ML18092B157
| ML18092B157 | |
| Person / Time | |
|---|---|
| Site: | Salem, Palo Verde, Surry, 05000000, Trojan |
| Issue date: | 05/27/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606020372 | |
| Download: ML18092B157 (34) | |
Text
,------
MAY 2 7 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON MAY 19, 1986 - MEETING 86-17 On May 19, 1986, an Operating Reactor Events meeting (86-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 12, 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 seve~al 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 cc w/Encl.:
See Next Page DISTRIBUTION I Central File NRC PDR ORAS Rdg ORAS Members
- JF:
BC:~
RWESSMAN Gary M. Holahan, Director Operating Reactors Assessment Staff
~
D: ORAS r.'\\~ ~
GHOLAHAN
'1
__L /.)-/ k --5-1
)
/.2) /86 5 l&//86 5 l-;;,/86
'1'-8606-020372 860527 PDR ADOCK 0~5"000272 S
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAY 2 7 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON MAY 19, 1986 - MEETING 86-17 On May 19, 1986, an Operating Reactor Events meeting (86-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 12, 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.
~~~°DLkJ Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/Encl.:
See Next Page
Harold cc:
D. Eisenhut M. Licitra J. Taylor R. Lee
- c. Heltemes G. Knighton T. Murley, Reg. I K. Johnston J. Nelson Grace, Reg. I I T. Chan J. Keppler, Reg. III
- w. Jones R. D. Ma rt in, Reg. IV D. Fischer J. B. Ma rt in, Reg. v
- s. Varga R. Starostecki, Reg. I R. Samworth R. Walker, Reg. II
- c. Patel
- c. Nore.l i us, Reg. I II L. Rubenstein E. Johnson. Reg. IV D. Kirsch, Reg. v H. Thompson 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. Baer E. Weiss R. Hernan
- s. Showe
- s. Rubin J
NAME R. Lee K. Johnston D. Terao D. Crutchfield
- c. Mi 11 er L. Crocker W. Regan L. Kelly G. Murphy D. Allison H. Bailey A. Dromerick M. Srinivasan M. Chiramal E. Jordan
- c. Rossi F. Miraglia G. Holahan ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-17)
MAY 19, 1986 DIVISION NAME NRR/PDB-7 D. Tarnoff NRR/PAD-3 B. Bagchi NRR/EB-A
- w. Swenson NRR/PWR-B B. Samworth NRR/PWR-B D. Ziemann NRR/PAFO G. Knighton NRR/PWR-B J. Fair NRR/ORAS/PWR-B D. Fischer ORNL/NOAC W. Jones IE/EAB J. Stone IE/EAB W. Paulson IE/EGCB
- s. Rubin NRR/BWR E. Brown AEOD R. Baer IE F. Schroeder NRR/PWR-A T. Novak NRR/PWR-B M. Virgilio NRR/ORAS J. T. Beard DIVISION NRR/ORAS NRR/EB-A NRR/ORAS NRR/PAFO NRR/DHFT NRR/PD-7 IE/DEPER NRR/PAD-3 IE/EAB IE/VPB NRR/PWR-B AEOD AEOD IE/DEPER NRR/PWR-B NRR/PWR-A NRR/ORAS NRR/ORAS
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING (86-17)
PALO VERDE UNITS 1 & 2 TROJAN SALEM UNIT 1 SURRY UNITS 1 & 2 MAY 19 I 1986 DISRUPTION OF OFFSITE POWER LINES REPEATED SNUBBER FAILURES LOSS OF BOTH MAIN FEEDWATER PUMPS OTHER EVENT OF INTEREST ELECTRICAL SYSTEM PROBLEMS
PALO VERDE UNITS l & 2 - DISRUPTION OF OFFSITE POWER LINES MAY 14, 1986 <R. LEE, NRR)
SLIDE NOT AVAILABLE FOR REPRODUCTION
_I
TROJAN - REPEATED SNUBBER FAILURES JUNE, 1985 <K. JOHNSTON, NRR)
PROBLEM:
STEAM GENERATOR HYDRAULIC SNUBBERS LOCKING UP DUE TO DESIGN INADEQUACY.
SIGNIFICANCE:
0 DAMAGE TO HOT LEG PIPE WHIP RESTRAINT (1985) 0 OVERSTRESSING OF HOT LEG ELBOWS 0
PREVIOUSLY UNACCOUNTED FOR MOVEMENT IN THE PRESSURIZER SURGE LINE (1982-1985)
CIRCUMSTANCES:
0 NRC RECENTLY LEARNED THAT RCS HOT LEG PIPE RESTRAINT HAD PULLED FROM WALL IN 1985 0
0 0
0 0
LICENSEE, NRR, AND REGION V WALKED DOWN RCS PIPING DYE PENETRANT TEST PERFORMED ON "B" SG ELBOW.
NO INDICATIONS FOUND.
