ML20035C646
| ML20035C646 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick, River Bend  |
| Issue date: | 03/26/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-011, OREM-93-11, NUDOCS 9304080236 | |
| Download: ML20035C646 (15) | |
Text
e i
MAR 2 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 MARCH 24, 1993 - BRIEFING 93-11 L
On March 24, 1993, we conducted an Operating Reactors Events Briefing (93-11) to inform senior managers from offices of the SECY, RES, ACRS, AEOD, NRR, OE, and regional offices of selected events that occurred since our last briefing on March 17, 1993. lists the attendees. presents the significant elements of.the discussed events.
, contains reactor scram statistics for the week ending March 21, 1993.
No significant events.were identified for input into the NRC-performance indicator program.
- original signed by Robert L. Dennig for -
l Alfred E.
Chaffee, Chief
~
Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated
_ DISTRIBUTION:
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OFFICIAL RECORD COPY DOCUMENT NAME:
ORTRANS.KAG (G:KAG) 9304000236 930326 bCCM/ BAT I
PDR ORG NPRB
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PDR amWITCGilIORY CBi!1MIES cp
4 cc:
T. Murley, NRR (12G18)
B. McCabe (PDI-1)
F. Miraglia, NRR (12G18)
R.
Capra (PDI-1)
F. Gillespie, NRR (12G18)
E. Baker (PDIV-2)
J.
Partlow, NRR (12G18)
S. Black (PDIV-2)
S. Varga, NRR (14E4)
J. Calvo, NRR (14A4)
G.
Lainas, NRR (14H3)
J. Roe, NRR (13E4)
J.
Zwolinski, NRR (13H24)
M. Virgilio, 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)
T. Novak, AEOD (MN-9112)
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)
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 B. Davis, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV J.B. Martin, 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
.i
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-11)
MARCH 24, 1993 NAME OFFICE NAME OFFICE B.
DENNIG NRR W.
LEFAVE NRR J.
CARTER NRR G.
ZECH NRR D.
SKEEN NRR J.
ROE NRR K.
GRAY NRR C.
VARGA NRR J.
MENNING NRR D.
)
R.
CAPRA NRR V.
BENAROYA AEOD i
C.
MOON NRR W.
TROSKOSKI OE i
S.
ROSENBERG NRR K. HART SECY
{
S.
BLACK NRR W.
MINNERS RES J.
TATUM NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Recions Resident Inspectors Region I Fitzpatrick Region II Region III Region IV Region V IIT/AIT Team Leaders Jiisc.
Technical Training Center i
{
s
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 93-11 LOCATION:
10 B11, WHITE FLINT WEDNESDAY, MARCH 24, 1993, 11:00 A.M.
FITZPATRICK LOW INTAKE LEVEL RESULTS IN MANUAL REACTOR SCRAM RIVER BEND BOTH CONTAINMENT AIR LOCK D0 ORS OPENED
'l PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR
93-11 FITZPATRICK LOW INTAKE LEVEL RESULTS IN MANUAL REACTOR SCRAM FEBRUARY 25, 1993 PROBLEM A PARTIAL BLOCKAGE OF THE LAKE INTAKE STRUCTURE RESULTED IN A LOW LEVEL IN THE PLANT INTAKE SCREENWELL AND CAUSED OPERATORS TO MANUALLY SCRAM THE REACTOR.
CAUSE THE BLOCKAGE WAS APPARENTLY DUE TO FRAZIL ICE BUILD UP AT THE INTAKE STRUCTURE.
SAFETY SIGNIFICANCE j
LOW SCREENWELL LEVEL COULD RESULT IN INOPERABLE SAFETY i
RELATED EQUIPMENT DUE TO LOSS OF SUCTION TO EMERGENCY SERVICE WATER (ESW) AND RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) PUMPS.
DISCUSSION e
01:25 - DURING A PERIOD OF EXTREMELY COLD WEATHER, WITH THE PLANT AT 100% POWER, THE CONTROL ROOM RECEIVED INDICATIONS THAT THE ELECTRIC FIRE PUMP HAD STARTED.
THE PUMP WAS SECURED AFTER VERIFYING ADEQUATE SYSTEM PRESSURE.
CONTACTS:
D. SKEEN, NRR/0EAB AIT:
N0 B. MCCABE, NRR/PDI-1 SIGEVENT:
NO
REFERENCES:
10 CFR 50.72 #25130 AND PN19313
FITZPATRICK 93-11 e
01:30 - OPERATORS NOTICED AN INCREASE IN SCREENWELL TEMPERATURE AND INCREASED CW PUMP CURRENT.
THE ELECTRIC FIRE PUMP STARTED A SECOND TIME.
e 01:32 - AN OPERATOR WAS DISPATCHED TO THE SCREENWELL PUMPHOUSE.
e 01:35 - DIESEL FIRE PUMPS AUT0 STARTED.
OPERATORS REDUCED POWER T0 70%
e 01:38 - ONE OF THREE CW PUMPS WAS SECURED.
e 01:40 - OPERATOR AT THE SCREENWELL PUMPHOUSE REPORTED THAT SCREENWELL LEVEL WAS 10 FT BELOW NORMAL.
