACTIVATION DURING REACTOR VESSEL HYDRO TEST SIGNIFICANCE:
INVALID ECCS ACTUATIONS DRY START OF DIESELS LACK 0F ATTENTION TO DETAIL DISCUSSION:
REACTOR VESSEL HYDR 0 IN PROGRESS (150*F, 20 PSI)
WATER LEVEL IN REACTOR VESSEL HEAD WITH SMALL BUBBLE "B" RCP OFF "B" SHUTDOWN COOLING ON OPERATORS SECURED "B" RHR PUMPS CAUSING FLOW REVERSAL IN "B" LOOP AND PRESSURE SPIKE ON REFERENCE LEG PRESSURE SPIKE IN REFERENCE LEG RESULTED IN FALSE LOW LEVEL SIGNALS AND ESF ACTUATIONS INCLUDING:
RPS SCRAM DIV. 1 - RHR (LPCI) AUT0 START DIV 1 8 2 - CORE SPRAY DIV, 2 - EDG (DIV 1 EDG IN MAINTENANCE)
BUBBLE IN REACTOR VESSEL HEAD ESCAPED THROUGH LEAKING FLANGE PRESSURE PERTURBATION CAUSED BY SYSTEM G0ING SOLID PRESSURE PEAKED AT 380 PSI - THE SHUT 0FF HEAD FOR THE LOW PRESSURE PUMPS FOLLOWUP:
PROCEDURES REVISED TO REQUIRE BOTH RCPs AND TO SECURE SHUTDOWN COOLING EARLIER
OTHER EVENTS OF INTEREST MCGUIRE 2 - FAILED EMERGENCY DIESEL GENERATOR TURB0 CHARGER JULY 25, 1986 (J. STONE, IE)
PROBLEM TURB0 CHARGER COMPRESSOR SIDE FAILED CATASTROPHICALLY DURING ROUTINE TESTING SIGNIFICANCE FAILURE OF TURB0 CHARGERS AFFECTS AVAILABILITY OF EMERGENCY POWER I
MAY BE GENERIC TO OTHER DIESELS USING BROWN B0 VERI TURB0 CHARGERS CIRCUMSTANCES DIESEL OPERATING AT 4000KW l
LOUD NOISE HEARD, LOAD DROPPED TO 1000KW, DIESEL MANUALLY SHUTDOWN COMPRESSOR SIDE BLADES ALL DESTROYED '
BEARINGS AND SHAFT UNDAMAGED 4
DISCUSSION CAUSE STILL UNDER INVESTIGATION BY LICENSEE APPEARS 3 BLADES BROKE - FATIGUE BROWN B0 VERI ASSISTING NOT AWARE OF ANY SIMILAR FAILURES DIESEL HAD 5000 HOURS ON IT REPLACED TURBOCHARGER BROWN B0 VERI TURB0 CHARGER USED ON OTHER DIESELS FOLLOWUP NEED FOR FURTHER ACTION WILL BE DECIDED ONCE CAUSE OF FAILURE IS DETERMINED j
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GINNA - RUPTURE OF 6" DRAIN LINE ELB0W IN TURBINE CYCLE JULY 29, 1986 - (M. FAIRTILE, NRR)
PROBLEM:
WASTAGE FAILURE IN MILD CARBON STEEL ELB0W IN DRAIN LINE BETWEEN 2A MOISTURE SEPARATOR REHEATER AND SA FEEDWATER HEATER SIGNIFICANCE:
POTENTIAL PIPE RUPTURES DUE TO EROSION MAY OCCUR NO PERSONNEL INJURY NO DAMAGE TO SAFETY RELATED EQUIPMENT NO RELEASE OF ACTIVITY DISCUSSION:
OPERATORS HEARD SOUND OF RUPTURE AND MANUALLY TRIPPED REACTOR AND TURBINE OPERATORS MANUALLY CLOSED MAIN STEAM ISOLATION VALVES MAIN FEEDWATER CONTINUED TO FLOW TO SGs UNTIL HI-HI SG SIGNAL CAUSED FEEDWATER REGULATOR VALVE TO CLOSE HIGH FLOW IN SGs CAUSED PRIMARY SIDE COOLANT VOLUME SHRILXAGE AND DROP IN PRESSURIZER LEVEL UNTIL FEEDWATER REGULATOR VALVE CLOSED (PREVAILED FOR ABOUT 11 SECONDS)
NORMAL CONTROLLED C00LDOWN THEN COMMENCED AND PLANT BROUGHT TO H0T SHUTDOWN FOLLOWUP:
RESIDENT INSPECTOR IS ON TOP 0F EVENT; RESIDENT, PROJECT MANAGER, AND F0B HAD CONFERENCE CALL LICENSEE DETERMINED WASTAGE IN MILD STEEL ELB0W CAUSED RUPTURE.
STUDY OF SIMILAR DRAIN SYSTEM ELB0WS AND UT OF SIMILAR ELB0WS UNDERWAY
REACTOR SCRAM
SUMMARY
WEEK ENDING 08/03/86 I.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15'/.
15%
07/28/86 PRAIRIE ISLAND 2
100 A PERSONNEL NO 3
0 3
07/29/86 GINNA i
100 A EQUIP /LINE BRK NO 1
0 1
07/30/86 HOPE CREEK 1
8A EQUIP /EHC PROB. NO O
7 7
07/30/06 GINNA 1
26 A UNKNOWN NO 2
0 2
08/01/86 FORT CALHOUN 1
86 M EQUIP / ELECT.
NO 2
0 2
08/01/86 COOK 1
25 A UNKNOWN NO 3
0 3
08/02/86 HATCH 1
55 A UNKNOWN NO 3
0 3
08/02/86 COOK 1
12 A UNKNOWN NO 3
1 4
100 A UNKNOWN NO 6
1 7
08/02/86 INDIAN POINT.
