ML20046C841
| ML20046C841 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Hatch, Salem, Perry, Indian Point, Wolf Creek, Pilgrim, Surry, Waterford  |
| Issue date: | 07/06/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-023, OREM-93-23, NUDOCS 9308120291 | |
| Download: ML20046C841 (16) | |
Text
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w JUL 0 61933 MEMORANDUM FOR:
Brian K.
Grimes, Director Division of Operating Reactor Support FROM:
Alfred E.
Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING JUNE 23, 1993 - BRIEFING 93-23 On June 23, 1993, we conducted an Operating Reactors Events Briefing (93-23) to inform senior managers from offices of NRR, AEOD, RES, OE, ACRS, and regional offices of selected events that occurred since our last briefing on June 16, 1993.
lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending June 20, 1993.
Two significant events were identified for input into the NRC performance indicator program (Enclosure 4).
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Enclosures:
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WASHINGTON, D.C. 20556 0001 s; ~ f VUL 0 61993 MEMORANDUM FOR:
Brian K.
Grimes, Director Division of Operating Reactor Support FROM:
Alfred E.
Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING JUNE 23, 1993 - BRIEFING 93-23 On June 23, 1993, we conducted an Operating Reactors Events
?
Briefing (93-23) to inform senior managers from offices of NRR, AEOD, RES, OE, ACRS, and regional offices of selected events that occurred since our last briefing on June 16, 1993.
lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending June 20, 1993.
Two significant events were identified for input into the NRC performance indicator program (Enclosure 4).
A Alfred
. Chaffeer Ctlef Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated cc w/ enclosures:
See next page
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T. Murley, NRR (12G18)
W.
Reckley (PDIV-2)
F. Miraglia, NRR (12G18)
S. Black (PDIV-2)
F. Gillespie, NRR (12G18)
G. Edison (PDI-3)
J.
Partlow, NRR (12G18)
W. Butler (PDI-3)
S.
Varga, NRR (14E4)
J. Stone (PDI-2)
J.
Calvo, NRR (14A4)
C. Miller (PDI-2)
G.
Lainas, NRR (14H3)
J.
Roe, NRR (13E4)
J.
Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4)
W.
Russell, NRR (12G18)
J. Richardson, NRR (7D26)
A.
Thadani, NRR (8E2)
S.
Rosenberg, NRR (10E4)
C.
Rossi, NRR (9A2)
B.
Boger, NRR (10H3)
F.
Congel, NRR (10E2)
D.
Crutchfield, NRR (11H21)
W.
Travers, NRR (11B19)
D.
Coe, ACRS (P-315)
E.
Jordan, AEOD (MN-3701)
G.
Holahan, AEOD (MN-9112)
L.
Spessard, AEOD (MN-3701)
K.
Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
G.
Grant, EDO (17G21)
R. Newlin, GPA (2GS)
E.
A.
Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T.
Martin, Region I W.
Kane, Region I C.
Hehl, Region I S.
Ebneter, Region II E. Merschoff, Region II S.
Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B.
Beach, Region IV B.
Faulkenberry, Region V K.
Perkins, Region V bec:
Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957
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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-23)
JUNE 23, 1993 NAME OFFICE FAME OFFICE A.
CHAFFEE NRR J.
O'BRIEN NRR R.
DENNIG NRR D.
BREWER NRR F.
GRAY NRR A.
THADANI NRR E.
RECKLEY NRR C.
ROSSI NRR S.
ROSENBERG NRR J.
ROE NRR S.
WITTENBERG NRR G.
EDISON NRR S.
KENDRICK NRR V.
BENAROYA AEOD i
J.
ZIMMERMAN NRR J.
FLACK RES S.
FLANDERS NRR W.
TROSKOSKI OE V.
HODGE NRR D.
l TELEPHONE ATTENDANCE (AT ROLL CALL)
Peoions Resident Inspectors Region I Region II i
Region III Region IV Region V IIT/AIT Team Leaders Misc.