~ PERFORMED UT ON ALL 4 HOT LEG ELBOWS AND FOUND NO INDICATIONS CRUSHED GRAPHITE SHIMS FOUND ON 3 OF 4 HOT LEG PIPE WHIP RESTRAINTS INDICATING HOT LEG TO RESTRAINT BINDING 11 OF 16 SG SNUBBERS FOUND TO HAVE FAILED AGAIN IN SAME WAY BACKGROUND:
0 1982 - LICENSEE REMOVED THE THERMAL SLEEVE ON THE 0
0 PRESSURIZER SURGE LINE; HOWEVER, SURGE LINE DID NOT SETTLE OVER NEXT FEW CYCLES, AS HAD BEEN EXPECTED IN
~ANALYSES; MOVEMENT CONTINUED 1985 - LICENSEE HIRED IMPELL TO REVIEW THE SURGE LINE MOVEMENT; UNABLE TO ACCOUNT FOR CONTINUED MOVEMENT 1985 - A HOT LEG <TO SG "B") PIPE WHIP RESTRAINT HORIZONTAL SUPPORT WAS FOUND PULLED FROM THE WALL
TROJAN - REPEATED SNUBBER FAILURES JUNE, 1985 <K. JOHNSTON, NRR), (CON'T,)
BACKGROUND, (CON 'TI) 0 1985 - SNUBBERS TESTED PER NEW TS REQUIREMENTS 0
0
- 2 OF 16 SG HYDRAULIC SNUBBERS WOULD NOT RESPOND TO 100 KIP LOAD; SHOULD HAVE RESPONDED AT< 10 KIP; ALL 16 WERE DECLARED INOPERABLE AND REBUILT
- SNUBBER FAILURE ATTRIBUTED TO CLOGGED HYDRAULIC LINES; CLEANED WHEN ASSUMED THAT ALL SG SNUBBERS WERE INOPERABLE, IMPELL ANALYSES WAS ABLE TO ACCOUNT FOR THE SURGE LINE MOVEMENT AND THE DAMAGE TO THE PIPE WHIP RESTRAINT THE LICENSEE CLAIMED (1985) THAT ALTHOUGH HOT LEG STRESSES EXCEEDED ASME SECTION III ALLOWABLES, STRAIN IS WITHIN 1%
LIMIT, WHICH WAS NRC-APPROVED LIMIT FOR SONGS-1 ON SEISMIC CRITERIA AND METHODOLOGY FOLLOW-UP:
0 SNUBBER CONTROL VALVES TO BE REPLACED WITH NEW DESIGN 0
LICENSEE TO PERFORM PRE-STARTUP WALKDOWN OF RCS IN A HOT CONDITION 0
NRR TO REVIEW RCS PIPING STRESSES AND APPLICABILITY AND ACCEPTABILITY OF LICENSEE'S ANALYSIS
14~RC.-t!IOl"*'l0 LOOP 1. OML.Y SOR. C.Ol<ITINUA.'TION Ill lllCiU"I J,C.*I IA"*RH*1~1R.*I~
1..00P 40,.,,J..Y
'O" CDf>,IT1)..MJA.'TION "9 '16UIU,,C.*8 TYPICAL REACTOR COOLANT
..kQQE J'Dll'~TlNUATION Ml FltlUA.n l.Cf*4, l.Cf*S,J.r.-C.,.lMO lkT.
RU.CTOll I VtWL
~
I
SALEM UNIT 1 - LOSS OF BOTH MAIN FEEDWATER PUMPS MAY 12, 1986 CW. R. JONES, IE)
PROBLEM:
NYLON CORD WAS USED TO HOLD LIMIT SWITCH CONTACTS CLOSED.
SIGNIFICANCE:
0 INDICATION OF PAST MAINTENANCE PRACTICES CIRCUMSTANCES:
0 0
0 0
0 0
0 0
PLANT AT 95% POWER; REACTOR TRIP DUE TO SIG HI FLOW WITH LO LEVEL; BOTH MAIN FEEDWATER PUMPS HAD TRIPPED SINGLE VALVE PROTECTS CLEANUP LINE BACK TO HOT WELL (PIPE RATED AT 600 PSI) FROM MAIN FEED PUMP DISCHARGE PRESSURE (850 - 1200 PSI)
LIMIT SWITCH MONITORS VALVE POSITION.
IF CONTACT IS OPEN, IT INDICATES VALVE IS OPEN, AND CAUSES BOTH MAIN FEED PUMPS TO TRIP.
THE VALVE ITSELF WAS ADMINISTRATIVELY CONTROLLED AND WAS LOCKED CLOSED; HOWEVER, LONG HISTORY OF CONTACT SWITCH NOT MAKING UP -- CONSEQUENTLY A NYLON CORD WAS USED TO TIE THE CONTACTS CLOSED THERE HAD BEEN AN EXISTING LONG-STANDING WORK ORDER TO REMOVE V~LVE'S ACTUATOR, AND ELIMINATE NEED FOR LIMIT SWITCH.
LOW PRIORITY WORK ITEM.
