ML20153G633
| ML20153G633 | |
| Person / Time | |
|---|---|
| Site: | River Bend, FitzPatrick, 05000000 |
| Issue date: | 08/30/1988 |
| From: | Jaudon J Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| GL-88-14, OREM-88-035, OREM-88-35, NUDOCS 8809080276 | |
| Download: ML20153G633 (15) | |
Text
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- NEHORANDUM FOR: Charles E. Rossi, Director' Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM:
Johns P. Jaudon Acting Branch Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING August 30, 1988 MEETING 88-35 On August 20, 1988, an Operating Reactors Events meeting (88-35) was held to brief senior managers from NRR, OSP, AEOD, Comission Staff, and Regional Offices on events which occurred since our last meeting on August 23, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents one event suggested for long term followup and a sumary of reactor scrams for the week ending August 28, 1988. One signif-icant event was identified fos input to NRC's Performance Indicator Program.
Johns P. Jaudon, Acting Branch Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
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AUS 8 4138, MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM:
Johns P. Jaudon, Acti g Branch Chief n
Events Assessment B:anch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
TPE OPERATING REACTORS EVENTS MEETING August 30, 1988 - MEETING 88-35 On August 30, 1988, an Operating Reactors Events meeting (88-35) was held to brief senior managers from NRR, OSP, AEOD, Comission Staff, and Regional Offices on events which occurred since our last meeting on August 23, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents one event suggested for long term followup and a sumary of reactor scrams for the week ending August 28, 1988. One signif-icant event was identified for input to NRC's Performa ce Indicator l'rogrem.
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Enclosures:
As stated cc w/Enclo.: See Next Page M
o ENCLOSURE 1 LIST OF ATTENDEES OPE 2/4 TING REACTORS EVENTS BRIEFING (88-35) August 30. 1986 NAME ORGANIZATION NAME ORGANIZATION R. Scholl NRR/DOEA M.L. Reardon NRR/00EA I D. Crutchfield NPR/DRSP P. Baranowsky NRR/00EA D.C. Fischer WRR/DOEA B. Boger NRR/ACR-1 S. Varga NRR/DRP J. Jaudon NRR/00EA l G. Lainas NRR/ADR-2 J.E. Konklin NRR/DRIS W.A. Paulson NRR/PD-4 J. Guttmann SECY J.A. Calvo NRR/DRSP !.0. Martin OEDO M. Karman OCM/KR F.J. Miraglia NRR ADP C. Schulten NRR/00EA M. Callahan GPA/CA W. Hodges NRR/ DEST T. Novak AE00/DSP t i { t [ l I .._._,,_...m_ _. _,. - - - - -.. - -. 1 -.o _,,,,-,_..-,-4
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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-35 EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT TMSDAY, AUGUST 30, 1988, 11:00 A.M. l l FITZPATRICK DROPPED FUEL BUNDLE 1 l l RIVER BEND SCRAM FROM 100% POWER WITH INITIATION l OF ENGINEERING SAFETY FEATURE AND l FAILURE OF POWER TO TRANSFER TO 0FFSITE I