THE REACTOR WAS MANUALLY SCRAMMED.
02:10 - SCREENWELL TEMPERATURE WAS NORMAL AND LEVEL HAD e
INCREASED BY FOUR FEET.
e 02:13 - A SECOND CW PUMP WAS SECURED AND SCREENWELL LEVEL RETURNED TO WITHIN ONE FOOT OF NORMAL WITHIN A FEW MINUTES.
FOLLOWUP FRIDAY, FEBRUARY 26 - A BOAT ATTEMPTED TO TAKE DIVERS e
OUT TO THE INTAKE STRUCTURE BUT COULD NOT GET OUT OF THE HARBOR DUE TO ICE ON THE LAKE.
j SATURDAY, FEBRUARY 27 - A ROBOTIC CAMERA WAS USED TO e
CHECK OUT THE INTAKE TUNNEL AND INTAKE STRUCTURE.
NO BLOCKAGE WAS FOUND.
FITZPATRICK 93-11 e
WEDNESDAY, MARCH 3 - WITH LOCAL TEMPERATURES MODERATING, DIVERS WERE ABLE TO INSPECT THE LAKE INTAKE STRUCTURE.
N0 BLOCKAGE WAS FOUND.
e SUBSEQUENT TO THIS EVENT, THE LICENSEE DEVELOPED A PROCEDURE TO DEAL WITH LOW SCREENWELL LEVEL AND INSTALLED LEVEL INDICATORS.
A SIMILAR LOSS OF CW SUCTION EVENT OCCURRED ON 10/19/90, WHEN THE INTAKE TRAVELING SCREENS BECAME CLOGGED WITH DEBRIS (LER 90-023).
e GINNA EXPERIENCED AN ICE BLOCKAGE EVENT IN 1984.
e PLANT SYSTEMS BRANCH IS CURRENTLY REVIEWING INTAKE LEVEL PROBLEMS AS PART OF GENERIC ISSUE 153 IN LIGHT OF AN EVENT AT NINE MILE POINT 1 IN FEBRUARY 1992 AND HAS BEEN MADE AWARE OF THIS EVENT.
BRIEFING 93-11 FITZPATRICK FIGURE 1 FITZPATRICK SCREENWELL LEVELS 248 ft l-----
LAKE LEVEL DURING EVENT 247 l
t 246 l
l 245 l-----
FSAR NORMAL LAKE LEVEL l
244 l-----
FSAR MINIMUM LAKE LEVEL i
243 l
242 l
1 241 l
l 240 ll-----
239.5 - MINIMUM WATER LEVEL FOR ELECTRIC & DIESEL 239 i
FIRE PUMPS I
238 l.
l 237 l-----
FIRE SYSTEM JOCKEY PUMP SUCTION STRAINER l----- 236.5 - FSAR SCREENWELL DESIGN LOW LEVEL 236 l
l l-----
235.5 - CIRC WATER & DSL FIRE PUMP SUCTION STRAINERS 235 l----- MINIMUM WATER LEVEL FOR ESW/RHRSW l
I 234 l-----
ELECTRIC FIRE PUMP SUCTION STRAINER I
~
233 l
l 232 l-----
ESW/RHRSW SUCTION STRAINER l
231 l
l 230 l
225 l
I 224 l
l 223 ll----- 222.5 - SERVICE WATER SUCTION STRAINER 222 l
l 221 l
BOTTOM 0F SCREENWELL
4 BRIEFING 93-11 FITZPATRICK FIGURE 2 - FITZPATRICK INTAKE STRUCTURE m.f y V 1
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93-11 RIVER BEND BOTH CONTAINMENT AIR LOCK DOORS OPENED FEBRUARY 25, 1993 l
PROBLEM WHILE THE REACTOR WAS OPERATING AT 100% POWER, THE SECOND CONTAINMENT AIRLOCK D0OR WAS OPEN WITHOUT PROPER CLOSURE OF THE FIRST D0OR.
CAUSE THERE WAS N0 OPERABLE FEATURE TO DETECT D00R " CLOSURE."
l l
SAFETY SIGNIFICANCE PRIMARY CONTAINMENT WAS NOT MAINTAINED WHEN REQUIRED.
DISCUSSION e
REACTOR WAS BEING OPERATED AT 100% POWER.
ON SEPARATE OCCASIONS, AND BY DIFFERENT PEOPLE, BOTH e
AIRLOCK D0 ORS WERE OPEN (BEING OPENED) AT THE SAME TIME.