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OPERATING REACTORS EVENTS BRIEFING 93-23 LOCATION:
10 B11, WHITE FLINT WEDNESDAY, JUNE 23, 1993, 11:00 A.M.
WOLF CREEK VANTAGE SH FUEL FAILURES BEAVER VALLEY, UNIT 1 SALEM, UNIT 2 PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR
O O
93-23 VANTAGE SH FUEL FAILURES WOLF CREEK BEAVER VALLEY, UNIT 1 SALEM, UNIT 2 PROBLEM IN THESE THREE PLANTS, A SIGNIFICANT NUMBER OF FAILED FUEL RODS HAVE BEEN FOUND DURING REFUELING OUTAGES CARRIED OUT-BETWEEN MARCH AND MAY 1993.
CAUSE GRID TO R0D FRETTING, BUT WITH DIFFERENT INITIATORS:
o WOLF CREEK HIGH CROSS FLOW VELOCITIES IN LOWER PART OF FUEL ASSEMBLY (FA) LENGTH DUE TO MIXTURE OF TWO TYPES OF FA BOTTOM N0ZZLES:
V5H AND LOPAR.
ALL FAILURES IN LOPAR FAs.
o BEAVER VALLEY 1 AND SALEM 2
[
] VIBRATION OF THE ENTIRE FA CAUSED BY [
3.
ALL FAILURES IN V5H FAs.
CONTACT:
F. ZARZUELA, NRR/0EAB AIT:
NO
REFERENCES:
10 CFR 50.72 #25267, SIGEVENT:
TBD MORNING REPORT DATED 05/06/93 AND MORNING REPORT DATED 05/21/93
WOLFLCREEK 93-23 BEAVER VALLEY, UNIT 1 SALEM, UNIT 2 SAFETY SIGNIFICANCE o
INCREASED REACTOR COOLANT (RC) ACTIVITY CAUSES ALARA CONCERNS.
1 o
REACHING RC TECHNICAL SPECIFICATIONS ACTIVITY LIMITS.
WOULD REQUIRE PLANT SHUTDOWN.
o POSSIBILITY OF SIMULTANE0US FAILURE DURING TRANSIENTS 0F FUEL RODS SUSCEPTIBLE TO THESE FAILURE MECHANISMS.
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' BEAVER VALLEY, UNIT 1 93-23 SALEM, UNIT 2 FOLLOWUP o
WESTINGHOUSE HAS SUGGESTED THE FOLLOWING CORRECTIVE MEASURES:
SHORT TERM (FOR FAs ALREADY IN THE CORE)
E 3
LONG TERM (FOR FAs TO BE MANUFACTURED)
[
]
o WESTINGHOUSE STATES THAT IT WILL NOT ISSUE A PART 21 NOTIFICATION BECAUSE N0 SUBSTANTIAL SAFETY HAZARD IS RAISED BY THESE FAILURES. THIS ASSERTION IS STILL BEING l
DISCUSSED BY SRXB.
o SRXB WILL ISSUE AN INFORMATION NOTICE WHEN IT GETS MORE INFORMATION.
o o
93-23 WOLF CREEK MARCH 16, 1993 DESCRIPTION DURING STH REFUELING OUTAGE, 40 FUEL R0D FAILURES o
DISTRIBUTED IN 3 FAs.
o DURING 6TH REFUELING OUTAGE, 17 FUEL R0D FAILURES DISTRIBUTED IN 3 FAs.
CHARACTERISTICS OF FAILURES:
- LOPAR TYPE FAs IN THE CORE FOR AT LEAST 2 CYCLES
- FAs WITH FAILED RODS LOCATED IN INNER POSITIONS OF THE CORE
- MANY FAILED RODS PRESENTED HYDRIDING BLISTERS BESIDES FRETTING MARKS DISCUSSION IN CYCLE 5, NEW TYPE DEBRIS FILTER BOTTOM N0ZZLE (DFBN) o FAs WERE INTRODUCED IN ONE THIRD OF THE CORE.