WORK WAS COMPLETED AFTER 5/12/86 REACTOR TRIP -- PRIOR TO RESTART UNIT 2 VALVE rs BEING HELD CLOSED WITH A METAL WIRE.
A SIMILAR WORK ORDER EXISTS FOR UNIT 2 AND WORK WILL BE ACCOMPLISHED AS SOON AS METHOD IS DEVISED TO PERFORM WORK AT POWER WITH LOW RISK OF REACTOR TRIP.
FOLLOW-UP:
° COMPLETE APPROVED WORK ORDER ON UNIT 2 0
REGION I HAS REVIEWED LICENSEE ACTIONS AND WILL CONTINUE TO FOLLOW.
REGION FEELS LICENSEE IS ADEQUATELY CONCERNED ABOUT EVENT.
EVENT IS RESULT OF HOLD OVER FROM PREVIOUS PRACTICES.
0 LICENSEE HAS A PROGRAM IN PLACE TO ADDRESS POSSIBLE CHALLENGES TO SAFETY SYSTEMS, WHICH INCLUDES SINGLE-CHANNEL BOP INPUTS
CONDENSER HOT WELLS TO STEAM GENERATORS VALVE BF - 65 CONDENSATE PUMPS HIGH PRESSURE BYPASS HIGH PRESSURE HEATERS
( SALE"M 1 LOW PRESSURE FW HEATERS S/G FEED PUMPS
OTHER EVENT OF INTEREST SURRY UNITS 1 & 2 - ELECTRICAL SYSTEM PROBLEMS MAY 11, 1986 CR. SAMWORTH, NRR)
PROBLEM:
UNIT 1:
REMOVAL OF STATION BATTERY CAUSED LOSS OF ONE TRAIN OF DC POWER AND SAFETY INJECTION UNIT 2:
12 HOURS LATER, DEGRADED OFFSITE POWER TO ONE DIVISION OF CLASS IE BUSES ON BOTH UNITS RESULTED IN A TRIP OF UNIT 2 SIGNIFICANCE:
0 BATTERY REMOVAL PROCEDURES INADEQUATE 0
USE OF MAINTENANCE CROSS-TIE BETWEEN DC TRAINS TO RESTORE POWER 0
POTENTIAL GENERIC APPLICABILITY CIRCUMSTANCES:
UNIT 1 0
PREPARING TO ENTER COLD SHUTDOWN FOR REFUELING OUTAGE; RCS AT 220°F; ON RHR SYSTEM 0
0 0
0 0
0 0
PER STONE & WEBSTER PROCEDURES FOR BATTERY REMOVAL, TECHNICIANS REDUCED CHARGER VOLTAGE FROM 132VDC TO 125VDC; PROCEDURE ANTICIPATED THAT CHARGER WOULD CARRY ALL DC LOADS WHEN BATTERY DISCONNECTED, BUS VOLTAGE FELL SHARPLY AND THEN STABILIZED AT ONLY 100 VDC THIS CAUSED AN ESF ACTUATION SIGNAL INITIATING TRAIN "B" SAFETY INJECTION, INCLUDING CHARGING PUMP REALIGNMENT TO THE SI MODE, LETDOWN ISOLATION, CONTAINMENT PHASE I AND II ISOLATION, AND START OF SHARED EMERGENCY DIESEL GENERATOR #3 ALSO LOST CONTROL ROOM ANNUNCIATOR PANELS F THROUGH K OPERATORS RESET SI AND REGAINED CONTROL OF CHARGING AND LETDOWN 800 GALLONS OF BORATED WATER INJECTED, INCREASING PRESSURIZER LEVEL FROM 33% TO 42%
DC POWER RESTORED TO DIVISION "B" WITH CROSS-TIE TO DIVISION "A" DC POWER
SURRY UNITS 1 & 2 - ELECTRICAL SYSTEM PROBLEMS MAY 11, 1986 CR. SAMWORTH, NRR), CCON'T,)
CIRCUMSTANCES, CCON'T,)
UNIT 2 0
AT 100% POWER 0
LOAD TAP CHANGER ON "C" RESERVE STATION TRANSFORMER FAILED TEMPORARILY IN LOW OUTPUT CONDITION 0
0 0
0 RESULT WAS DEGRADED VOLTAGE CONDITIONS ON UNIT 1 lH AND UNIT 2 2J 4160 EMERGENCY BUSES ERRATIC CONTROL ROD POSITION SIGNALS AND NUCLEAR INSTRUMENTATION CHANNEL 4 RESULTED IN A SERIES OF TURBINE RUNBACK SIGNALS REACTOR TRIPPED ON OVERPOWER DELTA T AS OPERATORS WERE TRYING TO STABILIZE THE UNIT.
ROD CONTROL SYSTEM WAS IN MANUAL.
