ML20057A026
| ML20057A026 | |
| Person / Time | |
|---|---|
| Issue date: | 07/09/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309100303 | |
| Download: ML20057A026 (11) | |
Text
'
O O
July 9, 1993 i
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 30, 1993 - BRIEFING 93-24 On June 30, 1993, we conducted an Operating Reactors Events Briefing (93-24) to inform senior man,1gers from offices of the Commission, NRR, AEOD, ACRS, and regional offices of selected events that occurred since our last briefing on June 23, 1993, i lists the attendees. presents the significant elements of the discussed events.
l contains reactor scram statistics for the week ending
[
June 27, 1993.
No significant events were identified for input into the NRC performance indicator program.
r Robert Dennig Alfred E.
Chaffee, Chief jfgpf Events Assessment Branch Division of Operating i
Reactor Support
Enclosures:
As stated DISTRIBUTION-CentraEFilesA cc w/ enclosures:
PDR See next page LKilgore, SECY EAB R/F KGray RDennig EGoodwin j
DSkeen EBenner l
i
/ ()r N
DO }S B/ DORS EAB/ DORS E
- ){D p 'h k L U $$d$Ipy g &p m y
- g g re m m Prd kh&
3C il KGra EGoodwin Achaffee 07/g /93 07/]/93 07/
/93 h 'f k} b j
)
~
4f /j !a/
O r
p OFFICIAL RECORD COPY l
DOCUMENT NAME:
ORTRANS.KAG (G:KAG) 9309100303 930709 l
l l
PDR ORG NRRB sh
^
l
\\
PDR r
j a
l l
O O
[,
,, ?g i
UNITED STATES l
f 't e e f i E NUCLEAR REGULATORY COMMISSION
(.{T j
WASHINGTON. D.C. 20555-0001 s'
e July 9, 1993 MEMORANDUM FOR:
Brian K.
Grimes, Director Division of Operating Reactor Support FROM:
Alfred E. Chaffee, Chief i
Events Assessment Branch Division of Operating Reactor Support l
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING JUNE 30, 1993 - BRIEFING 93-24 On June 30, 1993, we conducted an Operating Reactors Events Briefing (93-24) to inform senior managers from offices of the Commission, NRR, AEOD, ACRS, and regional offices of selected events that occurred since our last briefing on June 23, 1993.
- lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending June 27, 1993.
No significant events were identified for input into the NRC performance indicator program.
t
~--
y Alfred E. Chaffee, Chie 7 Events Assessment Brandh Division of Operating i
Reactor Support
Enclosures:
As stated l
cc w/ enclosures:
1 See next page
m o
o cc:
T. Murley, ARR (12G18)
J. Stone (PDI-2)
F. Miraglia, NRR (12G18)
C. Miller (PDI-2)
F. Gillespie, NRR (12G18)
J. Partlow, NRR (12G18)
S. Varga, NRR (14E4)
J.
Calvo, NRR (14A4)
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)
A.
Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin, Region I W.
Kane, Region I C.
Hehl, Region I S.
Ebneter, Eagion 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
o o
ENCLOSURE 1 LIST OF ATTENDEES l
OPERATING REACTORS EVENTS FULL BRIEFING (93-24)
JUNE 30, 1993 NAME OFFICE IMtig OFFICE i
A.
CHAFFEE NRR J.
ZIMMERMAN NRR i
E. BENNER NRR T.
CHAN NRR B. GRIMES NRR A. THADANI NRR J.
PARTLOW NRR R.
CROTEAU NRR M. VIRGILIO NRR J.
WIGGINS NRR l
S.
ROSENBERG NRR A. JOHNSON NRR 1
S.
WITTENBERG NRR W.
COLLINS NRR A. BYRDSONG NRR V.
BENAROYA AEOD N.
CAMPBELL NRR D.
M.
CHATTERTON NRR M.
LEACH OCM/IS A. CALVO NRR TELEPHONE ATTEh0ANCE (AT ROLL CALL)
)
Reaions Resident Inspectors l
Region I Ginna j
Region II i
Region III Region IV Region V l
IIT/AIT Team Leaders Misc.
W. Ruland (Salem) l t
l r
l
I Q
Q l
OPERATING REACTORS EVENTS BRIEFING 93-24 LOCATION:
10 B11, WHITE FLINT WEDNESDAY, JUNE 30, 1993, 11:00 A.M.
l l
SALEM, UNIT 2 R0D CONTROL SYSTEM SINGLE FAILURE POTENTIAL (AIT UPDATE) l 1
1 PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR
.i.-
o o
b 93-24 l
SALEM, UNIT 2 i
R0D CONTROL SYSTEM SINGLE l
FAILURE POTENTIAL (AIT UPDATE)
JUNE 6, 1993 PROBLEM i
SINGLE FAILURE IN THE R0D CONTROL SYSTEM COULD RESULT IN i
WITHDRAWAL OF ONE OR MORE RODS IN A GROUP WHEN THE GROUP l
IS GIVEN AN INSERT SIGNAL.
l CAUSE l~~DESIGNWEAKNESS.