IN CYCLE 6, CORE WAS LOADED WITH ONE THIRD OF V5H - DFBN -
PLUS ONE THIRD OF LOPAR-DFBN.
CURRENT 7TH CYCLE HAS ALL FAs WITH DFBN, EITHER LOPAR OR V5H.
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WOLF CREEK 93-23 o
AFTER INVESTIGATIONS BY LICENSEE WITH WESTINGHOUSE SUPPORT, CAUSE OF FRETTING DETERMINED TO BE HIGH CROSS FLOWS IN LOWER PART OF FUEL LENGTH.
POTENTIAL CAUSE RELATED TO MIXTURE OF TRADITIONAL AND DRBN FAs:
V5H HAS A DFBN THAT IS 0.455 IN. LONGER THAN STANDARD, CAUSING A SMALL DELTA-P BETWEEN ITS OUTLET AND THE EQUIVALENT HEIGHT OF AN ADJACENT LOPAR FA o
OPEN ISSUE IS WHY THIS HAPPENED ONLY IN WOLF CREEK.
THERE ARE OTHER PLANTS THAT HAVE HAD SIMILAR MIXED CONFIGURATIONS IN THEIR TRANSITION TO V5H.
IT MAY BE RELATED TO A KNOWN AN0MALY IN LOWER PLENUM 0F WOLF CREEK REACTOR VESSEL.
FOLLOWUP SINCE WOLF C;5dK HAS FINISHED ITS TRANSITION TO DFBN, THIS FAILURE MECHANISM IS NOT EXPECTED TO RECUR.
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93-23 BEAVER VALLEY, UNIT 1 (MAY 5, 1993)
SALEM, UNIT 2 (MAY 20, 1993)
DESCRIPTION BEAVER VALLEY 1 FOUND, BY ULTRASONIC TESTING, 11 FAs o
WITH 35 FAILED FUEL RODS DURING ITS 9TH REFUELING OUTAGE.
RC ACTIVITY CALCULATIONS COMPUTED BY WESTINGHOUSE HAD ANTICIPATED 4 FAILED RODS.
SALEM 2 FOUND OPEN DEFECTS IN 13 FUEL RODS IN 8 FAs o
DURING ITS 7TH REFUELING OUTAGE.
RC ACTIVITY CORRELATIONS HAD ANTICIPATED 1 OR 2 OPEN DEFECTS.
o COMMON WAS:
GRID TO R0D FRETTING AT [
] LEVEL POSITIONS FAs [
]
DISCUSSION o
V5 IS A NEW TYPE OF FA. ITS NEW FEATURES ARE:
INTERMEDIATE FLOW MIXER (IFM) GRIDS, DESIGNED TO GET BETTER DNB PERFORMANCE DEBRIS FILTER (DF) BOTTOM N0ZZLE, DESIGNED TO PREVENT DEBRIS ACCESS TO CORE
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BEAVER VALLEY, UNIT 1 93-23 SALEM, UNIT 2 o
V5 FUEL RODS HAVE A DIAMETER OF 0.360 IN.
V5H IS AN ADAPTATION OF V5 DESIGN TO FAs WITH STANDARD DIAMETER (0.374 IN.) FUEL RODS.
o TO MAINTAIN CORE FLOW PARAMETERS WITH V5H FAs, A LOW PRESSURE DROP (LPD) GRID SPACER [
] THAT PRODUCES LOWER PRESSURE DROP WAS USED.
o V5H GRID SPRINGS [
3.
o WESTINGHOUSE INVESTIGATED AND MADE TESTS E
- 3. ITS CONCLUSIONS ARE:
FRETTING STEMS FROM [
]
VIBRATION [
] 0F THE FAs THE CAUSE IS E 3
o ROOT CAUSE IS [
]
o CODES ESTIMATING NUMBER OF FAILED RODS BASED ON RC ACTIVITY HAVE UNDERESTIMATED ACTUAL FAILURES FOUND.