UNDERVOLTAGE CONDITION ON 2J BUS PERSISTED FOR MORE THAN 60 SECONDS ACTUATING DEGRADED VOLTAGE PROTECTION SYSTEMj WHICH CAUSED EMERGENCY DIESEL GENERATOR #3 TO START AND TO LOAD THE 2J BUS, FOLLOW-UP:
0 LICENSEE DETERMINED THE PROCEDURES FOR REMOVING THE BATTERY FROM SERVICE WERE INADEQUATE 0
STAFF DETERMINED CROSS-TYING THE TWO DC TRAINS TO RE-ENERGIZE THE BUS WAS NOT A LICENSE VIOLATION 0
0 LOAb TAP CHANGER WAS FOUND BACK IN THE NORMAL POSITION FOLLOWING THE EVENT.
LICENSEE INSTALLED SPECIAL MONITORING STAFF AND LICENSEE FOUND NO INTERCONNECTION BETWEEN UNITS WHICH COULD RELATE THE TWO EVENTS
DATE 05/12/86 05/13/86 05/13/86 05/13/86 05/14/86 05/15/86 05/17/86 05/17/86 05/17/86 05/18/86 05/18/86
~
05/19/86 SITE i..*
KEWAUNEE HATCH
--**-----~-----***-- --*- *- *-.*- -*
REACTOR SCRAM
SUMMARY
WEEK ENDING 05/18/86 I. PLANT SPECIFIC DATA SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL SALEM 1
93 A PERSONNEL/MA INT NO 4
FARLEY 2
12 A EQUIP/MFW NO 2
LACROSSE 1
0 A EQUIP/ELECT NO 6
KEWAUNEE 1
100 A PERSONNEL/TEST YES 4
CATAWBA 1
0 A EQUIP/MFW NO 4
HATCH 1
36 A PERSONNEL YES 1
BEAVER VALLEY 1
0 A EQUIPMENT NO 3
CATAWBA 2
15 A PERSONNEL ND 1
CATAWBA 1
45 A PERSONNEL NO 5
INDIAN POINT 3
4 A EQUIPMENT NO 2
CATAWBA 2
15 M EQUIPMENT NO 2
FARLEY 1
99 A EQUIPMENT NO 2
SUMMARY
OF COMPLICATIONS UNIT COMPLICATIONS 1
1 SOURCE RANGE CHANNELS FAILED TO ENERGIZE AT SETPOINT MAIN STEAM LINE FLOW TRANSMITTER INSTALLED BACKWARDS
I I. COMPARISON OF WEEl<LY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/18/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMSC5)
AVERAGE AVERAGE YTD (3) (4)
- POWER >15/.
EQUIP. RELATED
>15/.
1 4.4 5.4 (68/.)
PERS. RELATEDC6> >15/.
4 2.4 2.0 (25/.)
OTHERC7>
)15/.
0 (I. 0 0.6 ( 7/.)
- Subtotal **
5 6.8
- 8. (I
!r
- POWER <15/.
EQUIP. RELATED
<15/.
6 L7
- 1. 3 (54/.)
PERS. RELATED
<15/.
1 1.2 0.9 (38/.)
OTHER
<15/.
0 0.1 0.2 ( 8/.)
- Subtotal **
7 3.0 2.4
- Total ***
12 9.8 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1
0.7
- 1. 0 AUTOMATIC SCRAMS 11 9.1 9.4
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 CAUSE 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 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 95 REACTORS HOLDING A FULL POWER LICENSE.
- 6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 7.
noTHERu INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
Page Na.
(!5/20/86 MEETING NUMBER/
MEETING DATE 86-10 03/31i86 86-.10 03i31/86 86-10 03/31/86 86-13 04i21 i86 86-13 04121 /86 FACILITY NSSS VENDOR/
EVENT DESCFJP.
OYSTER CREEK SE I LEVEL SWITCH SETPOINT DF:IFT BRAiDWODD ;.
~ I WATER HAMMER JN MAIN STEAK LINE HADDAM NECK w ! NEW SMALL BREAK LOCA RESULTS PEACH BOTTaM BE I LOSS OF QFFSITE POWER SOURCE DUE TO A TRANSFORMER FIRE AND EDG FAILURE RIVER BEND w
I QA CONCERNS I
INVOLVING ARCHITECT ENGINEER OPERATINB REACTORS £VENTS ME£TJN6 FOLLOWUP iTEMS AS OF MEETING 86-17 ON MAY 19, 1986
!IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORD£RI RESPONSIBLE DIVISION/
INDIVIDUAL NRR iHOUSTON NRR /NDONAN w
v NP.R /SPEIS T I
IE iJOROAN E 1c:
/JORDAN E TASK DESCRIPTION RESOLVE THE ~UESTION OF THE ACCEPTABILITY OF BLIND SWITCHES AND DELETION OF DAILY CHANNEL CHECK RHlUEST REPORT OF EVENT FROM LICENSEE ASSESS THE POTENTIAL FOR GENERiC APPLI CAB I Li TY EVALUATE NEED FOR IE NOTICE DETERMINE NEED FDR VENDOR INSPECTION SCHEDULE CUMPLET.
