ML16341D839
| ML16341D839 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Byron, Diablo Canyon, Rancho Seco, 05000000 |
| Issue date: | 08/04/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608190327 | |
| Download: ML16341D839 (42) | |
Text
PgG 4 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
SUBJECT'ary M. Holahan, Director Operating Reactors Assessment Staff
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON JULY 28, 1986 - MEETING 86-26 On July 28, 1986, an Operating Reactor Events meeting (86-26) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 21, 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.
Original Signed By:
il Original Signed By:
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/Encl.:
See Next Page DISTRIBUTION
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 4, 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
SUBJECT:
Gary M. Holahan, Director Oper ating Reactors Assessment Staff
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON JULY 28, 1986 - MEETING 86<<26 On July 28,
- 1986, an Operating Reactor Events meeting (86-26) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on July 21, 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.
Enclosures:
As Stated
.~~ p ZM Gary M. Hol an, Director Operating Reactors Assessment Staff cc w/Encl.:
See Next Page
c ag.
Harold R. Denton cc:
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Vollmer Taylor Heltemes Ross Murley, Reg. I Nelson Grace, Reg. II
- Keppler, Reg. III D. Martin, Reg.
IV B. Martin, Reg.
V Starostecki, Reg. I
- Ebneter, Reg. I Walker, Reg. II
- Norelius, Reg. III Johnson.
Reg.
IV Kirsch, Reg.
V Thompson Miraglia Bernero Speis Russell Novak Schroeder Houston Sheron Ziemann Crutchfield Lainas Benaroya
=
Regan Vassallo Jordan Rossi-Baer Wqiss Hernan Showe Rubin Baranowsky
'L. Olshan V. Noonan H. Bailey G. Plumlee W. Regan S. Miner J. Stolz D. Hood B. Youngblood R.
Rothman J.
Stang J. Zwolinski
~
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ENCLOSURE 1
LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING 86-26 JULY 28 1986 NAME G. Holahan W. Swenson P. Kelly K. Eccleston G. Plumlee T. Cappucci B. Clayton T. Rotelly R.
Hermann S. Miner H. Bailey P.
Lam
'J.
Stone D. Crutchfield E. Jordan E. Rossi J. Stolz C. Ader F. Miraglia DIVISION NRR/ORAS NRR/ORAS NRR/PDB-6 TOSS NRR/PWR-8 NRR/PWR-8 NRR/PWR-A NRR/DBL/BWD-1 NRR/DBL NRR/PDB-6 IE/DEPER/EAB AEOD IE/DQAVT/VPB NRR/PWR-B IE NRR/PWR-A NRR/PWR-8 OCM/TR NRR/PWR-8 NAME M. Virgilio D. Tarnoff M. Caruso D. Vassallo W.
Regan V. Benaroya J.
Crooks J.
Stang G. Murphy C. Miller E. Weiss G. Klingler W. Paulson R.
Rothman F.
