ML20062C811
| ML20062C811 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Sequoyah, Braidwood, Haddam Neck, Fort Calhoun File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/16/1990 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-025, OREM-90-25, NUDOCS 9011020151 | |
| Download: ML20062C811 (22) | |
Text
-
October 16, 1990 MEMORANDUM FOR:
Charles E. Roasi, Sirector Division of Operat M al Events Assessment FROM:
Alfred E. Chaffee, Chiei Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING
=
OCTOBER 10, 1990 - MEETIPS 90 25 On October 10, 1990, weconductedanOperatingReactorsEventsmeeting(9025)
_i to inform senior managers from NRR, ACRS, AE00, RES, Commission staff, and.
regional offices of selected events that occurred since our last briefing'on-October 3,1990. lists the attendees. -Enclosure 2 presents the significant elements of the discussed events.
- contains. reactor scram statistics for the week ending 10/07/90.
- tabulates two significant events which were identified for input into the NRC performance indicator program.
2 Original slened by Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION:
2 Central File' 1
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1 October 16, 1990 1
I MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATlHG REACTORS EVENTS MEETING i
OCTOBER 10, 1990 MEETING 90-25 4
On October 10, 1990, we conducted an Operating Reactors Events meeting (90 25)'
to inform senior managers from NRR, ACRS, AE00, RES, Comission staff, and regional offices of selected events that occurred since our last briefing on October 3, 1990. lists the attendees. presents the significant elements of the discussed events.
'. contains reactor scram statistics for the week ending 10/07/90.
. tabulates two significant events which were identified for input into the NRC performance indicator program.
Original signed by Alfred E. Chaffee, Chief Events Assessment Branch Division of OpraHonal Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION:
Central File EAB Reading File Circulating Copy, EAB Staff MLReardon, EAB LKilgore, SECY PDR WKR rl0 FC :EAB:00EA
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ATE :10//o/90
- 10/a./90
- 10// /90 0FFICIAL RECORD COPY Document Name: TRANSMITTAL LETTER 10/10/90
CC:
T. Murley, NRR S. Sands, NRR F. Miraglia, HRR R. Dudley, NRR W. Russell, NRR D. Neighbors, NRR F. Gillespie, NRR R. Capra, NRR J. Partlow, NRR J. Donohew, NRR S. Varga, NRR F. Hebdon, NRR
]
R. Wessman, NRR i
G. Lainas, NRR l
D. Crutchfield, NRR
_l J. Zwolinski, NRR l
B. Boger,ilRR W. Travers,ilRR J. Richardson, NRR A. Thadani, NRR F. Rosa, NRR B. Grimes, NRR F. Congel, NRR J. Roe, NRR T. !!artin, RI l
W. Kane, RI l
C. Hehl, RI S. Ebneter, RII L. Reyes, R11 B. Davis, R111 E. Greenman, RIII i
S. Collins, RIV R.D. Martin, RIV J.B. Martin, RV R. Zimmerman, RV l
P. Boehnert, ACRS l
E. Jordan, AE0D i
T. Novak, AE0D L. Spessard, AE0D E. Weiss, AE00 l
S. Rubin, AE0D i"
M. Farper, AE0D W. Bateman, ED0 R. Newlin, GPA J. Cowan, lilP0 E. Beckjord, RES A. Bates, SECY s
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTOP.S EVEllTS BRIEFING (90-2M October 10, 1990 tame ORGAH12AT10H NAME ORGANIZATION T. Murley HRR/DONRR W. Russeii NRR/ADT P. Boehnert ACRS A. Chaffee NRR/DOEA M. Cullingford NRR/DONRR L. 01shan NRR/PD3-2 D. Fischer flRR/DOEA D. Neighbors llRR/PD1-1 C. Rossi NRR/DOEA J. Chesley ACRS L. Norrholm OCM/KC F. Nebdon NRR/PD2-4 M. Reardon llRR/DOEA H. Bailey NRR/DOEA K. Hart SECY V. Benaroya AEOD/DSP R. Pedersen OE F. Talbot-NRR/DRIS W. Brach NRR/DRIS G. Lainas NRR/DRP A. Fitzgerald NRR/DRIS C. Carpenter NRR/DRIS G. Marcus OCM/JC R. Pierson NRR/DRSP D. Trimble OCM/JC S. Diab NRR/DRSP R. Gallo OEDO R. Capra NRR/PD1-1 S. Varga NRR/DRP W. Jensen NRR/DOEA J. Thompset.
