ML20246C326
| ML20246C326 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Comanche Peak, 05000000 |
| Issue date: | 05/04/1989 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-89-018, OREM-89-18, NUDOCS 8905090339 | |
| Download: ML20246C326 (13) | |
Text
{{#Wiki_filter:.- -- _ _-_ MAY 0( ggg MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: -Wayne D. Lanning, Chief EvenM Assessment Branch ! Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETI!!G May 3, 1989 - MEETING 89-18 c. On May 3, 1989, an Operating Reactors Events meeting (89-18l was held to brief senior managers from NRR, AEOD, Commission Staff, and Regional Offices on events which occurred since our last meeting on April 26, 1989. The list of attendees is included as Enclosure 1. The events discussed and the significant elements of these events are presented in Enclosure 2. A summary of reactor scrams for the week ending 04/30/89 is presented in Enclosure 3. Three significant events were identified for input into the NRC performance indicator program. 0%:sv";4 Fan y ro; ;.. WayneD.Lanning,khnf Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.: See flext Page DISTRIBUTION h
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'0FFICIAL RECORD COPY
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J CC* T. Murley, NRR- *
.N. Malloy, NRR F.'Miraglia, NRR B. Grimes, NRR l J. Sniezek, NRR M. Boyle, NRR E. Jordan, AE0D J. Stolz, NRR J.. Taylor. EDO
- E. Beckjord, RES W. Russell,.RI
'M. Ernst..RII B.' Davis, RIII' R. D. Martin, RIV J. B. Martin,.RV W.-Kane, RI L.-Reyes, RII E. Greenman, RIII
, L. Callan, RIV D. Kirsch, RV S. Varga, NRR B. Boger, NRR G. Lainas, NRR L. Shao,fiRR B. Grimes, NRR F. Congel, NRR
'E. Weiss, AEOD
.T. Martin, EDO J. Lieberman, OE J. Guttmann, SECY
-A. Thadani, NRR S. Rubin, AEOD J. Forsyth, INP0 R. Barrett, NRR M. Harper, AE0D R. Newlin, GPA 3
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MAY 0 : 1969
-MEMORANDUM FOR: Charles E. Rossi, Director..
Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING May 3, 1969 - MEETING 89-18 On May 3, 1989, an Operating Reactors Events meeting (89-18) was held to brief senior managers.from NRR, AE00, Connission Staff, and Regional Offices on events which occurred since our last meeting on April 26, 1989.. The list of attendees is included as Enclosure 1. The events discussed and the significant elements of these events are presented ; in Enclosure 2. A summary of reactor scrams for the week ending 04/30/89 is presented in Enclosure 3. Three significant events were identified for input into the NRC. performance indicator program.
/
& j4 -
Waype D. Lanning, Chief Events Assessment Branc Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.: See Next Page
--___- _______m_____ _ _ _ . _ _ _ _
- l. .
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-18) Hay 5, 1989 NAME ORGANIZATION NAME ORGANIZATION F. Miraglia NRR/ADT- T. Murley D:NRR P. Baranowsky NRR/DOEA J. Sniezek DD:NRR J. Roe NRR/DLPQ C. Heltemes AE00 J..Lyons. NRR/CPPD M. Fields NRR/CPPD. G. Lainas NRR/ADR-2 J. Carter NRR/DOEA J. Partlow NRR/ADP A. Hunno NRR/DOEA E. Rossi NRR/DOEA D. Moran NRR/0SP L. Norrholm OCM/KC W. Troskoski. OE W. Lanning NRR/DOEA M. Reardon NRR/DOEA i i 1 I l
- i, Y ,
.. ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 89-18 EVENTS ASSESSMENT BRANCH L0f ATIO.tli 12B-11, WHITE FLINT WEENESDAY, MAY 3, 1989,.11:00 A.M.
C0MANCHE PEAK UNIT.1 HOT WATER INTRUSION INTO AUXILIARY FEEDWATER SYSTEM MILLSTONE UNIT 1 HIGH ENERGY LINE. EREAK EVALUATION K _ _ . _ - - - _ . _ . - - . - - _ - - - . _ . - _ _ - _ _ . - - . _ _ . _ _ - _ _ . - .
