ML20034G659
| ML20034G659 | |
| Person / Time | |
|---|---|
| Issue date: | 02/19/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-006, OREM-93-6, NUDOCS 9303100338 | |
| Download: ML20034G659 (13) | |
Text
l FEB 191993 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 FEBRUARY 17, 1993 - BRIEFING 93-06 On February 17, 1993, we conducted an Operating Reactors Events Briefing (93-06) to inform senior managers from offices of the Commission, RES, NRR, and regional offices of selected events i
that occurred since our last briefing on February 10, 1993. lists the attendees. presents the significant elements of the discussed event. contains reactor scram statistics for the week ending February 14, 1993.
One significant event was identified for input into the NRC performance indicator program (Enclosure 4).
original signed by Robert L. Dennig for Alfred E.
Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated DISTRIBUTION:
vCentral?Filess cc w/ attachments:
PDR See next page EAB R/F KCray RDennig LKilgore, SECY hthNE.%1RMOGMEL SWest, NRR
/
hfDRS b
EA O
kg{ Gray R
nnig AC aff
{/f/93 J /li /93 J /f7/93 OFFICIAL RECORD COPY DOCUMENT NAME:
ORTRANS.KAG (G:KAG)
RETURN 10 REGULATORY CENTRA
_ FILES 19 9303100339 7 f; cf [{.,/
PDR ORG ppg
- _.u i
A fwu,A r
/
i 1
1 1
^f w*
1 cc:
T. Murley, NRR (12G18) 1 F. Miraglia, NRR (12G18)
F.
Gillespie, NRR (12G18)
J.
Partlow, NRR (12G18) i S.
Varga, NRR (14E4) l J.
Calvo, NRR (14A4)
G.
Lainas, NRR (14H3) j J.
Roe, NRR (13E4)
J.
Zwolinski, NRR (13H24)
M. Virgilio, NRR (13E4) i W.
Russell, NRR (12G18)
J.
Richardson, NRR (7D26)
A. Thadani, NRR (8E2).
S.
Rosenberg, NRR (10E4) l C.
Rossi, NRR (9A2)
B.
Boger, NRR (10H3)
F.
Congel, NRR (10E2)
D.
Crutchfield, NRR (11H21) l W.
Travers, NRR (11B19)
D.
Coe, ACRS (P-315) i E.
Jordan, AEOD (MN-3701) i T.
Novak, AEOD (MN-9112) l L.
Spessard, AEOD (MN-3701)
K.
Brockman, AEOD (MN-3206)
S.
Rubin, AEOD (MN-5219)
M.
Harper, AEOD (MN-9112)
J.
Grant, EDO (17G21)
R. Newlin, GPA (2GS) i 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 i
E. Merschoff, Region II B.
Davis, Region III E. Greenman, Region III J. Milhoan, Region IV i
B.
Beach, Region IV
}
J.B. Martin, Region V i
K. Perkins, Region V j
bcc: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations i
1100 Circle 75 Parkway, suite 1500 Atlanta, GA 30339-3064 i
i i
i I
. _.. =.
}
.f
~. '
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-06)
FEBRUARY 17, 1993 NAME OFFICE NAME OFFICE I
B. GRIMES NRR R.
ARCHITZ2L NRR A.
CHAFFEE NRR E.
FOX NRR S.
WEST NRR R.
KIESSEL NRR D.
SKEEN NRR T.
ZECH NRR S.
BAJWA NRR F.
MIRAGLIA NRR
)
J. STANG NRR M.
VIRGILIO NRR l
S. ROSENBERG NRR J.
KENNEDY OCM W.
HAASS NRR N. JENSEN OCM/GD R.
EMCH NRR R. WOODS RES A. MASCIANTONIO NRR L.
BENBOUSKIY UKRAINE i
R. JENKINS NRR N.
BERKOFF DEPT. OF STATE (INTERPRETER)
)
TELEPHONE ATTENDANCE (AT ROLL CALL)
Recions Resident Inspectors i
i Region III Region IV Region V IIT/AIT Team Leaders Misc.
i
~
J l
[
s
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 93-06 LOCATION:
10 B11, WHITE FLINT WEDNESDAY, FEBRUARY 17, 1993, 11:00 A.M.
CURRENT ISSUES - THERM 0 LAG K. STEVEN WEST, NRR I
l PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR 9
4 d
THERMO-LAG 330-1 FIRE BARRIER SYSTEM TECHNICAL ISSUES AND NRC ACTIONS STEVEN WEST, SPLB/NRR February 17,1993
_2.,_._
TECHNICAL ISSUES
- FIRE ENDURANCE TESTING AND THE APPLICATION OF THE TEST RESULTS.