88-35 FITZPATRICK DROPPED FUEL BlINDLE AUGUST 22, 1988 PROBLEM A NEW FUEL BUNDLE WAS DROPPED INTO NEW FUEL STORAGE VAULT WHEN ATTEMPTING TO LIFT IT INTO FUEL PREP, MACHINE IN SPENT FUEL POOL WITH OVERHEAD CRANE, CAUSE o PROCEDURES ALLOWED MOVEMENT OF BOTH OVERHEAD CRANE AND REFUEllNG BilDGE DURING NEW FUEL HANDLING. o OVERHEAD CRANE SWlVEL STUD FAILED AFTER ITS CABLE COLLIDED WITH REFUEllNG BRIDGE MON 0RAll HOIST, SAFETY SIGNIFICANCE POTENTIAL FOR DAMAGING FUEL EITHER IN SPENT FUEL POOL OR THE NEW FUEL STORAGE VAULT, DISCUSSION o AT 10:15 P.M., THE REACTOR WAS C0ASTING DOWN FOR REFUELING, AN SR0 OPERATING THE REFUELING BRIDGE SNAGGED THE OVERHEAD CRANE CABLE WITH THE MONORAll HOIST, WHICH HAD A NEW FUEL BUNDLE SUSPENDED FROM IT, o SR0 MOVED BRIDGE TO RELEASE THE CABLE. SUBSEQUENTLY, WHEN THE FUEL TRANSFER PROCEEDED THE OVERHEAD CRANE SWlVEL STUD BROKE, AND THE NEW FUEL ASSEMBLY FELL 2 FT INTO THE NEW FUEL VAULT, o LICENSEE IDENTIFIED CAUSE OF DROP AS FAILURE OF SWlVEL STUD WHICH CONNECTS GENERAL PURPOSE GRAPPLE TO OVERHEAD CRANE HOIST CABLE, F0ll0WUP o LICENSEE'S PROCEDURES FOR LOAD TESTING SWlVEL STUD NOT IN ACCORDANCE WITH GE Sit NO, 10, o LICENSEE HAVING METALLURGICAL EXAM OF SWlVEL STUD. O DROPPED FUEL ASSEMBLY TO BE SHIPPED TO WILMINGTON, NC AFTER GE REPRESENTATIVE INSPECTS FOR DAMAGE, CONTACT: C, SCHULTEN
REFERENCE:
MORNING REPORTS DATED 08/22/88 AND 08/24/88
FITZPAT. RICK. 88-35 h FOLLOWUP (CONTINUED) j o LICENSEE INTENDS TO IMPROVE PROCEDURES AND RETRAIN PERSONNEL. O SEVERAL GE SILS HAVE BEEN ISSUED. THE LATEST WAS Sil NO. 10, ISSUED IN DECEMBER 1986, i r f I 1 1 s l l l l l l r I l r I l 1
n' REACTOR s LOG. REACTOR EXHAUST S L DO. FANS VENT / O O y v / "Mr " e T, L1 LJ [ CRANt [ \\ h 1 1 I T , Re o.i ri iv,m / v 6 n RigC. / CbRt R eactor e,.... Veswl F gLOWOUT ~ / A 5 MATCH ,a x. 7.~-W PE RSONS E'NTHY f \\ l 9 9
== _Y,E J L J L FITZPATRICK SECONDARY CONTAINMENT
i [1,TZPATRICK JN- = 4 4 b >NL 04-5 l PNL 04-8 A PNL 04 68 g i l EQUIP. M ATCHI t = s a .y".---A* C J r, SERVICE x PLATFORM L7". g REACTOR INT ER N AL S g STORAQt PIT I { ) k / n y g STUO TENeloNER HEAD WASMDOWN p o AREA l REACTOR R %= HEAD CAVITY Pff .i 8% b ganga 1 NW / 'i
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METAL STAMP OR ELECTROETC'l ILEMTIFICATION: GENERAL ELECTRIC CABLE TEPf! MAL
- 129831316--(GRnUP NO. AS ADPLICABLE) l j
j J mc... ,,,.o y = - -+ - n ' A % h_[ tNl ek ) N ~ j 7/16 - 14 UNC FEMALE THREAD
- G002 1/2 - 13 UffC 7/16 - 14 LHC FEfiALE THREAD
.. ALE THREAD FITZPATRICK Fictiet ! - CAstt ItanistAL (Used in SWR 2.3,4 and 5) O e-
88-35 RIVER BEND SCRAM FROM 100% POWER WITH INITIATION OF ENGINEERING SAFETY FEATURE AND FAllVRE OF POWER TO TRANSFER TO OFFSITE AUGUST 25, 1988 PROBLEM REACTOR SCRAMMED FROM 100% POWER WITH SPURIOUS START OF HPCS AND RCIC. THE DIVISION 111 4160 VAC Dl0 NOT TRANSFER TO 0FFSITE POWER, SUBSEQUENTLY, THE MPCS INJECTION PIPING WAS SUBJECTED TO REACTOR COOLANT, CAUSE o THE PLANT EXPERIENCED A SERIES OF COMPONENT FAILURES AND PROBLEMS, A GENERATOR BRUSH FAILURE CAUSED THE PLANT SCRAM, AN UNDERVOLTAGE RELAY FAILURE CAUSED A LOSS OF DIVISION lli POWER, A FAILURE OF THE HPCS CHECK VALVE AND THE INJECTION VALVE PERMITTED WATER TO FLOW FROM THE REACTOR VESSEL TO THE SUPPRESSION POOL VIA THE MINIMUM FLOW LINE, o THE SPURIOUS START OF THE HPCS AND RCIC WAS CAUSED BY PERTURBATIONS IN THE REFERENCE LEGS AS A RESULT OF THE STEAM DOME PRESSURE TRANSIENT, SAFETY SIGNIFif.ANCE THE PLANT DID NOT RESPOND TO A REACTOR TRIP IN AN EXPECTED MANNER, DISCUSSION o SEQUENCE OF EVENTS: GENERATOR TRIPPED FROM 100% POWER, TURBINE TRIPPED, REACTOR SCRAMMED, DIVISION 111 4160 VAC DID NOT TRANSFER TO OFFSITE. RPS MOTOR GENERATOR SET "A" TRIPPED, HPCS AND RCIC STARTED SPURIOUSLY, INSTRUMENT AIR COMPRESSORS TRIPPED ON HIGH TEMPERATURE, HPCS SYSTEM SECURED, HPCS DISCHARGE PIPING TEMPERATURE LIMITS WERE EXCEEDED, HPCS VALVES EVENTUALLY SEALED OFF THE LEAK, CONTACT: R. SCHOLL