NRR/DOEA N. Wagner NRR/ DST W. Minners RES/DSIR D. Brinkman NRR/PD1-1 R. Jo'tes llRR/SRXB D. Ray NRR/DLPQ J. Birmingham NRR/DOEA J. Guttmann OCM/FR C. Thompson OEDO i
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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 90-25 EVENTS ASSESSMENT BRANCH LOCATION:
10B-11, WHITE FLINT WEDNESDAY, OCTOBER 10, 1990, 11:00 A.M.
BRAIDWOOD UNIT 1 REACTOR COOLANT LEAK OUTSIDE CONTAINMENT (AIT)
INDIAN POINT UNIT 3 SPENT FUEL ASSEMBLIES REMAIN ATTACHED TO UPPER lNTERNALS SEQUOYAH UNIT 1 MAIN STEAM LINE CHECK VALVES DISC NUT PIN FAILURES (AIT) l
90-25 BRAIDWOOD UNIT 1 REACTOR COOLANT LEAK OUTSIDE CONTAINMENT (AIT)
OCTOBER 4, 1990 PROBLEM REACTOR COOLANT LEAK INTO AUX BUILDING CONTAMINATED THREE INDIVIDUALS, CAUSE PREMATjRE OPENING OF 1RH8702B HOT LEG ISOLATION VALVE WITH THE VENT VALVE IN THE SAME LINE STILL OPEN.
SAFETY SIGNIFICANCE o
HAZARD TO PERSONNEL FROM BURNS AND CONTAMINATION, o
POTENTIAL FOR AN INTERSYSTEM LOSS OF COOLANT.
DISCUSSION o
PLANT IN MAINTENANCE OUTAGE SINCE 09/29/90 T0 INVESTIGATE SPURIOUS SAFETY INJECTION SIGNALS.
o REQUIRED SURVEILLANCES BEING PERFORMED ON THE RHR SUCTION ISOLATION VALVES.
INDIVIDUAL VALVE LEAK TESTING.
STROKE TIME TESTING, o
REACTOR SYSTEM AT 360 PSIG AND 180 F.
o THE REDUNDANT RHR TRAINS HAVE INDEPENDENT SUCTION LINES FROM THE HOT LEGS, o
ON THE B-RHR TRAIN WITH SUCTION VALVE 1RH8702A'OPEN, LEAKAGE THROUGH CLOSED 1RH8702B BEING COLLECTED-AND MEASURED THROUGH VENT VALVE 1RH028B, o
LEAKAGE TEST REPORTED TO BE COMPLETED, o
VENT VALVE 1RH028B REQUESTED TO BE CLOSED.
o ISOLATION VALVE 1RH8702B OPENED FROM THE CONTROL ROOM FOR STR0KE TIME TESTING.
o VENT VALVE 1RH028B NOT YET CLOSED, AIT:
YES CONTACT:
W. SHAFER/W, JENSEN SIGEVENT:
YES
REFERENCES:
10 CFR 50,72 #19523 AND MORNING REPORT 10/04/90
BRAIDWOOD UNIT 1 90-25 o
TYGON MEASURING TUBE BROKE LOOSE, o
TWO TEST ENGINEERS SFRAYED WITH COOLANT, ONE EQUIPMENT ATTENDANT WAS BURNED (ALL THREE WERE CONTAMINATED),
o 620 GALLONS OF COOLANT LEAKED INTO AUX BUILDING, o
SZ LOSS IN PZR LEVEL.
S1h1LAR E_V_ENTS (BRAIDWOOD) o ON 12/01/89 60,000 GALLONS OF COOLANT LEAKED THROUGH B-TRAIN RHR SUCTION RELIEF VALVE AT BRAIDWOOD UNIT 1, o
ON 3/18/90 INADVERTENT OPENING OF AN RHR SUCTION VALVE ON i
UNIT 2 CAUSED COOLANT LOSS TO THE PWST AND LOSS OF PZR LEVEL INDICATION, FULLOWUP o
AIT SENT TO THE SITE T0 INVESTIGATE EVENT INCLUDING ROOT CAUSE ADEQUACY OF OPERATOR PERFORMANCE, PROCEDURES AND ADMINISTRATIVE
- CONTROLS, o
CONFIRMATORY ACTION LETTER ISSUED TO LICENSEE BY REGION 111, i
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1 BRAIDWOOD UNIT 1 3
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90-25 INDIAN POINT UNIT 3 SPENT FUEL ASSEMBLIES REMAIN ATTACHED T0 llPPER INTERNALS OCTOBER 4,1990 PROBLEM ON OCTOBER 4, 1990, THE LICENSEE DISCOVERED, WHILE LIFTING THE UPPER CORE INTERNALS, TWO FUEL ASSEMBLIES HAD BEEN INADVERTENTLY LIFTED FROM THE CORE AND REMAINED ATTACHED TO THE BOTTOM OF THE UPPER CORE INTERNALS, CAUSE EXACT CAUSE FOR FUEL ASSEMBLIES REMAINING ATTACHED TO THE UPPER CORE INTERNALS IS UNKNOWN AT PRESENT.