Rowsome G. Lainas D. Humenansky F. Schroeder DIVISION NRR/ORAS NRR/ORAS NRR/ORAS NRR/DBL NRR/PWR-8
'RR/PAFO AEOD NRR/DBL/BWD-1 ORNL NRR/PWR-8 IE/DEPER/EAB IE/DI/ORP8 NRR/PWR-8 NRR/PWR-8 NRR/DHFT NRR/DBL OCM/LZ NRR/PWR-8
I
~
Et(CLOSURE 2
OPERATING REACTOR EVENTS BRIEFING 86-26 JULY 28'986 FOREIGN REACTOR EXPERIENCE BYRON UNIT 1 RANCHO'ECO UNIT 1 NCGUI RE UNIT 2 gp~ $ 7d RANCHO SECO'ND DIABLO CANYON g~-g l5 LOCA PRESSURIZER SAFETY VALVE NAINTENANCE AND INSTALLATION ERRORS BOTH TRAINS OF DECAY HEAT REMOVAL DECLARED TECHNICALLY INOPERABLE REACTOR TRIP WITH CONPLICATIONS N
'ARTHQUAKE OTHER EVENT OF INTEREST LACROSSE NON-ISOLABLE PRIMARY SYSTEN LEAK
FOREIGN REACTOR'XPERIENCE - LOCA W. SWENSON'RR BRIEFING SLIDE CONTAINS'ROPRIETARY INFORNATION
'I
BYRON 1 - PRESSURIZER SAFETY VALVE MAINTENANCE & INSTALLATION ERRORS JULY 17, 1986 (H. BAILEY IE)
PROBLEM:
MULTIPLE MAINTENANCE AND TESTING ERRORS ON PRESSURIZER SAFETY -VALVES, I
SIGNIFICANCE:
SIGNIFICANT DEFICIENCY IN MAINTENANCE AND TEST PROGRAMS FOR CLASS 1
- SYSTEM, CIRCUMSTANCES:
JULY 2i 1986 BEGAN A CONTROLLED SHUTDOWN DUE TO EXCESSIVE RCS UNIDENTIFIED LEAKAGE.
1C PRESSURIZER SAFETY VALVE TAILPIPE RTD INDICATED LEAKAGE, JULY 6, 1986 - SAFETY VALVE 1C WAS REMOVED AND REPLACED WITH ANOTHER SAFETY VALVE STORED IN THE MECHANICAL MAINTENANCE HOT SHOP AND BELIEVED. TO HAVE BEEN REBUILT, JULY 17, 1986 BEGAN UNIT HEATUP TO MODE 3, AT 1750 PSIG, LOST "CLOSED'.
INDICATION ON VALVE 1C.
LOCAL. INSPECTION SHOWED THAT BOTH 1A AND 1C SAFETY VALVES WERE LEAKING.
THE UNIT WAS COOLED TO MODE 5 ON JULY 19i 1986 AND BOTH lA AND 1C SAFETY VALVES WERE
- REMOVED, INVESTIGATION SHOWED THE 1C VALVE HAD BEEN REPLACED,WITH A VALVE WITHOUT A VALVE DISK, THIS WAS CAUSED BY INADE-.
QUATE "HQLD" AND "RED" TAG ACCOUNTABILITY, INVESTIGATION SHOWED THAT 1A AND 1C DISCHARGE TEMPERATURE RTDs WERE CROSSED.
THE 1'A SAFETY VALVE WAS THE ONE ORIGINALLY LEAKING ON JULY 2,
~
IT WAS Al SO 'FOUND THAT THE VALVES HAD BEEN TESTED TO
+ 3X PER ASME CODE AND THE LIFT SETPOINTS WERE NOT WITHIN THE 1X TECH SPEC REQUIREMENT ~
BYRON CONTINUED THE= FOLLOWING FACTORS ALSO WERE FOUND TO HAVE CONTRIBUTED TO THIS EVENT:
1)
INADEQUATE COMPONENT IDENTIFICATION OF SERIAL NUMBERS ON THE HOLD AND RED TAGS LED TO MISTAKEN IDENTIFY OF THE DEFECTIVE COMPONENTS, 2)
THE MAINTENANCE PROCEDURE DID NOT SPECIFICALLY LIST THE SETPOINT AND ACCEPTANCE RANGE OF THE SAFETY VALVES TESTED, 3)
INSUFFICIENT SEGREGATION OF DEFECTIVE PARTS FROM REBUILT PARTS LED TO CONFUSION AS TO WHICH COMPONENTS WERE DEFECTIVE AND WHICH WERE NOT 0)
INSUFFICIENT FIELD VERIFICATION OF SAFETY VALVES DISCHARGE TEMPERATURE RTD WIRING LED TO FALSE I
I IND CAT ON OF THE LEAKING SAFETY VALVE, t
FOLLOWUP:
THE LI'CENSEE HAS REQUESTED ON INDEPENDENT INPO ASSESSMENT AND HAS INSTITUTED A NUMBER OF CORRECTIVE ACTIONS, REGION III CONTINUES $0 INVESTIGATE'HESE EVENTS, ENFORCE-MENT ACTIONS ARE PLANNED,
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RANCHO SECO UNIT 1 BOTH TRAINS OF DECAY HEAT REMOVAL DECLARED TECHNICALLY INOPERABLE JULY 22 1986 (G L.
