ML20245F222

Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl

ML20245F222
Person / Time
Site:	Millstone, Summer, 05000000
Issue date:	06/08/1989
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-89-021, OREM-89-21, NUDOCS 8906280064
Download: ML20245F222 (12)

Text

<

y

~.;

y -

}  ;

j

p. , .. ..

[.x L

OUN O 8 }g m

MEMORANDUM FOR: Charles E.' Rossi, Director w ,

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

SUBJECT:

' THE' OPERATING REACTORS EVENTS MEETING

! May 31,.1989 - MEETING 89 )

L l: On May 31, 1989, an Operating Reactors Events meeting (89-21) was held to brief senior managers from NRR, AE0D, RES, Commission Staff, and Regional Offices on events which occurred since our last meeting on May 31, 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 05/28/89 is t, '

presented in Enclosure 3. No significant events were identified for input 1

into the NRC performance indicator program.

l Ori::inni 51sood M.

n n. 3 . . .. .

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

Enclosures:

i As stated i

cc w/ Encl.:

See Next Page 1 l

DISTRIBUTION

l. .. Centrah Elle4  !

l EAB Reading File Circulating Copy, CAB Staff MLReardon, EAB D0udinot, EAB l' LKilgore, SECY PDR ha/

f.

ms 0 p~ ;1 4gg 1 l 3FC :EAB/DOEa, :C:EAB

.....:.9#. 2 4....:...../DOEA .......:._..........:............:............:............:........... l 1AME-:MLReardon :WDLanning  :  :  :  :  :

c.....:............:............:............:............:............:..... ......:...........

3 ATE :05/05/89 :06/ 1 /89  :  :  :  :  :

k h3"

--890628 064 8906 .

PDR ORG NRRB ,

i PDC a v

_ - _ _ - _ _ _ _ _ - _ - -________x-- ._----- - __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

'1_ f

< o,

. - ,4-

, cc:

' T. Murley, NRR: J. Hayes, NRR F.; Miraglia, NRR- E. Adensam, NRR J. Sniezek, NRR: D. Jaffe, NRR E.-Jordan, AEOD -J. Stolz, NRR' J. Taylor, ED0-E.-Beckjord,RES W. Russell, RI M. Ernst, RII B. Davis, RIII

'R. D.' Mar *'t, RIV J . ' B . Ma rc'.n , RV W. Kane, RI L. Reyes, RII E. Greenman, RIII L. Callan, RIV.

D. Kirsch, RV S. Vacga, NRR B. Boger, NRR G. Lainas, NRR L. Shao, NRR B. Grimes, NRR F. Congel, NRR E. Weiss, AE00 T. Martin, EDO ,

J. Lieberman, OE J. Guttmann, SECY A. Thadani, NRR S. Rubin, AEOD J. Forsyth, INPO R. Barrett, NRR M. Harper, AE00 R. Newlin, GPA i

_ _ _ _ _ _ __ _ _ _ . _ . . __ - _ _ . _ . - - - - - - - - l- J

8 l

h- x ~,a naq\

j(-.

g UNITED STATES NUCLEAR REGULATORY COMMISSION j W ASHINGTON. D. C. 20555 l

\,...../

i MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Wayne D. Lanning, Chief j Events Assessment Branch  !

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING May 31, 1989 - MEETING 89-21 On May 31, 1989, an Operating Reactors Events meeting (89-21) was held to brief senior inanagers from NRR, AEOD, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on May 24, 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 05/28/89 is presented in Enclosure 3. No significant events were identified for input into the NRC performance indicator program.

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

Enclosures:

As stated cc w/ Encl.:

See Ncyt Page l

I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i

p .: '

b 3

ENCLOSURE 1 l

L LIST OF ATTENDEES 1

OPERATING REACTORS EVENTS BRIEFING (89-21)

May 31, 1989 I NAME ORGANIZATION NAME ORGANIZATION J. Snierek DD:NRR E. Butcher NRR/PMAS F. Miraglia NRR/ADT A. Munno NRR/DOEA M. Boyle NRR/DRP L. Spessard AEOD/DOA W. Minners RES/DSIR J. Roe NRR/DLPQ

, R. Woodruff NRR/DOEA E. Rossi NRR/DOEA J. Stolz NRR/PD1-4 C. Ader OCM/TR J. Hayes NRR/PD2-1 G. Lainas NRR/DRP D. Trimble OCM/JRC R. Borchardt OEDO G. Hammer NRR/ DEST A. Vietti-Cook OCM/LZ P. Tam AEOD/ROAB J. Donohew NRR/ADSP J. Partlow NRR/ADP R. Lobel NRR/DOEA M. Reardon NRR/DOEA J. Carter NRR/DOEA P. Baranowsky NRR/DOEA L. Norrholm NRR/ DEST ,

_ _ _ . . _ _ . _ ~ _ . - - . . _ - - _.--.-____._ -. -._._.-____________._ ,--._ - -_ - -____ .--__--_-- _ _

l e' ,

4

. I

., EMCt.0SURE 2 i

l i

CPERATING REACTOPS EVENTS BRIEFING 89-21 i EVENTS ASSESSMENT BRANCH- f L6LATION: 12B-11, WHITE FLINT I WEDNESDAY, MAY 31, 1989, 11:00 A.M.  !