DATE !SI 06/30/86 I I 05/30/86 05/0i/86 I I i)5/30/86 I
I r
I i 05130/86 I
j I
I I 05i30/B6 I i
! I CLOSED DATE BY DOCUMENT, MEETINS, ETC.
OPEN OPEN OPEN OPEN OPEN ENCLOSURE 3 COMMENTS REVIEW BEING ACCOMPLISHED UHDEH TAC NO 61203
MAY 2 7 1986 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERAtING REACTORS EVENTS MEETING ON MAY 19, 1986 - MEETING 86-17 On May 19, 1986, an Operating Reactor Events meeting (86-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 12, 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 cc w/Encl.:
See Next Page DISTRIBUTION Centra 1 F/i 1 e NRC PDR ii ORAS Rdg ORAS Members
=JF:
)
/2) /86 sc:rJ/I..~
RWESSMAN 5 lc9//86 Gary M. Holahan, Director Operating Reactors Assessment Staff
~
D:ORAS rJ\\~ ~
GHOLAHAN s /'l'J./86
MEMORANDUM FOR:
FROM:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAY 2 7 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 MAY 19, 1986 - MEETING 86-17 On May 19, 1986, an Operating Reactor Events meeting (86-17) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 12, 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 a~vise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
~~~<cL{Jd\\J Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/Encl.:
See Next Page
Harold cc:
D. Eisenhut M. Licitra J. Taylor R. Lee
- c. Heltemes G. Knighton T. Murley, Reg. I K. Johnston J. Nelson Grace, Reg. I I T. Chan J. Keppler, Reg. I I I W. Jones R. D. Ma rt in, Reg. IV D. Fischer J. B. Martin, Reg. V
- s. Varga R. Starostecki, Reg. I R. Samworth R. Walker, Reg. I I
- c. Patel
- c. Nore.l i us, Reg. I II L. Rubenstein E. Johnson. Reg. IV D. Ki rs ch, Reg. V H. Thompson 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. Baer E. Weiss R. Hernan
- s. Showe
- s. Rubin
NAME R. Lee K. Johnston D. Terao D. Crutchfield
- c. Mi 11 er L. Crocker
- w. Regan L. Kelly G. Murphy D. Allison H. Bailey A. Dromerick M. Srinivasan M. Chiramal E. Jordan
- c. Rossi F. Miraglia G. Holahan ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-17)
MAY 19, 1986 DIVISION NAME NRR/PDB-7 D. Tarnoff NRR/PAD-3 B. Bagchi NRR/EB-A
- w. Swenson NRR/PWR-B B. Samworth NRR/PWR-B D. Ziemann NRR/PAFO G. Knighton NRR/PWR-B J. Fair NRR/ORAS/PWR-B D. Fischer ORNL/NOAC W. Jones IE/EAB J. Stone IE/EAB
- w. Paulson IE/EGCB
- s. Rubin NRR/BWR E. Brown AEOD R. Baer IE F. Schroeder NRR/PWR-A T. Novak NRR/PWR-B M. Virgilio NRR/ORAS J. T. Beard DIVISION NRR/ORAS NRR/EB-A NRR/ORAS NRR/PAFO NRR/DHFT NRR/PD-7 IE/DEPER NRR/PAD-3 IE/EAB IE/VPB NRR/PWR-B AEOD AEOD IE/DEPER NRR/PWR-B NRR/PWR-A NRR/ORAS NRR/ORAS
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING (86-17)
PALO VERDE UNITS 1 & 2 TROJAN SALEM UNIT 1 SURRY UNITS 1 & 2 MAY 19, 1986 DISRUPTION OF OFFSITE POWER LINES REPEATED SNUBBER FAILURES LOSS OF BOTH MAIN FEEDWATER PUMPS OTHER EVENT OF INTEREST ELECTRICAL SYSTEM PROBLEMS
PALO VERDE UNITS 1 & 2 - DISRUPTION OF OFFSITE POWER LINES MAY 14, 1986 <R. LEE, NRR)
SLIDE NOT AVAILABLE FOR REPRODUCTION
TROJAN - REPEATED SNUBBER FAILURES JUNE, 1985 CK. JOHNSTON, NRR)
PROBLEM:
STEAM GENERATOR HYDRAULIC SNUBBERS LOCKING UP DUE TO DESIGN INADEQUACY.
SIGNIFICANCE:
0 DAMAGE TO HOT LEG PIPE WHIP RESTRAINT (1985) 0 OVERSTRESSING OF HOT LEG ELBOWS 0
PREVIOUSLY UNACCOUNTED FOR MOVEMENT IN THE PRESSURIZER SURGE LINE (1982-1985)
CIRCUMSTANCES:
0 NRC RECENTLY LEARNED THAT RCS HOT LEG PIPE RESTRAINT HAD PULLED FROM WALL IN 1985 0
0 0
0 0
LICENSEE, NRR, AND REGION V WALKED DOWN RCS PIPING DYE PENETRANT tEST PERFORMED ON "B" SG ELBOW, NO INDICATIONS FOUND.