PLUMLEE. NRR)
PROBLEM:
LEAK ON THE 'B'ECAY HEAT REMOVAL (DHR)
PUMP CASING.
'A'HR TRAIN IN SERVICE WITH 'A'MERGENCY DIESEL GENERATOR (D/G)
OUT OF SERVICE, SIGNIFICANCE:
DHR CAPABILITY DEGRADED POTENTIAL GENERIC PUMP CASING PROBLEM DISCUSSION:
UNIT IN COLD S/D SINCE DECEMBER 26'986 OVERCOOLING EVENT 30 DROP PER MINUTE LEAK IDENTIFIED IN AN IDLE 'B'HR PUMP CASING LIKING FROM A 1" DIAMETER POROUS AREA OF THE CASING
'A'HR PUMP INSERVICE WITH 'A'/G INOPERABLE (SURVEILLANCE TEARDOWN)
UNUSUAL EVENT DECLARED AND TSC INITIALLYMANNED AS A PRECAUTIONARY MEASURE LICENSEE CONSIDERS THIS POTENTIALLY GENERIC TO 'A'HR PUMP ALSO LVR 86-002 REPORTED PIN HOLE LEAKS IN 'B'HR PUMP CAUSED BY DRAIN LINE ELBOW EROSION COMMON TO BOTH 'A'ND 'B'HR PUMPS ULTRASONIC EXAMINATION (UT)
OF 'B'HR PUMP CASING WITH CASING FULL OF WATER YEILDED INCONCLUSIVE RESULTS EMERGENCY PROCEDURE FOR BACKUP DECAY HEAT REMOVAL IMPLEMENTED UNUSUAL EVENT TO CONTINUE (8-9 DAYS) UNTIL 'A'/G IS RETURNED TO SERVICE FOLLOW-UP:
REGION IV IS FOLLOWING UP ON LICENSEE INVESTIGATIONS AND CORRECTIVE ACTIONS LICENSEE NEGOTIATING WITH CONSUMERS POWER (MIDLAND) FOR THE PURCHASE OF TWO PUMPS; ONE PURCHASE ON AN EMERGENCY BASIS TO REPLACE "B" DHR PUMP.
SCHEDULED FOR REPLACEMENT AUGUST 18'986
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MCGUIRE UNIT 2 -"REACTOR TRIP WITH COMPLICATIONS JULY 22 i 1986 (D,
HOOD NRR)
PROBLEM:
LOSS OF LOAD (LOLI CAUSES REACTOR TRIP ON HIGH PRIMARY PRESSURE FROM 93Ã POWER WITH RODS IN MANUAL
, SIGNIFICANCE:
OCCURRENCE OF PlOD.
FREQUENCY TRANSIENT WITH MULTIPLE EQUIPMENT FAILURES DISCUSSION; DEFECTIVE CARD IN DIGITAL ELECTRO-HYDRAULIC TURBINE CONTROL SYSTEM CAUSES LOL,(CLOSES GOVERNOR VALVE. FOLLOWED BY RX TRIP AND TURBINE TRIP)
~
PRIMARY PRESSURE INCREASED AT 19 LB/SEC TO 2385 psI6 MAX ONE OF THREE PRIMARY PORVs FAILS TO OPEN SOCKET WELD FAILURE ON ONE-INCH RELIEF VALVE ON HP FEEDWATER HEATER ONE IRI STICKS AT 1 X 10 AMPS DUE TO IMPROPER COMPENSATION FOLLOWUP:
ONE-INCH LINE ISOLATED AND SOCKET WELD REPAIRED SOURCE RANGE MANUALLY ENERGIZED, IRI ADJUSTED BLOCK VALVE FOR FAILED PORV MANUALLY CLOSED.
