ML20246B516

Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl

ML20246B516
Person / Time
Site:	Perry, Pilgrim, Quad Cities, 05000000
Issue date:	04/28/1989
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-016, OREM-89-16, NUDOCS 8905090081
Download: ML20246B516 (19)

Text

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HEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment 1

FROM: Wayne D. Lanning, Chief l Events Assessment Branch I Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING April 19, 1989 - MEETING 89-16 I On April 19, 1989, an Operating Reactors Events meeting (89-16) was held to

. brief' senior managers from NRR, AEOD, RES, Comm i ssi on Staff, and Regional Offices on events which occurred since our last meeting on April 12, 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 recctor scrams for the week ending 04/16/89 is presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program.. .,

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Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

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0FFICIAL RECORD COPY

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.T. Murley, NRR- D. Mcdonald, NRR F. Miraglia, NRR- R. Wessman, NRR

J.'Sniezek, NRR' T. Colburn, NRR E. Jordan, AE00 J..Hannon, NRR J. Taylor ~, EDO T. Ross, NRR E..Beckjord,RES D. Muller, NRR W.1 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-

8. Boger, NRR G. Lainas, NRR L'. Shao, NRR-B. Grimes, NRR F. Congel, NRRl E. Weiss, AE0D T. Martin,:EDO J. Lieberman, OE J. Guttmann, SECY A. Thadani, NRR' S. Rubin, AE0D J. Forsyth INP0-R. Barrett, NRR M. Harper, AEOD R. Newlin, GPA w_---__-- . _ _ _ _ _ _

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• L,w NEMORANDutt 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 April 19, 1989 - MEETING 89-16 On April 19, 1989, an Operating Reactors Events meeting (89-16) was held to brief senior managers from NRR, AE00, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on April'12, 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 sumary of reactor scrams for the week ending 04/16/09 is presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program.

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Way)ngD. anning, Ch'ef Events Assessment Dr h Division of Operation Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page 1

1

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, f ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-16)

April 19, 1989 NAME ORGANIZATION NAME ORGANIZATION T. Daniels. NRR/ADSP A. Munno NRR/D0EA

.T. Colburn NRR/PD3-3 M. Reardon NRR/DOEA M. Fairtile NRR/PDI-3 T. Greene NRR/DOEA J. Carte _r NRR/00EA W. Minners RES/DSIR W. Troskoski OEDO R. Gramm NRR/DRIS M. Harper AEOD/DSP P. Baranowsky NRR/D0EA J. Dyer NRR/RSIB R. Wessman NRR/PD1-3 l

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ENCLOSURE 2 0Q40 9, a iq QPERATING REACTORS EVENTS BRIEFING 89-16 9

EVENTS ASSESSMENT BRANCH LOCATI0h 12B-11, WHITE FLINT WEDNESDAY, APRIL'19, 1989, 11:00 A.M.

i PILGRIM UNIT 1' UNEXPECTED RCIC VALVE OPENING (AIT)

PERRY UNIT 1 HIGH TEMPERATURE IN MARK III DRYWELL t-OUAD CITIES UNIT I STUCK OPEN RELIEF VALVE I

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89-16.

EILDRIM UU11_1 Uhfl(PECIED RCIC VALVE OPENING ( AIT1 APRIL 12, 1989 EEDELEB A.6~ MONTH. LOGIC TEST OF THE TRIP AND INITIATION SIGNALS LED T0 i BACKFLOW OF WATER.THROUGH THE RCIC CHECK VALVE, BLOCK VALVES, PUMP AND LOW PRESSURE PIPING RELIEF VALVE TO THE RCIC ROOM.

o

!fAUSE PROCEDURAL AND PERSONNEL ERRORS (TAGGING, VERIFYING AND STATUS AWARENESS) PERMITTED BLOCK VALVES TO BE OPEN DURING TEST ON 04/12/89.

SAFETY SIGNIFl[ANff THIS IS SIMILAR TO A 1983 EVENT AT PILGRIM INVOLVING THE HPCI SYSTEM.

QUESTIONS RAISED REGARDING WHETHER THIS IS AN EVENT V PRECURSOR.

DISCUSSION o REACTOR WAS AT 25% POWER IN ACCORDANCE WITH POWER ASCENSION PROGRAM AFTER EXTENDED OUTAGE.

o TEST IS PERFORMED EVERY 6 MONTHS. DONE "SUCCESSFULLY" LAST TIME (10/05/88); REACTOR WAS NOT OPERATING OR PRESSURIZED.

O APPR0XIMATELY 100 GALLONc 0F WATER WAS DISCHARGED FROM RELIEF VALVE THROUGH DRAIN LINE T0 SUMP AND AREA.

O FIVE WORKERS BECAME SLIGHTLY CONTAMINATED - SH0ES AND ONE HAND.

o RCIC DECLARED INOPERATIVE - ENTERED 7-DAY LCO.

