ML20129H521

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Summary of Operating Reactors Events Meeting 96-13 on 961023,informing Senior Managers from Ofcs of Commission,Oe, NRR & Regional Ofcs of Selected Events That Occurred Since Last Briefing
ML20129H521
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 10/29/1996
From: Chaffee A
NRC (Affiliation Not Assigned)
To: Martin T
NRC (Affiliation Not Assigned)
References
OREM-96-013, OREM-96-13, NUDOCS 9611010072
Download: ML20129H521 (12)


Text

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O'tobr 29, 1996 t

MEMORANDUM TO: Thomas T. Martin. Director Division of Reactor Program Management FROM: Alfred E. Chaffee. Chief [ original signed by]

Events Assessment and Generic Communications Branch Division of Reactor Program Management

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING OCTOBER 23, 1996 - BRIEFING 96-13 On October 23, 1996, we conducted an Operating Reactors Events Briefing l (96-13) to inform senior managers from offices of the Commission OE. NRR and regional offices of selected events that occurred since our last briefing on October 16, 1996. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events, l

Attachment 3 contains reactor scram statistics for the week ending October 20, )

1996. One significant event was identified for input into the NRC Performance  !

Indicator Program (Attachment 4).

Attachments: As stated (4) cc w/atts:

See next page CONTACT: Kathy Gray. NRR (301) 415-1166 '

DISTRIBUTION: (w/atts)

Central" Files PUBLIC LKilgore. SECY t PECB R/F y3 l DOCUMENT NAME: G:\KAG\0RTRANS To receive a copy of this dccument, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No cop OFFICE PECB lEj PECB lEl PECB l C/PECB lN /

of f[

NAME KGray:kag hptp SKoenick y $/L EGoodwin (* AChatfee ;) \ f E DATE 10/gp /96 V 10/ 22]/96 10/g4 /96 ) 10 $ /96 f

OFT 6CLAL RECORO COPY f d {Q- j ptai;ncy n10090 '

9611010072 961029 -[3)f PDR ORO NRRB PDR

c I e  !

cc: )

F. Miraglia, NRR (0-12G18) R. Hernan NRR (0-14B21)

F. Gillespie, NRR (0-12G18) F. Hebdon, NRR (0-14B21)

R. Zimmerman, NRR (0-12G18) l A. Thadani, NRR (0-12G18)  !

B. Sheron, NRR (0-12G18) i S. Varga, NRR (0-14E4) l J. Zwolinski, NRR (0-14H3)

J. Roe, NRR (0-13E4)

E. Adensam. NRR (0-13E4)

G. Lainas NRR (0-7D26)

G. Holahan, NRR (0-8E2)

M. Virgilio NRR (0-8E2)

D. O'Neal, NRR (0-10E4)

8. Boger NRR (0-9E4)

M. Markley, ACRS (T-2E26)

E. Jordan, AE00 (T-4D18)

C. Rossi, AEOD (T-4A9)

F. Congel, AEOD (T-4D28)

R. Barrett. AEOD (T-4A43)

S. Rubin, AE00 (T-4D28)

M. Harper AE00 (T-4A9)

W. Leschek, AEOD (T-4A9)

V. McCree, EDO (0-17G21)

J. Gilliland, PA (0-2G4)

D. Morrison, RES (T-10F12)

W. Hill, SECY (0-16G15)

H. Miller, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II A. Beach, Region III J. Caldwell. Acting, Region III L. Callan, Region IV J. Dyer, Region IV K. Perkins. Region IV/WCF0 G. Fader. INPO J. Zimmer. DOE

6 ll LIST OF ATTENDEES I

OPERATING REACTORS EVENTS FULL BRIEFING (96-13)

OCTOBER 23. 1996 l

NAME OFFICE NAME OFFICE A. Chaffee NRR W. Burton NRR K. Gray NRR G. Galletti NRR E. Goodwin NRR S. Sanchez NRR S. Koenick NRR R. Correia NRR

T. Koshy NRR J. Wilcox NRR F. Hebdon NRR J. Beall OCM/McGaffigan R. Hernan NRR C. Ogle OCM C. Doutt NRR J. Kauffman OE S. Athavale NRR TELEPHONE ATTENDANCE (AT ROLL CALL)

Reaions Resident Insoectors Region II M. Shannon, Sequoyah Region III Region IV Misc.

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ATTACHMENT 1

l l

l OPERATING REACTORS EVENTS BRIEFING 96-13 l LOCATION: 0-10B11, WHITE FLINT WEDNESDAY, OCTOBER 23, 1996 11:00 A.M.

l SEQUOYAH, UNIT 2 REACTOR TRIP WITH i

COMPLICATIONS i

l l

PRESENTED BY:

EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH ,

DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR i

Attachment 2

l' 96-13 SEQUOYAH, UNIT 2 REACTOR TRIP WITH COMPLICATIONS OCTOBER 11, 1996 PROBLEM UNEXPECTED TURBINE RUNBACK COINCIDENT WITH INABILITY TO CONTROL THREE AUXILIARY FEEDWATER (AFW) PUMPS LEAD TO MANUAL REACTOR TRIP.

l

! CAUSE l T140 FAILED PRESSURE SWITCHES AND. FEEDWATER PUMP TRIP CAUSED MAIN TURBINE RUNBACK TRANSIENT.