PORV TESTED SUCCESSFULLY BUT SLOW, LICENSEE INVESTIGATING FAILURE TO OPEN
RANCHO SECO AND DIABLO CANYON EARTHQUAKE JULY 21, 1986 (R, L.
ROTHMAN, NRR)
PROBLEM; EARTHQUAKE CHALFANT VALLEY (NEAR BISHOP),
CALIFORNIA SIGNIFICANCE:
FELT AT BOTH RANCHO SECO AND DIABLO CANYON I SCUSS ION:
MAGNITUDE 6,0 USGSi 6,1 CALIFORNIA DIVISION OF MINES AND GEOLOGY (CDMG)
DISTANCE RANCHO SECO 160 MILES, DIABLO CANYON. 220 MILES DID NOT TRIGGER STANDARD STRONG MOTION INSTRUMENTS AT EITHER PLANT - WAS NOT FELT AT SAN ONOFRE RECORDED ON MORE SENSITIVE SUPPLEMENTAL INSTRUMENTS AT DIABLO CANYON SEVERAL FORESHOCKS IN PRECEDING FEW DAYS (LARGEST MAGNITUDE 5,5),
MANY AFTERSHOCKS CDMG RECORDED PEAK GROUND ACCELERATION (PGA)
OF ABOUT 0,5Gi 14 KM FROM EPICENTER REGION IS KNOWN FOR HIGH SEISMICITY AND HAS BEEN IDENTIFIED AS A POSSIBLE GAP FOR A MAGNITUDE 7'VENT AN NRC/ORES SPONSORED STRONG MOTION EXPERIMENT IS ABOUT 30 MILES FROM EPICENTER FOLLOW-UP:
LICENSEE IS PROCESSING DIABLO'ANYON DATA STAFF WILL OBTAIN EPICENTRAL STRONG MOTION DATA FROM USGS CDMG AND NRC/RES CONTRACTOR FOR REVIEW 1
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OTHER EVENT OF INTEREST LACROSSE - NON-ISOLABLE PRIMARY SYSTEM LEAK JULY 17 1985 (J,
STANG NRR)
~PROBL N:
THROUGH-WALL CRACKS FOUND IN NON-ISOLABLE PORTION OF THE DECAY HEAT SUCTION LINE (PRIMARY SYSTEM PIPING)
SIGNIFICANCE:
LEAKAGE OF PRIMARY COOLANT IN THE CONTAINMENT DISCUSSION:
WHILE IN HOT SHUTDOWN A VERY SMALL DRIP WAS OBSERVED ON THE 8" SUCTION LINE TO THE DECAY HEAT REMOVAL PUMP 2
SMALL CRACKS FOUND IN THE DECAY HEAT SUCTION LINE IMMEDIATELYADJACENT TO A PURGE PORT PLUG CRACKS ARE APPROXIMATELY 1/8 INCH AND 3/16 INCH LONG ON THE OD CIRCUMFERENTIAL CRACKS, THE LICENSEE HAS CONTRACTED WITH SOUTHWEST RESEARCH TO INVESTIGATE AND ANALYZE CRACKS INSPECTIONS OF THE SUCTION LINE IN THE AREA OF THE CRACKS AND 2 SIMILAR PURGE PORT PLUGS HAVE BEEN COMPLETED, NO INDICATIONS OBSERVED EXCEPT THESE 2 CRACKS.
SOUTHWEST RESEARCH INSTITUTE PERFORMED ULTRASONIC TESTS'ICENSEE QA DEPARTMENT PERFORMED PENETRANT TESTS.
AFTER PRELIMINARY INSPECTION THE LICENSEE DOES NOT FEEL THE CRACKS WERE CAUSED BY IGSCC.