SAFETY SIGNIFICANCE DROPPED FUEL BUNDLE ONTO CORE COULD RESULT IN DAMAGE TO FUEL CLADDING AND DAMAGE TO OTHER FUEL ASSEMBLIES, DISCUSSION o
ON OCTOBER 4, 1990, WHILE IN REFUELING (MODE 6), TWO FUEL BUNDLES WERE DISCOVERED HANGlWG FROM THE BOTTOM 0F UPPER CORE PLATE DURING REMOVAL OF THE UPPER INTERNALS PACKAGE, o
THE BOTTOM OF THE FUEL ASSEMBLIES ARE APPR0XIMATELY 3'11" OVER THE TOP 0F THE CORE AND THE UPPER INTERNALS HAVE BEEN DISPLACED 66" EAST FROM THE INSTALLED POSITION, o
THE TWO ASSEMBLIES ARE B-13 (CONTAINS A BURNABLE POIS0N ASSEMBl.Y)
AND A-5 (CONTAINS A THIMBLE PLUG ASSEMBLY),
o THE CRANE (LOAD CELL) DID NOT DETECT THE ADDED WEIGHT TO THE UPPER INTERNALS (128,000 LBS) FROM THE TWO ASSEMBLIES (1500 LBS, EACH).
THIS WAS DUE TO THE WEIGHT OF THE ASSEMBLIES WITHIN THE NOISE BAND FOR WEIGHT ACCURACY OF THE LOAD CELL.
R ERE E:
lb FR 5 72 #19526
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.Ib'DI AN POINT UNIT 3 90-25 DISCUSSION (CONTINUED) o USING A REMOTE VIDE 0 SUBMEhSIBLE, THE LICENSEE DETERMINED THAT ONE-0F-TWO GUIDE PINS (0N BOTH ASSEMBLY) IS BENT (AND NOT TOUCHING THE ASSEMBLY), WITH THE OTHER GUIDE PIN WEDGED INTO THE ASSEMBLY, SUCH THAT THE ASSEMBLY IS C0CKED AT ABOUT A 7 DEGREES ANGLE TO THE UPPER CORE PLATE.
o THE LICENSEE'S FUTURE PLAN OF ACTION INCLUDES:
- 3. PERFORMING A STATIC LIFT OF THE UPPER INTERNALS ANOTHER 8 FT,
- 2. MANUALLY ROTATING THE UPPER INTERNALS SUCH THAT THE ASSEMBLIES WILL BE POSITIONED OUTSlDE OF THE VESSEL AND CAVITY SEAL,
- 3. MOVING THE UPPER INTERNALS TO THE DEEP-END OF THE REFUELING i
CAVITY AND LOWERING THE ASSEMBLIES INTO TWO FABRICATED STEEL BASKETS (16" DIAMETER PIPING) WITH HOLES DRILLED INTO 1HE BASKETS FOR WATER SEEPAGE.
THE BASKETS WILL REST ON A TABLE CONSTRUCTED FOR THIS PURPOSE, Li, ATTEMPT TO FREE THE ASSEMBLIES, o
A CONFlRMATORY ACTION LETTER (CAL) HAS BEEN ISSUED TO THE LICENSEE AND REQUESTS THE LICENSEE TO PROVIDE A PLAN OF ACTION'AND NRC l
AGREEMENT BEFORE TAKING FURTHER ACTION,
~
SIMILAR EVENTS o
PAllSADES (9-3-88)
DURING REMOVAL OF REACTOR VESSEL UPPER GUIDE STRUCTURE (CE),
ONE FUEL ASSEMBLY WAS FOUND ATTACHED TO BOTTOM 0F UPPER GUIDE STRUCTURE, ASSEMBLY WAS FREED USING SPECIAL TOOLS, CABLES, AND A JIB CRANE, o
FOREIGN REACTOR EVENT (5-5-87)
DURING REFUELING OPERATIONS, A FUEL ASSEMBLY WAS FOUND ATTACHED TO THE UPPER INTERNALS UFON REMOVAL 0F.THE UPPER-3 INTERNALS PACKAGE.