~ PERFORMED UT ON ALL 4 HOT LEG ELBOWS AND FOUND NO INDICATIONS CRUSHED GRAPHITE SHIMS FOUND ON 3 OF 4 HOT LEG PIPE WHIP RESTRAINTS INDICATING HOT LEG TO RESTRAINT BINDING 11 OF 16 SG SNUBBERS FOUND TO HAVE FAILED AGAIN IN SAME WAY BACKGROUND:
0 1982 - LICENSEE REMOVED THE THERMAL SLEEVE ON THE 0
0 PRESSURIZER SURGE LINE; HOWEVER, SURGE LINE DID NOT SETTLE OVER NEXT FEW CYCLES, AS HAD BEEN EXPECTED IN
~ANALYSES; MOVEMENT CONTINUED 1985 - LICENSEE HIRED IMPELL TO REVIEW THE SURGE LINE MOVEMENT; UNABLE TO ACCOUNT FOR CONTINUED MOVEMENT 1985 - A HOT LEG CTO SG "B") PIPE WHIP RESTRAINT HORIZONTAL SUPPORT WAS FOUND PULLED FROM THE WALL
TROJAN - REPEATED SNUBBER FAILURES JUNE, 1985 CK. JOHNSTON, NRR), <CON'T.)
BACKGROUND I (CON 'TI) 0 1985 - SNUBBERS TESTED PER NEW TS REQUIREMENTS 0
0
- 2 OF 16 SG HYDRAULIC SNUBBERS WOULD NOT RESPOND TO 100 KIP LOAD; SHOULD HAVE RESPONDED AT< 10 KIP; ALL 16 WERE DECLARED INOPERABLE AND REBUILT
- SNUBBER FAILURE ATTRIBUTED TO CLOGGED HYDRAULIC LINES; CLEANED WHEN ASSUMED THAT ALL SG SNUBBERS WERE INOPERABLE, IMPELL ANALYSES WAS ABLE TO ACCOUNT FOR THE SURGE LINE MOVEMENT AND THE DAMAGE TO THE PIPE WHIP RESTRAINT THE LICENSEE CLAIMED (1985) THAT ALTHOUGH HOT LEG STRESSES EXCEEDED ASME SECTION III ALLOWABLES, STRAIN rs WITHIN 1%
LIMIT, WHICH WAS NRC-APPROVED LIMIT FOR SONGS-I ON SEISMIC CRITERIA AND METHODOLOGY FOLLOW-UP:
0 SNUBBER CONTROL VALVES TO BE REPLACED WITH NEW DESIGN 0
LICENSEE TO PERFORM PRE-STARTUP WALKDOWN OF RCS IN A HOT CONDITION 0
NRR TO REVIEW RCS PIPING STRESSES AND APPLICABILITY AND ACCEPTABILITY OF LICENSEE'S ANALYSIS
TYPICAL REACTOR COOLANT
...!::QQ£
\\
SALEM UNIT 1 - LOSS OF BOTH MAIN FEEDWATER PUMPS MAY 12, 1986 CW, R. JONES, IE)
PROBLEM:
NYLON CORD WAS USED TO HOLD LIMIT SWITCH CONTACTS CLOSED.
SIGNIFICANCE:
0 INDICATION OF PAST MAINTENANCE PRACTICES CIRCUMSTANCES:
0 PLANT AT 95% POWER; REACTOR TRIP DUE TO SIG HI FLOW WITH LO LEVEL; BOTH MAIN FEEDWATER PUMPS HAD TRIPPED 0
0 0
0 0
0 0
SINGLE VALVE PROTECTS CLEANUP LINE BACK TO HOT WELL CPIPE RATED AT 600 PSI) FROM MAIN FEED PUMP DISCHARGE PRESSURE
( 850 - 1200 PS I)
LIMIT SWITCH MONITORS VALVE POSITION.
IF CONTACT IS OPEN, IT INDICATES VALVE IS OPEN, AND CAUSES BOTH MAIN FEED PUMPS TO TRIP.
THE VALVE ITSELF WAS ADMINISTRATIVELY CONTROLLED AND WAS LOCKED CLOSED; HOWEVER, LONG HISTORY OF CONTACT SWITCH NOT MAKING UP -- CONSEQUENTLY A NYLON CORD WAS USED TO TIE THE CONTACTS CLOSED THERE HAD BEEN AN EXISTING LONG-STANDING WORK ORDER TO REMOVE VALVE'S ACTUATOR, AND ELIMINATE NEED FOR LIMIT SWITCH.
LOW PRIORITY WORK ITEM.
WORK WAS COMPLETED AFTER 5/12/86 REACTOR TRIP -- PRIOR TO RESTART UNIT 2 VALVE IS BEING HELD CLOSED WITH A METAL WIRE.
A SIMILAR WORK ORDER EXISTS FOR UNIT 2 AND WORK WILL BE ACCOMPLISHED AS SOON AS METHOD IS DEVISED TO PERFORM WORK AT POWER WITH LOW RISK OF REACTOR TRIP.