-[ ' E9-18 CCf1ANCBE_EEAK_DulI_l BDT WATER INTRUS_ ION IST0 AUXILJhEY_EEEDWATER SYSTEM APRIL 23, 1989 EEDELEM BACKFLOW CF HOT STEAM CENERATOR INVENTORY INTO AUXILIARY FEEDWATER SYSTEM PIPING.
ChDBE . OPERATOR ERROR AND MECHANICAL FAILURES. SAFETY SILNIFICASEE AUXILIARY FEEDWATER SYSTEM INOPERABLE, POTENTIAL STEAM BINDING OF PUMPS. 1 DlBCDSBlDE o CN. APRIL 23, 1989, DURING HOT FUNCTIONAL TESTING 0F THE AUXILIARY FEEDWATER (AFW) SYSTEM,' HOT STEAM GENERATOR INVENTORY FLOWED INTO AFW SYSTEM PIPING. O A COMBINATION OF OPERATOR ERROR AND MECHANICAL FAILURES CONTRIBUTED TO THIS EVENT. O WITH THE NUMBER 2 MOTOR DRIVEN AFW PUMP (MDAFWP) SUPPLYING l FEED FLOW, AN ATTEMPT WAS MADE TO ALIGN THE TURBINE DRIVEN AFW PUMP (TDAFWP) FOR H0T FUNCTIONAL TESTING. O PLANT PROCEDURES DIRECT THE OPERATOR TO CLOSE THE TDAFWP DISCHARGE VALVE (VALVE NO. IAF-041) AND THEN TO OPEN THE TDAFWP RECIRCULATION VALVE (VALVE NO 1AF-042). THIS EVOLUTION PROVIDES A FLOW PATH TO THE CONDENSATE STORAGE TANK FROM THE TDAFWP FACILITATING HOT ALIGNMENT TESTING OF THE TDAFWP PIPING. O THE VALVES WERE MANIPULATED. SIMULTANEOUSLY. THIS ERROR COUPLED WITH THE SUSPECTED FAILURE OF A NUMBER OF BORG-WARNER CHECK VALVES PROVIDED A PATH FOR INVENTORY IN STEAM GENERATORS 1, 2, AND 4 TO FLOW TO THE CONDENSATE STORAGE TANK. CONTACT: N. FIELDS SIGEVENT: _1ES_
REFERENCE:
OSP MORNING REPORT MAY 1, 1989
o
. COMANCHE PEAK UNIT 89-18 o FOR.UNKNOWNRkASONS,INVENTORYINSTEAMGENERATORNO.3 REMAINED C0fSTANT.
O POST' EVENT TESTING HAS DETERMINED THAT THE CHECK VALVES , ASSOCIATED WITh Tile DISCHARGE HEADERS FOR BOTH MDAFWPS ARE FAULTY. O HE MECHANICAL FAILURES MAY NOT HAVE SURFACEE HAD THE PROPER PROCEDURE BEEN FCLLOWED). o Tl!E CHECK VALVES ASSOCIATED WITH THE TDAFWP DISCHARGE HEADERS ARE CURRENTLY UNDERCOING TESTING TO DETERMINE THEIR CONDITION. ALL CHECK VALVES HAVE SATISFACTORILY UNCERGONE PREVIOUS OPERABILITY TESTING. FOLLORUE o OSP IS CONDUCTING A SPECIAl. INSPECTION OF THIS EVENT. o LICENSEE WILL COMPLETE HOT FUNCTIONAL TESTING, AFTER WHICH ALL CHECK VALVES WILL BE DISASSEMBLED TO DETERMINE FAILURE M00E. o LICENSEE IS EVALUATING THE NEED TO EXPAND CHECK VALVE d SURVEILLANCE TO INCLUDE OTHER AREAS OF THE PLANT. l i