O AIT SENT TO SITE ON APRIL 13, 1989, o RESTART PANEL WITHDREW RECOMMENDATION ON 04/14/89 FOR ALLOWING POWER INCREASE TO 50%.

0- LICENSEE SHUT DOWN REACTOR APRIL 15, 1989 TO COMPLETE TESTING AND' REPAIRS.  !

I o LICENSEE TO BRIEF AIT IN REGION ON APRIL 19.

o NEARLY IDENTICAL EVENT OCCURRED 6 YEARS AGO INVOLVING HPCI. k IN 84-74; AE0D CASE STUDY AE0D/C502 CONTACT: J. CARTER SIGEVENT: YES  ;

REFERENCES:

10 CFR 50.72 # 15310, MORNING REPORT 04/13/89, AND PN-I-89-027

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PILGRIM UNIT 1 89-16 FOLLOWUP-STAFF WILL ASSURE SATISFACTORY RESOLUTION PRICR TC RECOMMENDING l 'c. AUTHORIZATION OF POWER LEVELS AE0VE 25%.  !

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89-16 PERRY _llNIT 1 HIGH TEMPERATURE IN MARK III DRYWEL1  ;

FEBRUARY 28, 1989 1

PROBLELi HIGH TEMPERATURE IN UPPER PORTION OF DRYWELL.

LESE INADECUATE INSULATION AND/0R VENTILATION RESULTED IN RADIANT HEAT.

SAFETY SIGNIFICANCE THE UPPER DRYWELL AREA C0tlTAINS APPROXIMATELY 150 CABLES OF WHICH ABOUT 50 PER CENT ARE SAFETY-RELATED.

1)lSCUSSION o ON FEBRUARY 28, 1989, LICENSEE NOTICED HEAT DAMAGE TO CABLES Ifl THREE CONDUITS LOCATED IN UPPER DRYWELL.

o ON MARCH 2, 1989, LICENSEE DISCOVERED DURING A FUNCTIONAL TEST THAT TWO MECHANICAL SNUBBERS IN THE SAME AREA HAD APPARENT HEAT LAMAGE.

o ON APRIL 6, 1989, LICENSEE NOTIFIED NRC.

0 ESTIMATED THAT CABLES WERE EXPOSED TO TEMPERATURES IN EXCESS OF 300*F. SNUBBERS MAY HAVE BEEN EXPOSED TO TEMPERATURES AS HIGH AS 400-500*F.

o EQUIPMENT QUALIFICATION TEMPERATURES FOR CABLES IS 195'F AND FOR SNUBBERS, 300*F.

o AFFECTED CABLES INCLUDES SRMs, IRMs, SRVs AND HYDROGEN IGNITERS.

o LICENSEE PLANS TO REPLACE CABLES THAT SHOW VISUAL DAMAGE: 15 0F 73 SAFETY-RELATED CABLES AND E2 0F 79 NON-SAFETY-RELATED CABLES.

o LICENSEE PLANS TO JUSTIFY NOT REPLACING ALL THE CABLES BY ANALYZING THE MECHANICAL PROPERTIES OF THE CABLES (AN UNIQUE APPROACH).

O GE ISSUED RICSIL NO. 041, " EXCESSIVE MARK III DRYWELL TEMPERATURE",

MARCH 31, 1989 IN RESPONSE TO THIS EVENT. RICSIL MENTIONS SRVs, MSIVs, AND WATER LEVEL MEASUREMENT SYSTEM.

CONTACT: T. GREENE SIGEVENT: YES REFERENCE; MORNING REPORT 04/11/89

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'. PERRY UNIT 1 89-16 o NRC ISSUED INFORMATION NOTICE 89-30, "HICH TEMPERATURE ENVIRONMENT AT NUCLEAR POWER PLANTS", MARCH 15, 1989 WHICH ADDRESSES HIGH TEMPERATURES IN CRYWELL.

EDLLDHUE o GENERIC LETTER 88-07, " ENVIRONMENTAL CUAllFICATION OF ELECTRICAL-EQUIPMENT IMPORTANT TO SAFETY FOR NUCLEAR POWER PLANTS," DATED APNIL7,1988RECulRESLICENSEETOPROVIDEJC0WHENPOTENTIAL ECUIPMENT QUALIFICATION DEFICIENCIES HAVE BEEN IDENTIFIED.

o PROJECT MANAGER WILL COORDINATE NRC REVIEW.

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.. .' . 89-16 CUAD [lTIES UNJI_1 SIDELDEflLEELIEF VALVE APRIL 17, 1989 PROBLEM ELECTROMATIC RELIEF VALVE STUCK OPEN DURING SURVEILLANCE TESTING.