i i

. ]

SUMMER SPURIOUS OPENING 0F PRESSURIZER SAFETY VALVE

-]

MILLSTONE UNIT 1 RECIRCULATION PUMP SEAL FAILURE ,

i i

l t

I I

l l

i l

I l

l

___ _- .)

)

89-'21 SUMMER l SPURIOUS OPENING OF PRESSURIZER SAFETY VALVE MAY 28, 1989  ;

I PROBLEM A PRESSURIZER CODE SAFETY VALVE OPENED SPURIOUSLY DURING POWER l OPERATION.

CAUSE UNKNOWN.

SAFETY SIGNIFICANCE ,

LOSS OF REACTOR COOLANT AND POTENTIAL CHALLENGE TO PLANT SAFETY SYSTEMS, DISCUSSl@ ,

o REACTOR SYSTEM PRESSURE.AT 2250 PSIA, 100% POWER.

o SUDDEN LOSS OF REACTOR SYSTEM PRESSURE.

o ACOUSTIC NONITOR INDICATION OF OPEN SAFETY VALVE.

O PRESSURIZER SAFETY VALVE "C" DETERMINED TO BE OPEN BY IEC TECHNICIANS.

o AUTOMATIC / MANUAL REACTOR TRIP AT 2000 PSIG (SETPOINT OF 1870 PSIG INCREASED BY LEAD-LAG CIRCUITRY).

O FRESSURE REMAINED ABOVE SAFETY INJECTION SETPOINT.

o SAFETY VALVE "C" RESEATED, MINIMUM REACTOR COOLANT SYSTEM PRESSURE WAS 1854 PSIG.

o GNE CONDENSER DUhP VALVE STUCK OPEN, I/P CONVERTER FAILURE, CLOSED BY MANUAL ISOLATION OF AIR FROM ACTUATOR.

c LOW LEVEL IN 2 0F 3 STEAM GENERATORS.

O AUTO START OF MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS.

O REACTOR PRESSURE BEING MAINTAINED AT 1000 PSIG.

o INDICATION OF SIMMERING OF A SAFETY VALVE BEFORE "C" VALVE STUCK OPEN.

COM ACT: W JENSEN SIGEVENT YES

REFERENCE:

10 CFR 50.72 # 15732

~

TSUMhER UNTT 1-

-2 -- 21 oi.HIGH-TAILP1PElTEMPERATURE ON "E"' SAFETY VALVE ONE MONTH BEFORE' EVENT;.0NL"C" SAFETY ' VALVE ONE WEEK!BEFORE EVENT, 0: SAFETY VALVE SETPOINTS HAD BEEN SET 0FFSITE BY WESTINGHOUSE LURING PREVIOUS OUTAGE.

o. SAFETY VALVES "E" AND "C" T0 BE SENT TO WESTINGHOUSE.FOR FURTHER-EXAMINATION.

-FOL'LOWUP-REGION AND NRR WILL INVESTIGATE THE ADEGUACY OF WESTINGHOUSE SETPOINT TESTING AND OTHER FACTORS CONTRIBUTING TO SPURIOUS SAFETY

~

VALVE OPENING.

4 L 9

i J

1. .

u N-_______=__________________ __

f p

f~ +; g C9-21 7 :,

. MILLSTONE UNIT 1 RECIRCULATION PUMP SEAL FA] LURE

" MAY 29,,1989

' PROBLEM'

_ UNIDENTIFIED LEAK. RATE REACHED 44 GPM.

CAUSE J r BOTH SEALS OhERECIRCULATION PUMP "A" FAILED.

y SAFETY SIGNIFICANCE

' DEGRADATION OF PRlhARY COOLANT PRESSURE BOUNDARY.

DISCUSSION o THE RECIRCULATION PUMPS WERE MANUFACTURED BY BYRON-JACKSON.

o. THE SEALS WERE REPLACED DURING THE LAST OUTAGE.

o. STARTUP OCCURRED ON 05/26/89. ,

o [C0 3.GD RECUlRES THAT UNIDENTIFIED LEAKAGE NOT EXCEED 2.5 GPM AND THAT ILENTIFIED LEAKAGE NOT EXCEED 25 GPM. IF THESE CONDITIONS CANNOT BE hET, THE LICENSEE MUST INITIATE AN ORDERLY

. SHUTDOWN AND BE IN COLD SHUTDOWN WITHIN 24 HOURS.

o 0N-05/29/89 AT 14:50, THE POWER LEVEL WAS 80% AND THE UNIDENTIFIED LEAK RATE WAS 8.5 GPM.

o :AT 16:15, THE POWER LEVEL WAS 75% AND THE UNIDENTIFIED LEAK RATE WAS 8.5 GPM. THE LICENSEE BELIEVED THAT THE SOURCE WAS

" RESIDUAL WATER" AND THAT THE UNIDENTIFIED LEAK RATE WOULD DECREASE.