- AMPACITY DERATING TESTING AND THE APPLICATION OF THE TEST RESULTS.
- FIRE BARRIER INSTALLATION AND INSPECTION DEFICIENCIES.
- COMBUSTIBILITY OF FIRE BARRIER MATERIAL.
SAFETY SIGNIFICANCE OF THE NRC'S CONCERNS l
THE RELATIVE SAFETY SIGNIFICANCE IS LOW BECAUSE:
e TOTAL RELIANCE IS NOT PLACED ON THERMO-LAG.
" DEFENSE-IN-DEPTH" ENSURES THAT PLANTS ARE 1
EQUIPPED WITH OTHER PASSIVE AND ACTIVE FIRE PROTECTION FEATURES.
i e RECENT NRC AND INDUSTRY FIRE TESTS HAVE DEMONSTRATED THAT THERMO-LAG DOES PROVIDE SOME LEVEL OF FIRE PROTECTION.
e LICENSEES HAVE IMPLEMENTED MEASURES, SUCH AS FIRE WATCHES, TO COMPENSATE FOR INOPERABLE THERMO-LAG BARRIERS.
e THE AMPACITY DERATING ISSUE IS PRIMARILY A CABLE AGING ISSUE.
CABLE LIFE MAY BE REDUCED IF OPERATING TEMPERATURES ARE GREATER THAN DESIGN TEMPERATURES.
3
__ -=_-
NRC STAFF ACTIONS COMPLETED A SPECIAL REVIEW TEAM REPORT.
ISSUED TWO BULLETINS, FIVE INFORMATION NOTICES, AND A GENERIC LETTER.
DEVELOPED PROPOSED ACCEPTANCE CRITERIA FOR FIRE ENDURANCE TESTS.
REVIEWED AND APPROVED TEXAS UTILITIES THERMO-LAG PROGRAM FOR COMANCHE PEAK UNIT 2.
REVIEWING TVA'S THERMO-LAG PROGRAM FOR WATTS BAR.
REVIEWING NUMARC'S THERMO-LAG TESTING PROGRAM.
E l
NUMARC TEST PROGRAM e
NUMARC HAS COMMITTED TO CONDUCT A FIRE ENDURANCE AND AMPACITY DERATING TEST PROGRAM.
THE NUMARC PROGRAM WILL COVER A VARIETY OF CONFIGURATIONS CONSIDERED BY NUMARC TO BE MOST USEFUL TO INDUSTRY AS A WHOLE.
ADDITIONAL TESTS MAY BE REQUIRED BY SOME LICENSEES TO QUALIFY PLANT-SPECIFIC CONFIGURATIONS THAT ARE NOT BOUNDED BY THE NUMARC PROGRAM.
o
+
h
COMANCHE PEAK UNIT 2 TESTS e
TU ELECTRIC'S FIRE ENDURANCE TESTS FOR COMANCHE PEAK 2 SHOWED:
SOME THERMO-LAG BARRIER CONFIGURATIONS CANNOT ACHIEVE THEIR INTENDED FIRE RESISTANCE RATING WHEN INSTALLED IN ACCORDANCE WITH THE VENDOR'S RECOMMENDED INSTALLATION PROCEDURES.
SOME BARRIERS PASSED FIRE TESTS 'NHEN THE THICKNESS OF THE THERMO-LAG WAS INCREASED AND/OR THE BARRIER JOINTS WERE STRENGTHENED.
s
ENCLOSURE 3 REACTOR SCRAM Reporting Period: 02/08/93 to 02/14/93 YTD YTD ABOVE BELOW YTD E
PLANT & tfNii POUFR M
[A2SJ COMPL ICATIOWS 1),}
11}
191A.,L 02/09/93 suRRY 1 100 SA Equipment f at ture wo 2
0 2
02/10/93 WASHINCTOW NUCLEst 2 90 SA Ecpipment f at ture ho 3
0 3
NOTES PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR PERIOD OF INTEREST.