~~
1 i
j SAFETY SIGNIFICANCE l
R0D WITHDRAWAL OF THIS NATURE MAY RESULT IN EXCEEDING FUEL j
DESIGN LIMITS AND LOCALIZED FUEL DAMAGE.
i DISCUSSION (MAY 27, 1993) i o SHUTDOWN BANK A WITHDRAWN, NO R0D MOVEMENT INDICATED ON l
ANALOG R0D POSITION INDICATION (ARPI) WITH GROUP DEMAND l
INDICATION AT 20 STEPS.
i l
o RODS INSERTED TO 6 STEPS ON GROUP DEMAND INDICATION, j
R0D ISA3 OBSERVED INDICATING 8 STEPS ON ARPI.
i
}
o RODS INSERTED TO ZERO STEPS ON GROUP DEMAND INDICATION, j
R0D ISA3 INDICATING 15 STEPS ON ARPI.
j CONTACTS:
E. BENNER, NRR/ DORS AIT:
YES l
W. RULAND, REGION I/DRS SIGEVENT:
TBD l
REFERENCES:
10 CFR 50.72 #25609, 25585 AND l
PN19330 i
e i
1 a.
l-o o
l!-
SALEM, UNIT 2 93-24 e LICENSEE REMOVED POWER FROM STATIONARY GRIPPER TO INSERT R0D ISA3.
i e LICENSEE FOUND AND REPLACED TWO DEFECTIVE SLAVE CYCLER CARDS.
DAMAGE TO CARDS IS BELIEVED TO BE ASSOCIATED WITH MECHANICAL COUNTER BACK EMF.
i FOLLOWUP PUBLIC SERVICE ELECTRIC AND GAS ACTIONS:
)
e SUBMITTED REQUEST FOR LICENSE AMENDMENT TO ADDRESS i
~~
{
SINGLE FAILURE CONCERN.
- R0D CONTROL SYSTEM MAINTAINED IN MANUAL ONLY BELOW i
15% POWER.
- NO CHANGE IN R0D INSERTION LIMIT.
- PERFORM CURRENT TRACES ON R0D CONTROL SYSTEM PRIOR TO EACH STARTUP.
e INCREASED SURVEILLANCE TESTING.
I e FINAL APPROACH TO CRITICALITY TO BE DONE BY DILUTION l
VERSUS RODS.
- ESTABLISHED IMPROVED PRACTICES FOR CARD REMOVAL / INSTALLATION.
e INSTALLATION OF SUPPRESSION DIODES FOR BOTH UNITS.
e IMPLEMENT STATIC CHARGE GUARD HANDLING GUIDANCE.
l e CHANGE MECHANICAL STEP COUNTERS TO DIGITAL ELECTRONIC l
STEP COUNTERS.
l l
l l
l' O
O
- j-SALEM, UNIT 2 93-24
)
i e UNIT 2 ATTAINED CRITICALITY ON JUNE 28, 1993.
l
}
NUCLEAR REGULATORY COMMISSION GENERIC ACTIONS:
l e CONTACTED REGULATORY RESPONSE GROUP 0F THE WESTINGHOUSE l
OWNER'S GROUP ON JUNE 8, 1993.
I j
e INFORMATION NOTICE 93-46, "P0TENTIAL PROBLEM WITH WESTINGHOUSE R0D CONTROL SYSTEM AND INADVERTENT j
WITHDRAWAL OF A SINGLE R0D CONTROL CLUSTER ASSEMBLY,"
ISSUED.
DISCUSSES DETAILS OF SALEM EVENT AND SHORT
~'
~
TERM ACTIONS TAKEN BY LICENSEE.
- INTERIM INSTRUCTIONS TO PROJECT MANAGERS TO CONFIRM THE j
PERFORMANCE OF ACTIONS 1, 2, AND 4 0F A JUNE 11, 1993, i
WESTINGHOUSE NUCLEAR SAFETY ADVISORY LETTER ON R0D CONTROL SYSTEM FAILURE, PRIOR TO RESTART.
ACTIONS 1, j
2, AND 4 ARE AS FOLLOWS:
i LICENSED OPERATORS SHOULD CONTINUE NORMAL PROCESS i
0F VERIFYING THAT R0D MOTION IS PROPER FOR REQUIRED i
MOVEMENT.
l LICENSEES SHOULD CONFIRM THE FUNCTIONALITY OF R0D DEVIATION ALARMS.