REFERENCE:
50,72 #s 13285 AND 13292, MORNING REPORT 08/26/88, AND PNO-IV-88-70
RIVER BEND 88-35 o ANALYSIS OF EVENTS: THE PLANT RESPONSE TO THE INITIAL FAILURE WAS AS EXPECTED, THE FAILURE TO TRANSFER DIVISION 111 POWER RESULTED IN A TRIP 0F THE "A" RPS MOTOR GENERATOR SET. THE PRESSURE TRANSIENT IN THE STEAM DOME WAS LARGER THAN AT MOST PLANTS BECAUSE RIVER BEND ONLY HAS A 10% BYPASS CAPACITY, THE PEAK VESSEL PRESSURE WAS 11151 PSIG. THE LOSS OF THE MOTOR GENERATOR SET CAUSED ISOLATION OF THE t CONTAINMENT, SERVICE WATER SYSTEM AND CONTROL ROOM. l THE LOSS OF SERVICE WATER COOLING CAUSED THE INSTRUMENT AIR COMPRESSORS TO TRIP ON HIGH TEMPERATURE. E0LLOWUP o GENERIC LETTER 88-14 FOLLOWUP WILL DETERMINE THE SIGNIFICANCE OF A LOSS OF INSTRUMENT AIR AT RIVER BEND, o THE STAFF IS PURSulNG A REVIEW 0F THE LICENSEE'S EVALUATION OF THE LEAKING HPCS INJECTION AND CHECK VALVES, i i f t i l l
ENCLOSURE 3 Pete be. 1 C/26/Il Melliti LMtfm FILituuP Cft F Plat M M alt llplfitaf !stf14L FELOWP MillWEuf Sugetitti M9 Eft ;u Sullflf ItPittti Met met i1AMFit TI: tuPLiftp Mit 07m /80 Patt vteN 2 .F. Pcttsflat MitM Pt00Lin situ Pctill 9 Itutttti Ptffit gawritta net Mtaf Fa!Lustl. pust w/Ilts Effttti 8tLars. Ilm:( T4 Fiff Ilfelrltaatt IPittrit llM. FEl vitM pli 2, (M.ftm F f* P9:ktR 480 MfLN 4E M41!c FOLLauW MllMI 19 pt/titt. APPLicA4!Liff, il full Fa!LUDt Il#1L4R 78 ML8f Wt/1109 411M1 ft 50B179R Alt ellaf F41LWtl af Fa!LLIDtl fMT CMle't te3UBt M (I'4Lt!!t the#M PEI VitM M Mv!!e M Petita swritti plat v MPpf asp f( t!ctsMt'l M!pic guttritafle taattt!I. Mitu st MMI M ttttugit's Mef flu M LM fta Caettityt actlM Amt AMauAft. Mllenti 78114 liteaet,31t3, Miti TE 6 61192 FOR PEI YttM UBl! ! TE I 69173 FOR PER WR9E pli 2 f aC 149114 FOR Fall vilM Ub!! $
Page no. ,1 C8/30/0 PERFORNANCE INDICATOR $ $18N!FICMT EVENTS PLANT W E EVENT EvtNTDESCRIPi!04 ettl!BN!FICANCE DATE. ,RIVit !!NS 08/25/04 PLANT TRIP DN 6tutRATOR 3RU$N FA!LL9E N!TH FAILURE OF0 UN!!Pttfit PL WT RtlPON$t TO A Sti O!Vll!0N !!! 4160 VAC AND BACK LEAKAGE THROUGH leCS OF CON 0lf!CNS INJttil04ANDCHICKVALVil, l l l e 9
o ~, REACTOR SCRM IUMMAAv utit intial N/29/M
- l. PL M i SPECIFIC HTA Hit litt Uu!T P0utR Ill#4L C40$t COMPLI-Til fig Yip Chil0NI A90VE NLOW TOTAL 151 161 r
M/24/H CALVERT CLIFFS 1 IN A E00l M ui to 2 0 2 N/25/06 COOPER 1 100 A E9UIPMNT N0 3 0 3 N/25/M RIVtt M me i 1M A (GUI M bi ill 3 1 4 08/26/90OC0ttE 3 100 A EDUIPMui NO 1 0 1 N /26/ H $0UTH filal 1 iM A E00!PMENT
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1 4 Hl26/H HOPE CRitt i lH A E00!PMui N0 3 1 4 M/27/04 PALO VttM 1 16A PEA 50Nutt NO 1 6 $UMMART OF COMPLICATIONS SITE Leli COMPLICAi!ONS t IIVER H kD 1 F41LURf 0F AUllLintf itLAT FRIVitiff flANSFit 0F DIVlllC4 !!! 4160 VAC. I P!PlWG THERf44L M5!S4 LIMlil (ICEEMD DUE TO HPCI CMCK VALVE 440 INJttil04 VALVE Lt&KAGE. I i I i I i I l l s -. _.. _ -. _.}}