ML20148D925
| ML20148D925 | |
| Person / Time | |
|---|---|
| Issue date: | 05/29/1997 |
| From: | Chaffee A NRC (Affiliation Not Assigned) |
| To: | Slosson M NRC (Affiliation Not Assigned) |
| References | |
| OREM-97-06, OREM-97-6, NUDOCS 9706020196 | |
| Download: ML20148D925 (12) | |
Text
.
e May 29, 1997 MEMORANDUM TO:
Marylee M. Slosson. Acting Director Division of Reactor Program Management FROM:
Alfred E. Chaffee. Chief l Original signed by l Events Assessment and Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 28. 1997 - BRIEFING 97-06 On May 28, 1997, we conducted an Operating Reactors Events Briefing (97-06) to inform senior managers from offices of the EDO, AE00. NRR and regional offices of selected events that occurred since our last briefing on May 21, 1997. lists the attendees. Attachment 2 presents the significant elements of the discussed events. contains reactor scram statistics for the week ending May 25.
1997.
No significant events were identified for input into the NRC Po *ormance Indicator Program.
The statements contained in the attached briefing slides represent the best information currently available to the NRC.
Future followup could produce new information that may alter the NRC's current view of the events discussed.
Attachments: As stated (3) cc w/atts:
See next page CONTACT:
Kathy Gray. NRR (301) 415-1166 DISTRIBUTION:
(w/atts)
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May 29, 1997 MEMORANDUM TO:
Marylee M. Slosson, Acting Director
)
Division of Reactor Program Management (lih f ( /
FROM:
Alfred E. Chaffee. Chief Events Assessment and Generic Communications Branch Division of Reactor Program Managemar.t
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 28, 1997 - BRIEFING 97-06 On May 28. 1997, we conducted an Operating Reactors Events Briefing (97-06) to inform senior managers from offices of the EDO, AEOD NRR and regional off1ces i
of selected events that occurred since our last briefing on May 21. 1997. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending May 25.
1997.
No significant events were identified for input into the NRC Performance Indicator Program.
l The statements contained in the attached' briefing slides represent the best information currently available to the NRC.
Future followup could produce new information that may alter the NRC's current view of the events discussed.
Attachments:
As stated (3) cc w/atts:
See next page CONTACT:
Kathy Gray. NRR (301) 415-1166 1
b cc:
S. Collins. NRR (0-12G18)
F. Miraglia. NRR (0-12G18)
R. Wharton NRR (013E17)
F. Gillespie. NRR (0-12G18)
W. Bateman NRR (013E17)
R. Zimmerman. NRR (0-12G18)
T. Martin. NRR (0-12G18)
B. Sheron. NRR (0-12G18)
S. Varga NRR (0-14E4)
J. Zwolinski, NRR (0-14H3)
-J. Roe. NRR (0-13E4)
E. Adensam. NRR (0-13E4)
G. Lainas. NRR (0-7026)
G. Holahan. NRR (0-8E2)
D. O'Neal. NRR (0-10E4)
B. Boger. NRR (0-9E4)
M. Markley. ACRS (T-2E26)
D. Ross. AEOC (T-4018)
C. Rossi AEOD (T-4A9) i F. Congel. AEOD (T-4D28)
R. Barrett. AEOD (T-4A43)
S. Rubin. AEOD (T-4028)
M. Harper. AEOD (T-4A9)
W. Leschek. AE00 (T-4A9) i V. McCree. EDO (0-17G21)
J. Gilliland. PA (0-2G4)
D. Morrison RES (T-10F12)
W. Hill. SECY (0-16G15)
H. Miller Region I C. Hehl Region I L. Reyes, Region II J. Johnson. Region II S. Vias. Region II A. Beach. Region III i
G. Grant. Region III E. Mershoff. Region IV P. Gwynn. Region IV K. Perkins. Region IV/WCF0 G. Fader. INP0 J. Zimmer. DOE
I LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (97-06)
MAY 28. 1997 NAME OFFICE NAME OFFICE A. Chaffee NRR M. Dapas OEDO T. Greene NRR C. Rossi AEOD K. Gray NRR S. Weiss NRR R. Dennig NRR J. Hannon NRR E. Goodwin NRR K. Parczewski NRR M. Cullingford NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Insoectors Region-I Region II Region III Region IV Misc.
Bill Johnston. Region IV Jeff Shackelford. Region IV ATTACHMENT 1
I OPERATING REACTORS EVENTS BRIEFING 97-06 i
l LOCATION:
0-10B11, WHITE FLINT WEDNESDAY, MAY 27, 1997 11:00 A.M.