ATTEMPTS TO FREE THE ASSEMBLY RESULTED.
IN DROPPING THE-ASSEMBLY TO THE BOTTOM 0F THE REFUELING _ CAVITY, o
HADDAM NECK INFORMATION NOTICE 86-58 i
J
1.NDIAN POINT UNIT 3 90-25 FOLLOWUP o
THE REGION AND NRR HAVE PROVIDED 24 HOUR SITE COVERAGE AND WILL CONTINUE TO PROVIDE ASSISTANCE TO THE SITE INSPECTORS UNTll THE EVENT IS TERMINATED, o
NPR AND THE REGION HAVE SENT A SPECIAL INSPECTION TEAM TO THE SITE TO REVIEW THE LICENSEE'S PROCEDURES AND FUTURE ACTIONS, o
EAD WILL FOLLOW THIS EVENT AND DETERMINE 1F ANY GENERIC COMMUNICATIONS ARE WARRANTED, l
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90-25 SEQUOYAH UNIT 1 MAIN STEAM LINE CHECK VALVES DISC NUT PIN FAILURES (AIT)
OCTOBER 8, 1990 PROBLEM THE LICENSEE FOR UNIT 1 DISCOVERED THAT 3 0F 4 MAIN STEAM LINE CHECK VALVES HAD DISC NUT PIN FAILURES WITH ONE OF THE VALVE i
DISCS LOCATED DOWNSTREAM 0F THE VALVE BODY, CAUSE EXACT CAUSE IS UNKNOWN AT PRESENT, SAFETY SIGNIFICANCE FAILURE OF A CHECK VALVE COULD PREVENT CLOSURE OF THE ASSOCIATED MSIV DUE TO REVERSE FLOW CONDITIONS DURING A MSLB, BACKGROUND f
o IN 1982, A MS CHECK VALVE FAILED AT THE SEAL WELD ON THE CHAMFERED-SIDE OF THE DISC, o
EARLY 1990, THE LICENSEE (WITH THE VALVE VENDOR) MADE REPAlRS AND MODIFICATIONS AT THE REQUEST OF ATWOOD AND MORRILL TO 3 0F 4 UNIT 1 MS CHECK VALVES BECAUSE OF TURBULENCE-INDUCED FLOW l
VlBRATIONS CAUSING THE VALVES TO CHATTER EXCESSIVELY, o
THE MODIFICATION WAS TO UPGRADE THE VALVES AT UNITS 1/2 TO CURRENT VENDOR DESIGN, WHICH INCLUDED A RETAINIF PIN THROUGH THE DISC NUT, o
THE VENDOR HAD BEEN MAKING THESE UPGRADED VALVES SINCE 1982 TIMEFRAME, o
THE VALVES AT SEQUOYAH WERE PURCHASED IN EARLY 3970'S, DISCUSSION o
IN LATE SEPTEMBER 1990, AFTER_ HEARING LOUD NOISES COMING FROM MS CHECK VALVE 1-CK-1-624 (0N S/G 2), THE LICENSEE ATTEMPTED TO MANUALLY MOVE THE VALVE FLAPPER / DISC, DISC MOVEMENT EXHIBITED RESISTANCE AFTER A FEW INCHES OF TRAVEL, THE VALVE VENDOR WAS CONSULTED, AIT:
YES CONTACT:
J. THOMPSON SIGEVENT:
YES l
REFERENCE:
10 CFR 50,72 #19549 i
SEQU0YAH UNIT 1 90-25 DISCUSSION (CONTINUED) o RESULTS FROM THE SURVEILLANCE INDICATED THAT ALL VALVE DISCS WERE IN PLACE, o
APPR0X TWO WEEK LATER, THE LICENSEE PERFORMED X-RAY SURVElLLANCE ON MS CHECK VALVE 1-CK-1-624.
o THE X-RAY SHOWED THAT THE CHECK VALVE DISC HAD SEPARATED, o
FURTHER SURVElLLANCE BY THE LICENSEE DISCOVERED THAT 3 0F 4 CHECK VALVES HAD FAILED DISC PINS, o
THE PINS WERE SHEARED WHERE THE VALVE DISC MEETS THE FLAPPER ARM, o
ONE VALVE (UPON DISASSEMBLY) REVEALED THAT THE DISC HAD TRAVELLED SOME DISTANCE IN THE MAIN STEAM PIPING AFTER ITS DISC PIN FAILED, o
UNIT 2 (UPON DISASSEMBLY) SHOWED NO DISC PIN FAILURES, o
THE CHECK VALVES ARE MANUFACTURED'BY ATWOOD a MORRILL AND ARE DESCRIBED AS A 32" VALVE, 26" ID, WITH THE FLAPPER & DISC WEIGHING APPR0X 700 LBS, o
THREE OF THE FOUR VALVES ON UNIT 1 HAD BEEN MODIFIED.