OPERATORS SHOULD REVIEW THIS TRANSMITTAL TO ENSURE
]
THEIR UNDERSTANDING OF THE EVENT.
e GENERIC LETTER 93-04, " ROD CONTROL SYSTEM FAILURE AND WITHDRAWAL OF A R0D CONTROL CLUSTER ASSEMBLY,"
DEVELOPED TO ALERT LICENSEES TO SUSCEPTIBILITY TO SALEM 3
j EVENT AND REQUIRE ASSESSMENT OF WHETHER OR NOT THEIR LICENSING BASIS IS STILL SATISFIED AND, IF NOT, WHAT i
COMPENSATORY ACTIONS ARE TO BE TAKEN.
4
!~
O O
i SALEM, UNIT 2 93-24 l
INP0:
i e SIGNIFICANT EVENT NOTIFICATION ISSUED.
RECENT SALEM EVENTS j
e WHILE PERFORMING MAINTENANCE ON JUNE 23, 1993, BLEW TWO TRANSISTORS THROUGH INCORRECT USE OF A JUMPER.
e LICENSEE RECEIVED URGENT FAILURE ALARM ON JUNE 25, l
l 1993.
i
- FOUND AN ORIGINAL EQUIPMENT RESISTOR WHICH WAS l~~
INCORRECT BY A FACTOR OF 10.
~~
i
- NRC IS ASSESSING THE NEED FOR AN ADDITIONAL l
INFORMATION NOTICE.
e ANALYSIS OF PREVIOUSLY FAILED CHIPS BY MOTOROLA REVEALED ELECTROSTATIC DISCHARGE DAMAGE.
l l
l e ON JUNE 29, 1993, THE LICENSEE FOUND THREE ARPIs FOR CONTROL BANK "B" INDICATING GREATER THAN TWELVE STEPS FROM DEMAND POSITION, ARPIs RECALIBRATED.
GINNA l
e ON JUNE 29, 1993, AT 9:00 P.M. WITH THE UNIT AT NEARLY l
FULL POWER, CONTROL R0D ERROR ALARM WAS RECEIVED.
l e R0D CONTROL SYSTEM CREATED A DEMAND SIGNAL, "V1" MOVED l
IN ONE DIRECTION WHILE "V2" MOVED IN THE OTHER DIRECTION.
e OPERATORS PLACED R0D CONTROL IN MANUAL TO HALT R0D i
MOTION.
l 1
(
,r3
\\
\\>
REACTDR SCRAM Reporting Period: 06/21/93 to 06/27/93 YTD YTD ABOVE BELOW YTD l
pf,T[
PLAWT E UNIT POWER YYPE CAUSE cos8PLICAT1(*S j.13 M
TOTAL 06/22/93 TURKEY PO!WT 4 35 SA Maintenance Error NO 1
0 1
06/24/93 FT CALHOUN 1 100 SA Maintenance Error NO 1
0 1
l 06/25/93 CALVERT CLIFFS 2 4
$A Operating Error NO O
2 2
l 06/26/93 CDMANCHE PEAK 1 100 SM Equipment Failure NO 3
0 3
e i
i i
1 i
i Ect2: Year To Date (YTD) Totals include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period ETS 10 Tage:1 07/07/93
l O
O I
COMPAR150N OF WEEKLY SCRAR STATIS11CS WITH INDUSTRY AVERAGES i
i PERIOD ENDlWG 06/27/93 1
l j
NUMBER 1993 1992 1991*
1990*
1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY WEKLY SCRAN CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER TRAN OR EQUAL 1015%
EQUIPMENT FAILURE
- 1 2.0 2.6 2.9 3.4 3.1 l
l OESIGN/ INSTALLATION ERROR
- 0 0.1
}
OPERATIhG ERROR
- 0 0.4 0.2 0.6 0.5 1.0 MAINTEkANCE ERROR
- 2 0.6 0.4 o
EXTERNAL
- O 0.2 l
OTHER*
0 0.0 0.2 0.1
$ 2 total 3
3.3 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
I I
EQUIPMENT FAILURE
- 0 0.5 0.4 0.3 0.4 0.3
)
DESIGN / INSTALLATION ERROR
- 0 0.0 OPERATING ERROR
- 1 0.2 0.1 0.2 0.1 0.3
}
MAINTENANCE ERROR
- O 0.0 0.1 EXTERkAL*
0 0.0 r
OTHER*
O 0.0 0.1 1
Subtotal 1
0.7 0.7 0.5 0.5 0.6 l
I
(
TOTAL 4
4.0 4.1 4.0 4.4 4.8 i
i l
l 1993 1997 1991 1990 1989 kO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCPAM TYPE SCRAMS AVERAGE AVERAGE-AVERAGE AVERAGE AVERAGE (YTD) l ToiAL AUTOMATIC SCRAMS 3
2.6 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 1
1.2 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF
- Detailed breakdown not in database for 1991 and earlier
- EKTERNAL cause included in EQUIPMENT FAILURE
- MAINTENANCE ERROR and DESIGN /INSTALLAT!DN ERROR causes included in OPERATING ERROR
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 l
I i
l ETS-15 Page: 1 07/07/93-
...