I 4
FORT CALHOUN RUPTURE IN EXTRACTION STEAM LINE PRESENTED BY:
EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR ATTACHMENT 2
)
97-06 FORT CALHOUN RUPTURE IN EXTRACTION STEAM LINE l
APRIL 21, 1997 PROBLEM RUPTURE IN EXTRACTION STEAM LINE.
l CAUSE j
EXCESSIVE PIPE WALL THINNING IS BEING ATTRIBUTED TO FLOW-l l
ACCELERATED CORROSION (EROSION / CORROSION).
i
{
SAFETY SIGNIFICANCE l
RUPTURE OF PIPING LED TO UNNECESSARY PLANT TRANSIENT AND l
PERSONNEL HAZARD.
POSSIBLE GENERIC IMPLICATIONS j
ASSOCIATED WITH PREDICTIVE METHODOLOGY (CHECWORKS).
t l
DESCRIPTION OF EVENT l
o ON APRIL 21, 1997, WHILE OPERATING AT 100 PERCENT POWER, CONTROL ROOM OPERATORS HEARD A LOUD NOISE IN THE TURBINE BUILDING, FOLLOWED BY A VERY LOUD CONTINUOUS NOISE.
e THE OPERATORS CHECKED THE REACTOR INSTRUMENTATION AND NOTED NO ABNORMALITIES: THERE WERE NO CHANGES IN REACTOR COLD-LEG TEMPERATURE, STEAM GENERATOR PRESSURE, OR REACTOR POWER.
i CONTACT:
JEFFREY SHACKELFORD, REGION IV/DRS AIT: N0 l
TOM GREENE, NRR/DRPM/PECB l
REFERENCE:
10 CFR 50.72 #32193 SIGEVENT: TBD
FORT CALHOUN. 97-06 l
e WHEN THE SHIFT SUPERVISOR OPENED THE CONTROL D00R TO INVESTIGATE, HE SAW A LARGE AMOUNT OF STEAM FLOWING FROM THE GRATING IN THE TURBINE BUILDING.
THE REACTOR L
WAS MANUALLY TRIPPED WITHIN 19 SECONDS OF THE EVENT.
i e
THE OPERATOR REALIZING THAT THE PLANT MAY BE EXPERIENCING AN UNCONTROLLED HEAT EXTRACTION EVENT ENTERED THE PLANT EMERGENCY OPERATING PROCEDURES AND INITIATED EMERGENCY B0 RATION AS A PRECAUTIONARY MEASURE.
l e
DURING THE EVENT, THE FIRE SUPPRESSION SYSTEMS ACTUATED AND THERE WERE INTERMITTENT ELECTRICAL SYSTEM GROUNDS.
l e
APPR0XIMATELY 40 MINUTES INTO THE EVENT, THE OPERATORS ISOLATED THE FIRE PROTECTION SYSTEM.
e APPR0XIMATELY 52 MINUTES INTO THE EVENT, SHUTDOWN MARGIN WAS VERIFIED AND EMERGENCY B0 RATION WAS SECURED.
NO SAFETY SYSTEMS WERE AUTOMATICALLY ACTUATED.
DISCUSSION e
FT. CALHOUN EXPERIENCED A RUPTURE IN THE 12-INCH LINE THAT CONNECTS THE FOURTH STAGE OF THE HIGH PRESSURE TURBINE TO THE FEEDWATER HEATERS.
THE LINE IS FILLED WITH 92 PERCENT QUALITY STEAM AT 250 PSI AND 400 DEGREE FAHRENHEIT.
THE " FISH-MOUTH" RUPTURE OCCURRED AT THE OUTER EDGE OF A 5 FOOT RADIUS BEND AND WAS APPR0XIMATELY 54 INCH LONG AND 18 INCHES WIDE.
,p
FORT CALHOUN 97-06 o
THE RUPTURE BEND WAS NOT INCLUDED IN SITES INSPECTED BY j
l THE LICENSEE IN THE EROSION / CORROSION MONITORING l
PROGRAM.
THE LICENSEE USES THE "CHECWORKS" COMPUTER l
CODE AS A TOOL TO AID IN THE IDENTIFICATION OF SITES'TO l
BE INSPECTED.
THE CHECWORKS METHODOLOGY DID NOT l
PREDICT THE WEAR RATES WHICH WERE EXPERIENCED IN THE i
SYSTEM AND INDUSTRY-WIDE EXPERIENCE NOT INCORPORATED INTO THE EROSION / CORROSION PROGRAM (0CONEE IN 1982, SURRY IN 1986, TROJAN IN 1987, AND ARKANSAS IN 1989).
o THE'OVERALL OPERATOR RESPONSE TO THE EVENT WAS SUPERIOR.
THE OPERATORS ACTED IN A TIMELY, DECISIVE AND CONSERVATIVE MANNER.
I o
THERE WAS EXTENSIVE DAMAGE IN THE VICINITY OF THE RUPTURE.
THE BACK PANEL OF ONE NON-SAFETY MOTOR CONTROL CENTER (MCC) WAS DAMAGED DUE TO STEAM IMPINGEMENT.
INSULATION, CONTAINING ASBESTOS, WAS BLOWN THROUGHOUT THE TURBINE BUILDING.