THE MODIFIED VALVES FAILED, NO FAILURES INDICATED ON THE UN-MODIFIED VALVES, o
THE MODIFICATION WAS TO PUT A RETAINING PIN THROUGH THE DISC NUT TO PREVENT THE NUT FROM LOOSENING, FGLLOWUP o
AIT SENT TO THE SITE ON 10-09-90, o
EAB WILL FOLLOW THIS EVENT TO DETERMINE GENERIC SIGNIFICANCE AND FURTHER ACTION,
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At4Ci04 SCRAM $UMMARY NEEK EClO 10/07/90 ENCLOSURE 3
- 1. PLANT $PICIFICDATA Daft Slit UN!i PONER SISNAL CAU$t COMPLI-VfD VfD VfD CAil0NS A80VE DELOW 10iAL 151 151 10/04/90 MILT $'ONE 1
100 M
[0VIPMENT NO 2
0 2
10/06/90 HATCH 1
22 A
[0VIPMENT ND 3
0 3
10/06/90 FERMI 2
1A (GUIPMENT ND 1
1 2
10/07/90 CATAWBA 2
98 A (GUIPMENT NO 1
0 1
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- 31. COMF ARISON Oc WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 10/07/90 SCRAM CAUSE POWER NUMBER 1990 1989 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)
- FOWER >15%
i EOUIP. RELATED
>15%
3 3.4 2.9 3.1 3.9 4.3 PERS. RELATED(6) >15%
0 0.7 1.0 1.0 1.3 1.8 OTHER(7)
>15%
0 0.0 0.1 0.5 1.2 0.'
- Subtotal **
3 4.1 4.0 4.6 6.4 6.5 r
- POWER <15%
EQUIP. RELATED
<15%
1 0.4 0.4 0.5 1.2 1.4 FERS. RELATED
<15%
1 0.1 0.3 0.3 0.6 0.8 OTHER
<15%
0 0.0 0.7 0.1 0.3 0.2
- Subtotal **
2 0.5 1.4 0.9 2.1 2.4
- Total ***
5 4.6 5.4
- 5. 5 0.5 8.9 MANUAL VS AUTO SCRAMS TYPE NUMBER 1990 1989 1988 1987 1C86 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 1
1.3 C.9 1.0 1.4 1.0 AUTOMATIC SCRAMS 4
3.3 3.8 4,5 7.0 7,9 v
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 ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
2.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED 10 CAUSE OF SCRAM.
3.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
.0EAD SCRAM DATA Manual and Automatic Scrams for 1986 ------------------ 461 Manual and Automatic Scrams for 1987 ------------------ 439 i
Manual and Automatic Scrams for 1983 ------------------ 287 K
Manual and Automatic Scrams for 1989 ------------------ 244 i
ManualandAutomaticScramsfor1990(YTD10/07/90)---174 4
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i ENCLOSURE'4 10/C4/90 FEEF0KP.AN:[ ikCA10K$ $liN1FICANT [VEN11' FLANTh:.PI [.'t NT GTR ll6hlFICANCE [V[N1 DE$tklF110N IAll FORTCALK0LN1 N/25/90 0 FDTINTIAL FOR OR AtiUAL tilFALATION [L[VAi[D AP.ll[NT 1[MFIEATUR[$ (AU3! H!AT )UlltVP IN DFSAf[1MELA!!!10UlFPENT. Ih5TRUPEN1CAllh[T!AtiVLisd6IN[MEE6[NCYt![$tt 6tNIFATORFM}L[MS. 4 Alt:P NIO: (0/:0/90 0 (01[h11AL FDA 0A ACTUC itGRALATION TUFilh[ IRIVIN AFW PUMF $1[AM AIMili10N VALVil CFiN iC3 (FSAffiV4tLAi!D[GUTFJtET. Fall CAU51Ni FUMF iklF DN OviA!F((D. FLOW CtNTEDLLER $tillNB h[t!!$ARY TO ACH![VE MINIMUM E!GUlKED FLCnEATI tilutis IN illF 0F ATW FUU TUK)]NIS Di DV[FSF((D. 5 4}}