D0 ORS HAVE MECHANICAL AND ELECTRICAL INTERLOCKS:
MECHANICAL INTERLOCK WAS WORKING ELECTRICAL INTERLOCK HAD NOT BEEN WORKING, NOR WAS IT " REQUIRED" LICENSEE DID NOT BELIEVE NECESSARY FOR PROPER OPERATION CONTACT:
J. CARTER, NRR/0EAB AIT:
NO
REFERENCE:
10 CFR 50.72 #25195 SIGEVENT:
TBD I
RIVER BEND 93-11 e
MECHANICAL INTERLOCK IS ATTACHED TO HAND WHEELS LOCATED ON BOTH D0 ORS:
HANDWHEEL IN OPEN POSITION ON OPEN DOOR PREVENTS OPERATION OF HANDWHEEL ON CLOSED D00R INFLATES / DEFLATES PNEUMATIC BOOT SEAL BETWEEN D0OR AND FRAME ON TWO OCCASIONS, OUTER D0OR WAS NOT FULLY CLOSED:
e HANDWHEEL ON OUTER D00R WAS TURNED TO CLOSED POSITION, THEREBY PERMITTING OTHER D00R HANDWHEEL TO BE TURNED: PERMITS D00R TO BE OPENED e
ON ONE OCCASION, SAME PERSON OPENED BOTH D0 ORS.
ON SECOND OCCASION, PEOPLE EXITING CONTAINMENT STARTED e
TO OPEN INNER D00R WITH A PERSON INSIDE THE AIRLOCK AND THE OUTER DOOR OPEN.
e CONTAINMENT WAS PROMPTLY ESTABLISHED BY CLOSING THE INNER D00R.
e ELECTRICAL INTERLOCK HAS MULTIFUNCTIONS:
DETECTS D00R CLOSED /NOT CLOSED PREVENTS OPENING D00R WITH PRESSURE DIFFERENTIAL e
CONCERN EXISTED THAT SINGLE FAILURE COULD PREVENT EXIT FROM CONTAINMENT:
ELECTRICAL INTERLOCK DISABLED e
AIRLOCK INTERLOCK CONTROLS PROVIDED BY "W. J. WOOLEY."
4 RIVER BEND 93-11 PERRY AND SOUTH TEXAS NAVE SAME OPERATING AIRLOCKS AS RIVER BEND.
F0LLOWUP e
LICENSEE IS CONTINUING TO INVESTIGATE AND EVALUATE NEED FOR CORRECTIVE ACTION.
PROJECTS AND TECHNICAL STAFF ARE FOLLOWING LICENSEE ACTIONS.
e AN INFORMATION NOTICE MAY BE ISSUED.
1 e
I
I
~
ENCLOSURE 3 l
REACTOR SCRAM
. e
Reporting Feriod: 03/15/93 to 03/21/93 YTD YTD ABOVE BELOW YTD g
PLAWT 8 Uwit POWER TYPi
[AQS1 COMDLICATIONS j ,UJ LOlAL C3/16/93 HATCH 1 38 sM Equipment failure WO 1 0 1 C3/16/93 SALEM 2 100 SA Equipnent Failure WO 2 0 2 i NOTES 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE PERIOD OF INTEREST. 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. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM. 3. SA = Scram Automatic; SM = Scram Manual OEAB SCRAM DATA Manual and Automatic Scrans for 1987 ------------------ 435 Manual and Automatic Scrans for 1988 ------------------ 291 Manual and Automatic Scrans for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrans for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 03/21/93)-- 52 1 1 l acte: Year lo Date (YTD) lotels Include Events Within The Calendar Year indicated By The End Cate of The specified Reporting Feriod ETS 10 page:S 03/25/93 .3
s COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERACES d PERIDD ENDING 03/21/93 i NUMSER 1993 1992 1991* 1990* 1989* OF VEE KLY bEEKLY WEEKLY WEEKLY WEEKLY SCEAN CAUSE SCRAMS AVERACE AVERA0E AVERACE AVERAGE AVERACE (YTD) FDWER GREATER THAN OR EQUAL TO 15% EDU!PMENT FA! LURE
- 2 2.6 2.6 2.9 3.4 3.1 CES!Ch/ INSTALLATION ERROR
- O 0.2 OPERATINO ERROR
- 0 0.4 0.2 0.6 0.5 1.0 MAINTEhAAE ERROR
- 0 0.7 0.4 EXTERNAL
- 0 0.3 OTHER*
O 0.0 0.2 0.1 Sabtetet 2 4.2 3.4 3.5 3.9 4.2 POWER LESS THAN 15% EOUIPMENT FAILURE
- 0 0.3 0.4 0.3 0.4 0.3 cESIGN/INSTALLATICA ERROR
- O 0.0 OPERATik0 ERROR
- O 0.2 0.1 0.2 0.1 0.3 MAINTEAANCE ERROR
- O 0.0 0.1 EXTERNAL
- 0 0.0 OTHER*
O 0.0 0.1 Ssbtotal 0 0.5 0.7 0.5 0.5 0.6 TOTAL 2 4.7 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 h0. OF WEEKLY WEEKLY WEEKLY WEEKLY bEEKLV SCDiv TfDE SCRAMS A VE R ACE A VE R ACE AVE R A0E AVE R ACE AVERA0E (YTD) TOTAL AUTDMATIC 5: RAMS 1 3.3 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 EECAU!E OF POUN0th0 CFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause included in EQUIPMENT FAILURE - MAINTIAANCE [PROR and DESIGN /thSTALLATION ERROR causes included in OPERATING ERROR - CTPER cause included in EQUIPMENT FAILURE 1991 and 1990 ETS 14 Page: 1 03/25/93}}