LAUSE l EROSION OF PILOT VALVE. ,

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' SAFETY SIGNIEJCANCE REACTOR C00LDOWN RATE AVERAGED 200*F/ HOUR DURING FIRST HOUR; THIS COULD CAUSE THERMAL STRESS TO THE REACTOR VESSEL AND INTERNALS. i DISCUSSICE 0; PLANT WAS'IN STARTUP (10% POWER) AFTER PERFORMING MAINTENANCE ON ELECTROMATIC RELIEF VALVE IC.

o POST-MAINTENANCE TESTING OF THE VALVE WAS REQUIRED; IT WAS DECIDED l

.T0 PERFORM 6 MONTHS REQUIRED SURVEILLANCE ON THE REMAINING ELECTRCMATIC VALVES.

o VALVES IC, lA, AND 1B WERE TESTED SUCCESSFULLY. AT 3:27 A.M.

VALVE ID WAS OPENED AND REMAINED IN THE OPEN POSITION; THE VALVE WOULD NOT SHUT DESPITE REPEATED ATTEMPTS.

O LICENSEE SCRAMMED REACTOR AT 3:30 A.M. PER PROCEDURES AND DECLARED AN UNUSUAL EVENT.

o MAXIMUM SUPPRESSION POOL TEMPERATURE WAS 100*F AT 5:12 A.M.

o REACTOR C00LDOWN RATE AVERAGED 200*F/ HOUR DURING THE FIRST HOUR (FIGURES 1 & 2), AND ABOUT 115'F/ HOUR DURING THE FIRST TWO HOURS. '

o GE PRELIMINARY ANALYSIS INDICATES THAT THIS THERMAL CYCLE WILL NOT HAVE-AN IMPACT ON PLANT LIFE.

O CAUSE OF THE FAILURE IS SUSPECTED TO BE EROSION IN THE PILOT VALVE (FIGURE 3). ,

o THE ENTIRE VALVE HAS BEEN REPLACED; THE OLD VALVE WILL BE DECONTAMINATED AND DISASSEMBLED FOR INSPECTION.

CONTACT: A. MUNNO SIGEVENT: NO

REFERENCE:

10 CFR 50.72 # 15358 AND MORNING REPORT 04/17/89

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..- OdAD.CITIESUNIT1 89-16 o ALL PILOT VALVES HAVE BEEN REPLACED ON THE ELECTROMATIC VALVES;  ;

ALL VALVES WILL BE TESTED DURING STARTUP.

o THREE OTHER FACILITIES HAVE ELECTROMATIC VALVES: OYSTER CREEK, NINE MILE POINT 1, AND DRESDEN 2 & 3.

SINCE 1970, THERE HAVE BEEN SIX INSTANCES OF ELECTROMATIC RELIEF

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o VALVE FAILURES; 5 HAVE BEEN ATTRIBUTED TO PILOT VALVE FAILURE.

O LICENSEE IS COMMITTED TO PERFORMING A THOROUGH ROOT.CAUSE ASSESSMENT OF THE ID ELECTR0MATIC RELIEF VALVE FAILURE. j FOLLOWUP o GE WILL PERFORM AN EXTENSIVE REACTOR THERMAL STRESS ANALYSIS FOR THIS EVENT.

o REGION III AND NRR WILL FOLLOW LICENSEE'S ASSESSMENT OF VALVE FAILURE CAUSE AND REACTOR THERMAL-STRESS EVALUATION. NRR WILL I FOLLOW LICENSEE ACTIONS AND IF NECESSARY PERFORM TECHNICAL

, REVIEW.

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FERFORGANCE INDI:ATORS !!EN!FICANT EVENTS ENCLOSURE 3 I

i fLANT NME EVENT EVENT DESCRIPil:N GTR SIEN!FICANCE DATE l 04/09/89 INOPERABLE RHR ISOLATION VALVE DUE TO WIRING ERROR. O FDIENTIAL FOR CR ACTUAL LE3F.A:ATIEN

. TF 0J4 1 RESULT 5 IN DEGRADATION OF PRES 3URE ECLNDARY FROTECTICN. OF FR! MARY COOLANT FRE33'5E EDUNOARY. l 1

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EEACTCR ECF AM EUMARY I BEEK ENDINS 04/16/B9

1. PLANT SFECIFIC LATA DATE SITE UNii POWER $!SNAL CAUSE COMPLI- YTD YTD YTD CATIONS AB0VE EELCw TOTAL 151 151 04/11/39 EALEM 2 100 A EQUIPMENT ND 3 1 4 04/12/89 QLAD CITIES 1 75 N EQUIPMENT NO 1 0 1 04/13/E9 NINE MILE F0!NT 2 '9 A EGU!FMENT h0 1 0 1 04/15/29 BE0JDYAH 2 30 A FERSONNEL NO 1 0 1 04/15/89 DRESDEN 3 92 A EQUIFPENT N0 3 0 3 04/15/E9 SOUTH TEXAS 2 24 A EQUIPNENT ND 1 1 2 04/16/69 SEQUOYAH 2 16 A PERSONNEL NO 2 0 2 04/16/89 DIABLD CANYON 2 50 A EGUIPMENT NO 1 0 1

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l NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 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 R0D MOTION, AND EXCLUDE PLANNED i TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONS: REC 0VERY 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.

4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING),' SYSTEM DESIGN, OR UNKNOWN CAUSE. ,

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