SCRAMS ARE DEFINED AS REACTOR PROTECTION SYSTEM ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE THOSE FROM PLANNED TESTS OR AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
SA - SCRAM AUTOMATIC; SM -' SCRAM MANUAL OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 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 02/14/93)-- 031 Cote: Year to Date (YTD} Totals Include Events Witt'in The Calender Year Irxficated By The End Date Of The Specified Reporting Perlo
.E15 10 Page:1 02/18/9 t
s-COMPARISON of WEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERICX) ENDlWG 02/08/93 to 02/14/93 NUMBER 1993 1992*
1991*
1990*
1989*
OF WEEKLY MEKLY WEEKLY WEEKLY WEEKLY SCRAM f:AUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (TTD)
POLTR GREATER THAN OR EcuAL TO 15%
EDulPMENT FAILURE
- 2 2.5 2.6 2.9 3.4 3.1 DE$1GN/lWSTALLAT]DN ERROR
- C 0.3 DPERATING ERROR
- O 0.3
.8 0.6 0.5 1.0 MAINTENANCE ERROR
- 0 0.9 EXTERNAL
- 0 0.2 (THER*
0 0.0 0.1 Subtotal 2
4.2 3.4 3.5 3.9 4.2 POWER LESS TMAN 15E EQUIPMENT FAILURE
- O p.3 0.4 0.3 0.4 0.3 DESIGN /lWSTALLATION ERROR
- 0 0.0 OPERATING ERROR
- 0 0.3 0.2 0.2 0.1 0.3 MAINTENANCE ERROR
- 0 0.0 EXTERNAL
- O 0.0 OThER*
0 0.0 Subtetat 0
0.6 0.6 0.5 0.5 0.6 TOTAL 2
4.8 4.0 4.0 4.4 4.8 1993 1992 1991 1990 1989 WO. OF WEEKLY WEEKLY W EKLY WEEKLY WEEKLY SCPAM TYPE SCRAMS AVERAGE AVE RAGE AVERAGE AVERAGE AVERAGE (TTD)
TOTAL AUTOMATIC SCRAMS 2
3.7 T.0 3.3 3.2 3.9 TOTAL MAWAL SCRAMS 0
1.1 1.0 0.7 1.2 0.9
- Detailed breakdwn not in database for 19Q and earlier EXTERNAL cause Incttded in EQUlPMENT FAILURE
- MAINTEkANCE ERROR and DESIGN /INSTALLAfl0N ERROR causes included in OPERATING ERROR
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 EXTERNAL CAUSE INCLUDES SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (EG LIGHTNING, LOSS OF 0FFSITE POWER)
ROUNDING OFF MAY RESULT IN A DIFFERENCE BETWEEN TOTALS.
39
/8 1
/2 O
0 4
L AM E
R E
R O
9 F
U N
S I
O L
C N
E R
E J
T W
R E
E S
T E
R R
A P
C G
N G
I 40 I
S S
I 3
R 9
T
=
B N
e E
py V
T E
t e
n c
e n
T v
a E
m N
r A
o f
C 3
r 9
e I
/
P F
2 1
t I
/
n 2
a N
0 l
G E
P e=
C I
t >
N d
a A
e B
D e C
t t
I c
t a F
e S
nD p
I e
N x
T vt G
e N
E u I
n o
S U
1 A
> e L
e T s g
P R o a
Ol P
SC E
R ST O
H O
A T
G T
C EOI E A
e R HCM p
OiES Ct P I E
y US L T
R R
B OSAA t
T Y T
n CA S
G e
A D.i v
N E
E S
R OS N I
WOE ET L E T
Y H
B R
A E
T SE R
V AH D.
O U
T A E R G H G E
H N F A
P T OON K L
0A O
W El E T
OSR f L N
LAA A E
F WR R V
YA UO E
G L GF F
I IBGI N
N F s O
L SI N V OSE Ot N
OOBCS CP P
O SG f
N R R N E P
WOOI H OF T T T I
D A A RC T T R R T S
USEE S E
H OP P E D
34 8
9
/
4 2
3 9
/
N 52
/
1 0
1 f
K i
E N
E U
R C
R 1
T E
1 N
T A
S S
L Y
T P
O E
.