OPTIONS WHICH-INCLUDE PIPE REPLACEMENT AND WELD OVERLAY. ARE BEING EXAMINED BY LICENSEE NO DECISIONS HAVE BEEN MADE, J
FOLLOW-UP REGION III WILL FOLLOW THE LICENSEE'S COURSE OF ACTION REGION III TO ISSUE TIA TO REQUEST NRR PROVIDE TECHNICAL ASSISTANCE
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REACTOR SCR4M
SUMMARY
WEEK ENDING 07/27/86 I.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-.
YTD,YTD CATIONS 4BOVE BELOW 15%
15/
YTD TOTAL 07/22/86 07/22/86 07/23/86 07/24/86 07/24/86 07/25/86 07/25/86 07/25/86 07/25/86 07/26/86 07/26/86 07/27/86 COOK MCGUIRE OCONEE WOLF CREEK MILLSTONE PALO VERDE WNP GRAND GULF HOPE CREEK CALLAWAY SAN ONOFRE SUMMER 1
2 2
1
..2 2
1 1
1 3
1 90 A
92 A
100 A
13 A
17 A
50 A
71 A
78 4 3 4 73 4 80 M
90 A
PERSONNEL/MAINT YES EQUIPMENT YES EQUIP/EXCESS FW NO PERSONNEL YES PERSONNEL NO PERSONNEL/TEST NO PERSONNEL/TEST NO EQUIPMENT NO PERSONNEL NO EQUIP/TURB. CTRL NO EQUIP/CONDENSER YES IJNKNOWN/TESTING NO 2
2 4
4 3
3 3
3 0
4 5
0 0
1 7
1
- 2 2
6 1
1 1
4 5
10 5
6 5
6 SUMM4RY OF COMPLIC4TIONS SITE UNIT COMPLIC4T IONG COOK MCGUIRE WOLF CREEK
~ SAN ONOFRE 1
SRM SLOW TO ENERGIZE 2 PRIM.
PORV DID NOT OPEN IRMS MALFUNCTIONED 3/4" FWTR HTR RELIEF LINE RUPTURED 1
ONE SRM FAILED TO ENERGIZE 3 OFF-NORMAL RCP SEAL LEAKOFF
II.
COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 07/27/86 SCPAM CAUSE POWER NUMBER OF SCRAMS(5) 1986 WEEKLY AVERAGE YTD 1'785 WEEKLY AVERAGE (3) (4)
+~
POWER >15/
EQUIP.
RELATED
>15%
PERS.
RELATED(6) >15/
OTHER(7)
>15%
Subtotal 5
1 4.6
- 2. 1 0.3 7.0
- 5. 4 (68%)
- 2. 0 (25%)
0 6
(
7%)
8.0
~~
POWER <15/
EQUIP.
RELATED PERS.
RELATED OTHER Subtotal Total
< 15%
< 15%
<15%
0 2
0 1.6 1.1 O. 1 2.8
- 1. 3 (54/)
0.9 (38%)
0 2
( 8%)
2 4
- 10. 4 MANUAL VS AUTO SCRAMS TYPE NUMBER OF SCRAMS 1986 WEEKLY AVERAGE YTD 1985 WEEKLY AVERAGE MANUAL SCRAMS AUTOMATIC SCRAMS 0.8 9.0 1 ~ 0 9.4
s J 4
f
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NOTES 1.
PLANT SPECIFIC DATA-BASED ON INITIALREVIEW OF 50.72 REPORTS FOR THE WEEK gF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
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' PLAN/ PROCEDURE.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF. SCRAM.
3.
1985 INFORMATION DERIVEO FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985.
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 REACT9R PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 1PO OPERATING REACTORS 6,
PEPSQNNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
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83-28).DEVELOP RECCNNEHDATIONS (OR FURTHER A."?ION CONSIDER REVIEMINIB ELEC'IRKCAL SYSTEN O.
PLANT MKT)I BKNILAR SR!NB EJ(
DESKS)t DETAIN 4ND R(V!EM INFO%HAT!Oh PFLATED TC RECUR...ENCE CF FIR(
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