O AT 16:59, ThE POWER LEVEL WAS 55%.

o AT 18:13, THE POWER LEVEL WAS 20%.

o AT 21:00, THE UNIDENTIFIED LEAK RATE WAS 44 GPM AS MEASURED BY PUMPING THE FLOOR DRAIN AND ECUIPMENT SUMPS.

0 THE E0P-REQUIRES DECLARATION OF AN ALERT IF THE UNIDENTIFIED LEAK RATE REACHES 50 GPM.

c. AT 22:00, Tf!E UNIDENTIFIED LEAK RATE WAS 42 GPM. ,

c AT 22:59, THE ROCS WERE INSERTED.

CCNTACT: R. WOODRUFF SICEVENT _YIS_ '

REFERENCE:

10 CFR 50.72 # 35741 AND MORNING REPORT 05/30/89.

1 L__________.._ _ ..

,kl,LLETChEUhlT1 -E- 09-21 c- AT 23:33, THE UNIDENTIFIED LEAK RATE WAS 30 GPM, REACTOR COOLANT l SYSTEM PRESSURE WAS 22: PSIG, AND THE TEMPERATURE WAS 395'F.

I o ALSO AT 23:33, THE LICENSEE REPORTED THAT THE CUTBOARD SEAL HAD CCKPLETELY FAILEP AND THE INE0ARD SEAL HAD PARTIALLY FAILED.

A LREAKDOWN LUSHlhG BETWEEN THE SEALS IS INTENDED TO LIMIT L LEAKAGE TO 00 GPM WITH COMPLETE FAILURE OF BOTH SEALS.

L o ON 05/30/89 AT 03:45, THE UNIDENTIFIED LEAK RATE WAS 9.5 GPM.

o AT 04:16, THE UNUSUAL EVENT WAS TERM!NATED WHEN COLD SHUTDOWN MCDE WAS ENTERED.

o CONTAINMENT WAS INITIALLY LEINERTED THRU THE STANDLY GAS TREATMENT SYSTEM.

EDLLDEUE OEAB WILL DETERMINE WHETHER THE SEAL PROBLEM IS GENERIC, 0GCB WILL ISSUE AN INFORMATION NOTICE, IF APPROPRIATE.

e G

l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ i

~

MACT03 SCRAQ EUZARY EiiCLOSURE 3

,- , WEEK ENDINS 05/28/89

!. PLANT SPECIFIC LATA DATE SITE UNIT POWER S!6NAL CAUSE COMPLI- YTD YTD YTD CATIONS APOVE FELOW TOTAL 151 151 05/22/89 FARLEY 2 35 A PEFSDNNEL ND 1 0 1 Of/22'Bi VCGTLE 2 12 A PERSONNEL NC 2 1 3 05/2t/B9 CLINTON 1 20 M EQUIP"ENT ND 1 0 1 05/26/89 FFAIRIE ISLAND 2 100 A EQUIPMENT ND 1 0 1 05/27/B9 PEAVER VALLEY 2 0A PERSONNEL NO 1 1 2 05/27!B9 FARLEY 2 90 A EQUIPMENT NO 2 0 2 05/2B/S9 SUM?ER 1 100 M EDUIPMENT YES 2 0 2

SUMMARY

OF COMPLICAT10NS  !

t- ElTE UNIT COMPLICATIONS SUMMER 1 STEAM DUMP VALVE STUCK 0 FEN i

l

-_-.-_.-__-_--Y

I

~

NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF S0.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH L MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE

-ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN Id ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

t l

i 3.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL

. DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL-PROBLEMS.

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

4 i

i

r

}{-

z.

MEMORANDUM FOR: Charles E. ' Rossi, Director Division of Operational Events Assessment ,

FROM: Weyne'D. Lanning, Chief Events Assessment Branch-Division of_ Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING

-May 31, 1989 - MEETING 89-21 On May 31, 1989, an Operating Reactors Events meeting (89-21) was held to brief senior managers from NRR, AE0D, RES, Commission Staff, and Regional e Offices on events which occurred since our last meeting on May 31._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 05/28/89 is presented in Enclosure 3. No significant events were identified for input into the NRC performance indicator program.

Wayne D. Lanning, Chief Events Assessment Branch '

Division of Operational Events Assessment

Enclosures:

As stated

- cc w/ Encl.:

See Next Page DISTRIBUTION Central File EAB Reading File Circulatir.g Copy, EA8 Staff MLReardon, EAB D0udinot, EA8 LKilgore, SECY PDR 0FC :EAB/DSJA :C:EAB/DOEA :  :  :  :  :

. . . . . : # WA, . . . : . . . . . . . . . . . . : . . . . . . . . . . _ _ : _ . . . . . . . . . . . : - _ _ . . . . . . . . . : . . . . . . . . . . . . : . . . . . . . . . . .

NAME :MLReardon :WDLanning  :  :  :  :  :

DATE :05/0f7/89 :06/ /89  :  :  :  :  :

OFFICIAL RECORD COPY I