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0 E9-18 MI L LSTONE_DUJI_1 JJJDB_fEERGYLillEEREAKEVALUtTlDN MARCH 22, 1989 PRCBLEB THE REACTCR BUILDING CLOSED COOLING WATER (RECCW) SYSTEM LOCATED WITHlf! THE DRYWELL IS NOT PROTECTED FROM A HIGH ENERGY LINE BREAK. ChDSE THE DESIGN DID;NOT RECOGNIZE THAT A HIGH ENERGY LINE COULE FAIL THE RBCCW PIPING WHICH WAS ASSUMED TO EE AN EXTENSION OF CONTAlllMEhT. SifETY SILBlFICANCE RADIOACTIVITY RELEASED AS A RESULT OF A POSTULATED. RECIRCULATION LINE BREAK COULD BYPASS CONTAINMENT, LISCUSS10fl o MILLSTONE UNIT 3 HAS A MAFK I CONTAINMENT. c ISOLATION FOR THE RBCCWS PROVIDED BY A SINGLE ISOLATION VALVE. O RBCCW SYSTEM IS NOT SAFETY-RELATED. o PIPE WHIP AND IMPINGEMENT EFFECTS NOT ADECUATELY CONSIDERED IN THE ORIGINAL ANALYSIS. o LICENSEE HAS INSTALLED A PAIR OF REMOTE MOTOR OPERATED BLOCK VALVES OUTSIDE CONTAINMENT IN BOTH THE SUPPLY LINE AND RETURf' LINE. O MODIFICAT10fi DCNE FOLLOWING 50.59 REVIEW. EDLLDMUE l 0 PM AND RESIDENT IflSPECTOR TO ASSURE LICENSEE MODIFICATION IS
- i. ACCEPTABLE.
I o If1 FORMATION NOTICE BEING DRAFTED. CONTACT: J. CARTER SIGEVENT: _YES_
REFERENCE:
10 CFR 50.72 #15092
a Fist M. I s'!!0;/ET' FERF0;MANCE IhDICATCR3 31BNIFICANT Ei!NT! i
, ENCLOSURE 3 FLANT N;"E EVENT EVENT LESCRIFT:GN QiR SIGNIFICANCE
!Ai!
FIL5 FIR 04/12/89 AN RCIC lhJECTICN BLOCK VALVE WA3 INADVERTENTLY OFENEI 1 FOTENTIA; FOR CR ACT;AL CEERA:AitCs DL11h6 A TEST AND AN FCFB CHECK VALVE LEAKED FEECWATER OF FRIPARY CODLANT FFE35;FE SACK TRHC!i3H RCIC SUCTION FIPING AND OUT A RELIEF VALVE. PCUNDARY C'.'AD CITIES 04/17/3? DURING TESTINS OF ELECTROMATIC RELIEF VALVE "D", THE 1 3CFAM WlIH C ZFLICAIICN3 VAL 7E FAILED TO CLD3E. CFERATORS MANL' ALLY 3 CRAMPED THE REACTOR FER FROCEDL'RES. REACT R C00Lf0WN FATE EXCEEDED TECH SPEC LIMIT CF 100 IESFEE3 F CURIN3 THE FIRST ikC HARS CF THE PLOWXWN. - RIVER IIND 1 04/20/89 FREEIE FLUG IN SERVICE WATER P!FE FAILED CAUSING FLOCDING 1 UNEXFECTED FLANI FE3FCN?E TO A 3Ei AND L0E3 CF F0 DER TO RsR, 5FENT FUEL FOOL, AND DiHER OF CONDITION 3 EGulfr.ENT. l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _J
e REACTOR SCRAM
SUMMARY
WEEKENDING 04/30/89
- 1. PLANT SPECIFIC DATA DATE SITE UNIT POWER S16NAL CAUSE COMPLI- YTD YTD YTD CA110NS ABOVE PELOW TOTAL 151 15%
NO REACTOR SCRAMS THIS WEEK i
o. NOTES
- 1. PLANT SPECIFIC DATA BASED ON INITIAL kEVIEW 0F 50.72 REPORTS-FOR THE WEEK 0F INTEREST. PERIOD IS HIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS FEACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRANS AS PART OF PLANNED SHUTDOWN IN ACCORCANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
P. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM. 3.- PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS. 1 4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. 1
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