2 03/04/86 CATAWBA 2
49 M PERSONNEL / TEST NO 3
2 5
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 08/03/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE YTD (3) (4)
- POWER >15%
EQUIP. RELATED
>15%
2 4.5 5.4 (68%)
PERS. RELATED(6) >15%
2 2.1 2.0 (25%)
OTHER(7)
>15%
4 0.4 0.6 ( 7%)
- Subtotal **
8 7.0 8.0
- POWER <15%
EQUIP. RELATED
<15%
1 1.6 1.3 (54%)
PER.S. RELATED
<15%
0 1.0 0.9 (38%)
OTHER
<15%
1 0.2 0.2 ( 8%)
- Subtotal **
2 2.8 2.4
- Total ***
10 9.8 10.4 MANUAL VS AUTO SCRAMS
~
TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2
0.8 1.0 AUTOMATIC SCRAMS 8
8.9 9.4 m
NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D 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 CAUSE OF SCRAM.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF
^
UNPLANNEDREACTORTRIPSIN1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4.
IN 1985, THERE WERE AN. ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 100 OPERATING REACTORS 6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
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ENCLOSURE 3 Page No.
1 08/06/06 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETINS 86-27 DN AU6UST 4, 1986 (IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORDER)
MEETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS WUMBERI N555 VENDOR /
DIVISIDN/
COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
< DATE 86-10
- 0) STER CREEK NRR / HOUSTON W RESOLVE THE QUEST!DN OF THE 10/30/06 DPEN
/ /
FOLLOWUP ACTION TO 03/31/96 6E / LEVEL
/
ACCEPTABILITY OF BLIND SWITCHES
/ /
BE INCORPORATED IN SWITCH SETPOINT AND DELETION OF DAILY CHANNEL
/ /
REY!EW 0F JUNE DRIFT CHECK 1,1996$VENTAT LASSALLE B6-21 VERMONT YANKEE NRR /HOLAHAN 6.
DETERMINE STATUS AND 05/20/06 OPEN
/ /
06/23/86 6E / PROBLEMS
/
EFFECTIVENESS OF STAFF AND
/ /
WliH SCRAM LICENSEE ACil0N GN
/ /
SCtENDID VALVES POST-MAINTENANCE TESTINS (SL 03-28).DEVELOPRECOMMENDATIONS FOR FURTHER ACTIDN 86-21 TURKEY POINT NRR / ROSA F.
CONSIDER REVIEWINS ELECTRICAL 08/30/86 DPEN
/ /
06/23/E6 h / PDTENTIAL
/
SYSTEM 0F PLANT WITH SIMILAR
/ /
FAILURE OF ALL SWIN5 BUS DESIGN
/ /
EMERGENCY DIESEL 6ENERATORS B6-23 PEERY NRR / HOUSTON W.
OBIAIN AND REVIEW INFORMAT10N 08/29/06 OPEN
/ /
07/07/86 6E / FIRE IN
/
RELATED TO RECURRENCE OF FIRE
/ /
OFFSAS CHARC0AL AND INVEST 16 ATE PROPOSED
/ /
BEDS ACTIONS B6-23 MULTI NRR / HOUSTON W.
DETERMINE APPROPRIATE 09/30/26 0 FEN
/ /
07/07/66 NA /
/
REBULATORY REQUIREMENTS BASED
/ /
BWRS-RESIDUAL ON RECOMMENDATIONS DISCUSSED AT / /
HEAT REMOVAL BRIEFING PUMP / WEAR RINS FAILURES -
FDLLOWUP B6-23 MULTI NRR /EERLINGER C.
ASSURE NRR AND IE COORDINATION 08/30/86 DPEN
/ /
07/07/06 NA /
/
TO DETERMINE THE NEED FOR AN IE
/ /
PWRS-INADEQUATE BULLETIN
/ /
DESIGN OF ECCS PUMP MINIMUM FLOW PATHS
, 86-26 PANCHO SECD 1 NRR /RESAN W.
FIND OUT IF PUMPS f,RE USED IN 09/30/96 OPEN
/ /
, 07/22/E6 SW / EDTH TRAINS
/
DTHER SYSTEMS AT RANCHO SEC0
/ /
OF DECAY HEAT
/ /
REMOVAL DECLARED TECHNICALLY IN0PERAELE
. Page No.
2 C/08/B6 DPERATIN6 REACTORS EVENTS MEETING FULLDWUP ITEMS AS OF MEETING 86-27 ON AU6UST 4, 1986 IIN ASCENDING MEETING DATE, NSSS VEND 05, FACILITY ORDER)
EETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUMBER /
NSSSVEND6R/
DIVISIDN/
COMPLET. BY DOCUMENT, EETIN6 EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
DATE B6-26 RANCHO SECO 1 NRR /REGAN W.
FOLLOWUP DN USE OF FERMINITE IN 08/30/06 DPEN
/ /
07/29/96 BW / BOTH TRAINS
/
PUMPS DRAIN LINE
/ /
OF DECAY HEAT
/ /
REMOVAL DECLAPED TECHNICALLY INOPERABLE 86-26 RANCHO SECD I IE / STONE J.
ASSESSTHEPDTENt!ALFOR 08/30/06 CLOSED 08/04/06 07/28/B6 BW / BOTH TRAINS
/
SENERIC APPLICABILITY
/ /
ASSESSMENT OF DECAY HEAT
/ /
PROVIDED ON REMOVAL DECLARED 7/31/B6 INOPERABLE File has been deleted.
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