f O
O acwsunu REACTOR SCRAM Reporting Period: 06/14/93 to 06/20/93 YTD YTD ABOVE BELOW YTD E
PLANT $ UNIT g
TYIl gap}i COM*LICATIONS M
M E
06/15/93 NATCM i 100 SA Equipment Fallure NO 2
1 3
06/15/93 WATERFORD 3 100 SA Equipment Fallure NO 2
0 2
06/20/93 SURRY 2 100 SA Equipment Failure No 1
0 1
i l
i l
Nite Year To Date (YTD) Totals Include Events Within The Calender fear Irdicated By The End Date of The Speelflod Reporting Period '
j ETS-10 Page:1 06/21/93 1
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COMPARISON OF WEKLY SCRAM STAT!STICS WITN INDUSTRY AVERAGES PERICD ENDING 06/20/93 NUMBER 1993 1992 1991*
1990*
1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAW CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER TMAN OR EQUAL TO 15%
j EQUlPMENT FAILURE
- 3 2.0 2.6 2.9 3.4 3.1 LESIGNil biALLATION ERROR
- 0 0.1 OPERATING ERROR
- 0 0.4 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
- 0 0.5 0.4 i
EXTERNAL
- 0 0.2 CTHER*
0 0.0 0.2 0.1 Subtotal 3
3.2 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EQUlPMENT FAILURE
- 0 0.5 0.4 0.3 0.4 0.3 DESIGN /INSTALLAfl0N ERROR
- 0 0.0 OPERATING ERROR
- 0 0.2 0.1 0.2 0.1 0.3 MAINTENANCE ERROR
- 0 0.0 0.1 EXTERNAL
- 0 0.0 CThER*
0 0.0 0.1 Subtotal 0
0.7 0.7 0.5 0.5 0.6 TOTAL 3
3.9 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 Wo. OF WEEKLY WEEKLT WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERACE AVERAGE (YTD)
TOTAL AlJTOMATIC SCRAMS 3
2.6 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 0
1.2 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF
- Detalled breekdown not in detsbase for 1991 ord earlier EXTERNAL cause included in EQUIPMENT FAILURE MAINTENANCE ERROR and DESIGN /lWSTALLATION ERROR causes included in CPERATING ERROR OTHER cause incitded in EQUIPMENT FAILURE 1991 and 1990 ETS 15 Pages 1 06/21/93
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,v ESTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 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.
PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCELURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
3.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAICTRES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
4.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and AutomatAc Scrans for 1988 ------------------ 291 Manual and Automatic Scrams for 19 8 9 ------------- - ---- 2 5 2 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 06/20/93)-- 93
ENCLOSURE 4 OPERATIN2 REACTOR PLANT 3 GICNIFICANT EVENT 3 SORT > Event Date QUERY > Event Type SIG & Close Out Date >= 06/01/93 & Close Out Date <= 06/22/93 & Event Type * "SIG"
' PLANT 8 UNIT R DESCRIPTION OF EVENT SIGNIFICANCE BRI ING PRESENTER N
4 PILGRI:3 1 09/02/901927D MALFUNCTION OF FEEDWATER REGULATING SYSTEM AND 90-22 HUNEMULLER N.
NIGHLIGHT RCIC FAILURE.
PERRY 1 01/16/93 25415 TWO RNR SUCT!ON STRAINERS WERE FDJND TO HAVE Safety-Reteted Cooling System 93-14 CARTER J.
EFR 93-024 COLLECTED DE8Ris, AFTER THEY WERE CLEANED, THE LICENSEE OBSERVED THAT THE CONICALLY SHAPED STRAINERS MAD SEEN DEFORMED,1 MAD CRACKS.
- INDIAN POINT 3 03/18/93: 0 ENTERING INTO AND OPERATING AT MID-LOOP WITHOUT Safety-Related Cooling System 93-18 KOSHY T.
HIGHLIGHT FUNCTIONAL LEVEL INDICATION.
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- ~ Previously-identified as a.Significant Event in. Briefing Package 93-22.
ETS-11 Page:1 06/24/93
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