FOLLOW-UP:
° COMPLETE APPROVED WORK ORDER ON UNIT 2 0
REGION I HAS REVIEWED LICENSEE ACTIONS AND WILL CONTINUE TO
- FOLLOW, REGION FEELS LICENSEE IS ADEQUATELY CONCERNED ABOUT EVENT.
EVENT IS RESULT OF HOLD OVER FROM PREVIOUS PRACTICES.
0 LICENSEE HAS A PROGRAM IN PLACE TO ADDRESS POSSIBLE CHALLENGES TO SAFETY SYSTEMS, WHICH INCLUDES SINGLE-CHANNEL BOP INPUTS
CONDENSER HOT WELLS TO STEAM GENERATORS VALVE BF - 65 CONDENSATE PUMPS HIGH PRESSURE BYPASS HIGH PRESs'tJRE HEATERS
( SALEM 1 LOW PRESSURE FW HEATERS S/G FEED PUMPS
OTHER EVENT OF INTEREST SURRY UNITS 1 & 2 - ELECTRICAL SYSTEM PROBLEMS MAY 11, 1986 <R. SAMWORTH, NRR)
PROBLEM:
UNIT 1:
REMOVAL OF STATION BATTERY CAUSED LOSS OF ONE TRAIN OF DC POWER AND SAFETY INJECTION UNIT 2:
12 HOURS LATER, DEGRADED OFFSITE POWER TO ONE DIVISION OF CLASS IE BUSES ON BOTH UNITS RESULTED IN A TRIP OF UNIT 2 SIGNIFICANCE:
0 0
0 BATTERY REMOVAL PROCEDURES INADEQUATE USE OF MAINTENANCE CROSS-TIE BETWEEN DC TRAINS TO RESTORE POWER POTENTIAL GENERIC APPLICABILITY CIRCUMSTANCES:
UNIT 1 0
PREPARING TO ENTER COLD SHUTDOWN FOR REFUELING OUTAGE; RCS AT 220°F; ON RHR SYSTEM 0
0 0
0 0
0 0
PER STONE & WEBSTER PROCEDURES FOR BATTERY REMOVAL, TECHNICIANS REDUCED CHARGER VOLTAGE FROM 132VDC TO 125VDC; PROCEDURE ANTICIPATED THAT CHARGER WOULD CARRY ALL DC LOADS WHEN BATTERY DISCONNECTED, BUS VOLTAGE FELL SHARPLY AND THEN STABILIZED AT ONLY 100 VDC THIS CAUSED AN ESF ACTUATION SIGNAL INITIATING TRAIN "B" SAFETY INJECTION, INCLUDING CHARGING PUMP REALIGNMENT TO THE SI MODE~ LETDOWN ISOLATION, CONTAINMENT PHASE I AND II ISOLATION, AND START OF SHARED EMERGENCY DIESEL GENERATOR #3 ALSO LOST CONTROL ROOM ANNUNCIATOR PANELS F THROUGH K OPERATORS RESET SI AND REGAINED CONTROL OF CHARGING AND LETDOWN 800 GALLONS OF BORATED WATER INJECTED, INCREASING PRESSURIZER LEVEL FROM 33% TO 42%
DC POWER RESTORED TO DIVISION "B" WITH CROSS-TIE TO DIVISION "A" DC POWER
SURRY UNITS 1 & 2 - ELECTRICAL SYSTEM PROBLEMS MAY 11, 1986 <R. SAMWORTH, NRR), <CON'T.)
CIRCUMSTANCES, <CON'T.)
UNIT 2 0
AT 100% POWER 0
LOAD TAP CHANGER ON "C" RESERVE STATION TRANSFORMER FAILED TEMPORARILY IN LOW OUTPUT CONDITION 0
0 0
0 RESULT WAS DEGRADED VOLTAGE CONDITIONS ON UNIT 1 lH AND UNIT 2 2J 4160 EMERGENCY BUSES ERRATIC CONTROL ROD POSITION SIGNALS AND NUCLEAR INSTRUMENTATION CHANNEL 4 RESULTED IN A SERIES OF TURBINE RUNBACK SIGNALS REACTOR TRIPPED ON OVERPOWER DELTA T AS OPERATORS WERE TRYING TO STABILIZE THE UNIT.
ROD CONTROL SYSTEM WAS IN MANUAL.
UNDERVOLTAGE CONDITION ON 2J BUS PERSISTED FOR MORE THAN 60 SECONDS ACTUATING DEGRADED VOLTAGE PROTECTION SYSTEM, WHICH CAUSED EMERGENCY DIESEL GENERATOR #3 TO START AND TO LOAD THE 2J BUS.
FOLLOW-UP:
0 LICENSEE DETERMINED THE PROCEDURES FOR REMOVING THE BATTERY FROM SERVICE WERE INADEQUATE 0
0 0
STAFF DETERMINED CROSS-TYING THE TWO DC TRAINS TO RE-ENERGIZE THE BUS WAS NOT A LICENSE VIOLATION LOAD TAP CHANGER WAS FOUND BACK IN THE NORMAL POSITION FOLLOWING THE EVENT.