NO PERSONNEL WERE IN THE VICINITY AT THE TIME OF THE RUPTURE.
o THE INTERMITTENT ELECTRICAL GROUNDS WERE OBSERVED ON TWO SAFETY-RELATED BUSES.
THESE GROUNDS WERE ATTRIBUTED TO GROUNDS ON TURBINE BUILDING MCCs WHICH ARE SUPPLIED BY THESE BUSES.
THESE BUSES ARE CONNECTED VIA CRITICAL QUALITY EQUIPMENT BREAKERS DESIGNED TO ISOLATE THE SAFETY BUSES IN THE EVENT OF GROUND FAULTS.
(FT. CALHOUN OPERATES AN UNGROUNDED ELECTRICAL SYSTEM).
l' FORT CALHOUN 97-06 l
FOLLOWUP o
NRC DISPATCHED A SPECIAL INSPECTION TEAM ON APRIL 23, j
1997, TO INVESTIGATE THE CAUSES AND CIRCUMSTANCES SURROUNDING THE EVENT.
A SPECIAL PUBLIC MEETING WAS i
CONDUCTED ON MAY 2, 1997, PRIOR TO RESTART.
i o
LICENSEE CONDUCTED EXTENSIVE WALKDOWN INSPECTIONS TO IDENTIFY AND ASSESS POTENTIAL DAMAGE TO PLANT EQUIPMENT.
o LICENSEE IMPLEMENTED MEASURES TO INCORPORATE INDUSTRY-WIDE OPERATING EXPERIENCE INTO THE EROSION / CORROSION PROGRAM.
o LICENSEE CONDUCTED EXTENSIVE FOLLOWUP ULTRASONIC TESTING OF OTHER LARGE RADIUS ELB0WS.
o NRC IS CONSIDERING THE NEED FOR AN INFORMATION NOTICE DISCUSSING THE ISSUES ASSOCIATED WITH CHECWORKS MODELLING PREDICTIONS.
b
. _ - _... ~.
., _ - - - - ~. - _ -..
.~. -..-. -... -..-
.. _.. _.. =. -... - -
i i
REACTOR SCRAN Reporting Period: 05/19/97 to 05/25/97 YTD YTD A80VE ELOW YTD E811 PLANT & UNIT M
M CAUK COMPLICATIONS M
S TOTAL 05/20/97 WDLF CREEK 1 90 SM Equipment Falture NO 1
0 1
05/24/97 aAAIDWOOD 1 0
SM Equipment Failure NO O
1 1
l t
I l
l I
ATTACHMENT 3 N te: YearToDate(YTD)TotalsIncludeEventsWithinThECalenderYearIndicatedByTheEndDateofTheSpecifiedReportingPeriod 05/27/97 ETS 10 Page:1
l
~
COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES i
PERIOD EN0 LNG 05/25/97 l
NUMBER 1997 1996 1995 1994 1993 l
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAE j
l (YTD) l POWER GREATER THAN OR EQUAL To 15%
i EQUIPMENT FAILURE 1
0.77 1.52 1.83 1.52 1.83 DESIGN / INSTALLATION ERROR 0
0.19 0.10 0.12 0.08 0.04 OPERATING ERROR 0
0.10 0.08 0.15 0.21 0.27 MAINTENAECE ERROR 0
0.29 0.50 0.38 0.54 0.52 EXTERNAL 0
0.05 0.13 0.21 0.17 0.13 OTNER 0
0.05 0.10 0.06 0.02 Subtotal 1
1.45 2.43 2.75 2.52 2.81 i
j POWER LESS THAN 15%
EQUIPMENT FAILURE 1
0.24 0.23 0.10 0.27 0.38 i
DESIGN /lNSTALLATION ERROR 0
0.00 0.02 OPERATING ERROR 0
0.05 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 0
0.10 0.06 0.C8 0.02 EXTERNAL 0
0.00 0.04 OTHER 0
0.00 SLAtotal 1
0.39 0.39 0.31 0.37 0.57 TOTAL 2
1.84 2.82 3.06 2,39 3.38 1
1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 0
1.06 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRAMS 2
0.77 1.10 1.13 0.69 0.94 TOTALS MAY DIFFER BECAUSE OF ROUNOING OFF l
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l 4
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ETS-16 Page: 1 05/27/97 I
l l
NhTES 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.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
3.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
J 4.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES 1
(LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 i
Manual and Automatic Scrams for 1989 ------------------ 252 Manuel and Automatic Scrams for 1990 ------------------ 226 Manuel and Automatic Scrams for 1991 ------------------ 206
.d Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175 Manual and Automatic Scrams for 1994 ------------------ 150 Manual and Automatic Scrams for 1995 ------------------ 159 Manual and Automatic Scrams for 1996 ------------------ 146 Manual and Automatic Scrams for 1997 --(YTD 05/25/97)-- 38
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