P00R MAINTENANCE PRACTICES COMPLICATED EVENT. 1 SAFETY SIGNIFICANCE I REACTOR TRIP WITH COMPLICATIONS.

CHALLENGE TO SAFETY SYSTEM FROM A NON-1E PRESSURE SWITCH FAILURE.

BACKGROUND LOSS OF A FEED PUMP AT POWER LEVEL > 80% PRODUCES:

- TURBINE RUNBACK;

- ANTICIPATORY START SIGNAL TO AFW SYSTEM FOR POTENTIAL LOSS OF SECONDARY HEAT SINK; AND

- AFW RUNS IN AUTOMATIC STEAM GENERATOR LEVEL CONTROL MODE.

CONTACT: S. K0ENICK, NRR/DRPM/PECB AIT: N0

REFERENCES:

10 CFR 50.72 #31138 AND SIGEVENT: YES PNO-II-96-071

SEQUOYAH, UNIT 2 96-13 l

SEQUENCE OF EVENTS e OPERATORS COMMENCED CONTROLLED PLANT SHUTDOWN IN RESPONSE TO REACTOR COOLANT PUMP (RCP) #4 SEAL #2 LEAK 0FF FLOW 0F 1.5 GPM EXCEEDING PROCEDURAL LIMIT OF 0.5 GPM.

e FOLLOWING MANUAL TRIP 0F MAIN FEEDWATER PUMP (BY PROCEDURE BELOW 50% POWER), PLANT EXPERIENCED UNEXPECTED TURBINE RUNBACK AND AUT0 START OF AFW PUMPS.

l e 10 0F 12 STEAM DUMPS OPENED ON DEMAND (PRIOR TO EVENT TWO ISOLATED BECAUSE OF LEAKAGE).

e OPERATORS MANUALLY TRIPPED REACTOR IN RESPONSE TO UNEXPECTED PLANT PERFORMANCE.

e MAIN FEEDWATER ISOLATION OCCURRED AT LOW Tavg 550 F:

ONE MFIV FAILED TO CLOSE.

, e OPERATORS WERE UNABLE TO TAKE MANUAL CONTROL OF AFW LEVEL CONTROL VALVES FOR MOTOR DRIVEN AND SPEED CONTROL FOR TURBINE DRIVEN PUMPS.

l e OPERATORS TRIPPED THE TWO MOTOR DRIVEN PUMPS AND PLACED THEM IN PULL-TO-LOCK AND THROTTLED TURBINE DRIVEN FLOW WITH LEVEL CONTROL VALVES TO FOUR STEAM GENERATORS.

o STEAM DUMPS ATTEMPT TO MODULATE PLANT TO NO LOAD Tavg (547 F) AND INTERLOCK ACTUATES TO BLOCK STEAM DUMPS AT LOWLOW Tavg (540 F).

o REACTOR COOLANT SYSTEM EXPERIENCED C00LDOWN TO APPR0XIMATELY 538 F REQUIRING OPERATORS TO EMERGENCY

! BORATE.

e SEQUOYAH, UNIT 2 96-13 e DECAY HEAT WAS REMOVED VIA STEAM DUMPS TO CONDENSER.

DISCUSSION OF COMPLICATIONS RCP #4 SEAL #2 LEAK 0FF FLOW 1.5 GPM EXCEEDING PROCEDURAL LIMIT l

CAUSE: FAILED 0-RING IN ASCO SOLEN 0ID VALVE CLOSED SEAL RETURN ISOLATION VALVE; EFFECT: OPERATORS COMMENCED SHUTDOWN IN RESPONSE TO #2 SEAL FLOW ON #4 RCP EXCEEDING PROCEDURAL LIMIT.

UNEXPECTED TURBINE RUNBACK COINCIDENT WITH AUTO START OF ALL AFW PUMPS CAUSE: 2 PRESSURE SWITCH CONTACT FAILURES (M0ISTURE INDUCED CORROSION) LOCKED-IN SIGNAL FOR > 80%

POWER:

EFFECT: MAIN FEEDWATER PUMP TRIPPED CAUSING TURBINE RUNBACK: AUTO START OF AFW, AND MDAFW FLOW CONTROL VALVES G0ING FULL OPEN AND TDAFW PUMP G0ING TO FULL SPEED ACCORDING TO DESIGN.

l UNABLE TO RESET AFW START SIGNAL BECAUSE > 80%

POWER SIGNAL NEVER CLEARED.

1 MAIN FEEDWATER ISOLATION VALVE FAILED TO CLOSE CAUSE: MOISTURE INDUCED CORROSION OF MAGNETIC BRAKE IN MOV BLOCKED ROTOR; EFFECT: MOV FAILURE (SEIZED MOTOR).