LICENSEE INSTALLED SPECIAL MONITORING STAFF AND LICENSEE FOUND NO INTERCONNECTION BETWEEN UNITS WHICH COULD RELATE THE TWO EVENTS
t DATE 05/12/86 05/13/86 05/13/86 05/13/86 05/14/86 05/15/86 05/17/86 05/17/86 05/17/86 05/18/86 05/18/86 05/19/86 SITE KEWAUNEE HATCH REACTOR SCRAM
SUMMARY
WEEK ENDING 05/18/86 I. PLANT SPECIFIC DATA SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL SALEM 1
93 A PERSONNEL/MA INT NO 4
FARLEY 2
12 A EQUIP/MFW NO 2
LACROSSE 1
0 A EQUIP/ELECT NO 6
KEWAUNEE 1
100 A PERSONNEL/TEST YES 4
CATAWBA 1
0 A EQUIP/MFW NO 4
HATCH 1
36 A PERSONNEL YES 1
BEAVER VALLEY 1
0 A EQUIPMENT NO 3
CATAWBA 2
15 A PERSONNEL NO 1
CATAWBA 1
45 A PERSONNEL NO 5
INDIAN POINT 3
4 A EQUIPMENT ND 2
CATAWBA 2
15 M EQUIPMENT NO 2
FARLEY 1
99 A EQUIPMENT NO 2
SUMMARY
OF COMPLICATIONS UNIT COMPLICATIONS 1 SOURCE RANGE CHANNELS FAILED TD ENERGIZE AT SETPOINT 1 MAIN STEAM LINE FLOW TRANSMITTER INSTALLED BACKWARDS
I I. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/18/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMSC5>
AVERAGE AVERAGE YTD (3) (4)
- POWER >15/.
EQUIP. RELATED
)15/.
1 4.4 5.4 C68'l.)
PERS. RELATEDC6> >15/.
4 2.4 2.0 C25'l.>
OTHERC7)
>15'l.
0
- o. (l 0.6 ( 7'l.)
- Subtotal **
5 6.8
- 8. (l
- POWER <15/.
EQUIP. RELATED
<15/.
6 L7
- 1. 3 (54'l.)
PERS. RELATED
< 15'l.
1 1.2 0.9 C38'l.)
OTHER
<15'l.
(l 0.1 0.2 ( 8/.)
- Subtotal **
7 3.0 2.4
- Total ***
12 9.8 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1
0.7
- 1. 0 AUTOMATIC SCRAMS 11 9.1 9.4
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 CAUSE 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 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 CHOLDING 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 95 REACTORS HOLDING A FULL POWER LICENSE.
- 6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 7.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
Page Na.
05/20/86 MEETING NUMBER/
MEETING DATE 86-10 03/31i96 86-10 03/3i/86 86-10 03!3 i /86 86-13 04/21/86 B6-13 04/21/86 FACILITY NSSS VENDOR/
EVENT DESCRIP.
OYSTER CREEK BE ! LEVEL SWITCH SETPOHH DF:!FT.
BRAiDWOOD w I WATER HAMMER 1N MAIN STEAM LINE HADDAM NECK w I NEW SMALL BREAK LOCA RESULTS PEACH BOTTOM SE I LOSS OF OFFSITE POWEF:
SOURCE DUE TO A TRANSFORMER FIRE AND EDG FA!LUF:E RIVER BEND w ' QA CONCEF:NS I
INVOLVING ARCHITECT ENGINEER OPERATINS REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETING 86-17 ON MAY 19, 1986 (IN ASCEND ING MEET ING DATE, NSSS VENDOR, FACIUTY ORDER)
RESPONSIBLE DIVISION/
INDIVIDUAL NRR /HOUSTON w HRR /NOONAN V NP.R /SPEIS T I
Tt:
- ~ /JORDAN E ye
.~ /JORDAN E I
TASK DESCRIPTION RESOLVE THE QUEST! ON OF THE ACCEPTABILITY OF BLIND SWITCHES AND DELETION OF DAILY CHANNEL CHECK REQUEST REPORT OF EVENT FROM LICENSEE ASSESS THE POTENTIAL FOR GENERiC APPLiCABiUTY EVALUATE NEED FOR IE N01ICE DETERMINE NEED FOR VENDOR INSPECTION SCHEDULE COl1PLET.
DHTElSl 06/30/86
! i I
05/30/86 05/01/86 I I 05/30/86 I
I i 05/30/86 I
I I
'/ i 05i30/86 I i I
j CLOSED DATE BY DOCUMENT, l'IEETitlG, ETC.
OPEN I
OPEN I
I OPEN OPEN OPEN ENCLOSURE 3 COMMENTS REVIEW BEING ACCOMPLISHED UNDrn TAC NO 61203