I SEQUOYAH, UNIT 2 96-13 INDICATIONS OF WATER HAMMER ON #11 STEAM DUMP LINE TO CONDENSER I CAUSE: LEVEL CONTROL FAILURE ON STEAM DUMP DRAIN TANK CAUSED CONDENSATE TO GACK UP IN STEAM DUMP LINE:

EFFECT: HANGER DAMAGE: PIPE DEFORMATION: AND TWO CRACKS ON WELD CONNECTING LINE WITH MAIN STEAM HEADER (BOTH LESS THAN TWO INCHES IN LENGTH AND 0.5  ;

l INCHES DEEP / PIPE THICKNESS NOMINAL 1.25 INCHES).  ;

l FOLLOWUP l i

e REGION II CONDUCTED SPECIAL INSPECTION TO REVIEW EVENT. .

  • REGION II TO ISSUE TIA TO NRR TO ASSESS EMERGENCY 2

FEEDWATER CONTROLS.

! l e NRR REVIEWING GENERIC IMPLICATIONS.

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i l 4

REACTOR SCRAM Reporting Period: 10/14/96 to 10/20/96 YTD YTD ABOVE BELOW YTD QAl[ PLANT & UNIT M lY_P[ ggji COMPLICATIONS jj} jj} TQTAL 10/14/96 V0GTLE 2 50 SM Equipment Failure NO 1 0 1 10/15/% PEACH BOTTOM 2 70 SA Equipment Failure NO 2 0 2 10/18/% COMANCHE PEAK 2 100 SA Equipment Failure NO 3 0 3 10/20/96 Ros!Ns0N 2 20 SA Equipment Failure NO 2 0 2 Attachment 3 Nits: Year To Date (YTD) Totals Inchde Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period ETS 10 Page:1 10/22/96

)

. . _ _ _ _ _ - = _ . _ _ . . _ _ _. . _ _ _ _ _ _ . - _ . _ . . - _..m. ._ . .

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COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES l

l l PERIOD ENDING i 10/20/96 l NUMBER 1996 1995 1994 1993 1992 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCR M CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

POWER GREATER THAN OR EQUAL 70 15%

l EQUIPMENT FAILURE 4 1.57 1.83 1.52 1.83 2.62 DESIGN / INSTALLATION ERROR 0 0.12 0.12 0.08 0.04 -

OPERATING ERROR 0 0.07 0.15 0.21 0.27 0.31 MAINTENANCE ERROR 0 0.55 0.38 0.54 0.52 0.50 l EXTERNAL 0 0.17 0.21 0.17 0.13 -

OTHER 0 0.10 0.06 -

0.02 -

Subtotal 4 2.58 2.75 2.52 2.81 3.43 l

l POWER LESS THAN 15%

i EQUIPMENT FAILURE O 0.21 0.10 0.27 0.38 0.42 l DESIGN / INSTALLATION LRROR 0 0.00 -

0.02 - -

OPERATING ERROR 0 0.10 0.13 0.08 0.13 0.15 l

MAINTENANCE ERROR 0 0.07 0.08 -

0.02 0.08

EXTERNAL 0 0.00 - - 0.04 -

OTHER 0 0.00 - - - -

I l . Subtotat 0 0.38 0.31 0.37 0.57 0.65 l

TOTAL 4 2.96 3.06 2.89 3.38 4.08 1996 1995 1994 1993 1992 NO. OF WEFTLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE j (YTD)

TOTAL AUTOMATIC SCRAMS 3 1.83 1.92 2.19 2.44 3.06 TOTAL MANUAL SCRANS 1 1.12 1.13 0.69 0.94 1.02 l

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TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF 4

ETS-14 Page: 1 10/22/96 l

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l / NOTES

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 l MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN l

IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

l 2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, i l AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

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3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

OEAB SCRAM DATA l

l Manual and Automatic Scrams for 1987 ------------------ 435 Mnnual and Automatic Scrams for 1988 ------------------ 291 Manunl and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manuel and Automatic Scrams for 1991 ------------------ 206 Manuel and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175 Manual and Automatic Scrams for 199< ------------------ 150 Manual and Automatic Scrams for 1995 ------------------ 159 Manual and Automatic Scrams for 1996 --(YTD 10/20/96)-- 124 i

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  • e.* g i

OPERATING REACTOR PLANTS SIGNIFICANT EVENTS L

No Sort Specified QUERY > Event Type SIG & Close Out Date >= 10/09/96 1 DATE OF 50.72 i PLANT & UNIT EENI NLNESER DESCRIPTION OF EVENT SIGNIFICANCE BRI FING PRESENTER DRESDEN 3 06/11/ % 0 In June 1996 et Dresden 3, a circuit breaker for a Safety-Related Cooling System NODGE V. MIGMLIGHT low-pressure coolant injection p g failed to open [

i on demand from the control room. The licensee fotnd hardened greese in the breaker mechanism.

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Attachment 4 ETS-11 Page:1 10/24/96 t

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