ML20247F199

From kanterella
Jump to navigation Jump to search
Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl
ML20247F199
Person / Time
Site: Nine Mile Point, Palo Verde, Surry, North Anna, 05000000
Issue date: 03/24/1989
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-89-012, OREM-89-12, NUDOCS 8904030356
Download: ML20247F199 (13)


Text

_ _ - - - _ _ _ - _ _ _

. g4W MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment L .

FROM: Wayne D. Lanning, Chief Events Assessment Branch i

Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING l

March 22, 1989 - MEETING 89-12 l

On March 22, 1989, an Operating Reactors Events meeting (89-12) was held to brief senior managers from NRR, AEOD, RES, Commission Staff, and Regional Offices.on events which occurred since our last meeting on March 15, 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. Enclosure 3 includes a sumary of reactor scrams and a comparison of weekly statistics with industry averages for the week ending 03/19/89. No significant events are included for input to NRC's performance indicator. program in this sumary. ,

E I

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

Enclosures:

' As stated -

cc w/ Encl.:

See Next Page DISTRIBUTION ,

Central: Files EAB Reading' File Circulating Copy, EAB Staff MLReardon, EAB D0udinot, EAB /) / 3 LKilgore, SECY /-l j 3

1 'f -

6 0FC :E B :C:EAB/D EA :  :

NAME :MLReardon :WDLa ning  :  :  :  :

DATE :03/21 /89 :03/f3/89  :  :  : ,

0FFICIAL RECORD COPY 8904030356 890324 PDR ORG NRRB

_-______________________ PDC

n .

' a

. 4 cc:

T. Murley, NRR L. Engle, NRR F. Miraglia, NRR R. Capra, NRR J. Sniezek, NRR T. Chan, NRR E. Jordan, AE00 G. Knighton, NRR J. Taylor, EDO B. Buckley, NRR E. Beckjord, RES H. Berkow, NRR W. Russell, '<I M. Ernst, R(I B. Davis, RIII R. D. Martin, R1'y J. B. Martin, RV W. Kane, RI L. Reyes, RII E. Greenman, RIII L. Callan, RIV D. Kirsch, RV S. Varga, NRR D. Crutchfield, NRR B. Boger, NRR G. Lainas, NRR G. Holahan, NRR L. Shao, NRR B. Grimes, NRR F. Congel, HRR E. Weiss, AE00 T. Martin, EDO J. Lieberman, OE J. Guttmann, SECY A. Thadani, NRR S. Rubin, AE0D J. Forsyth, INP0 R. Barrett, NRR M. Harper, AE00 R. Newlin, GPA

I e

, . g(p' "%,'94 UNITED STATES y g NUCLEAR REGULATORY COMMISSION 5 j WASHINGTON, D. C. 20555

%...../

IAR : 41M PEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FR0ti: Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING March 22, 1989 - MEETING 89-12 On March E2, 1989, an Operating Reactors Events meeting (89-12) was held to brief senior managers from NRR, AE00, RES, Comission Staff, erd Regional Offices on events which occurred since our last meeting on March 15, 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. Enclosure 3 includes a sumary of reactor scrams and a comparison of weekly statistics with industry averages for the week ending 03/19/89. No significant events are included for input to NRC's perfomance indicator program in this sumary.

W '

Wayre D. Lanning, Chi Events Assessment Bra ch Division of Operatione ents Assessment I

Enclosures:

l As stated cc w/ Encl.:

See t; ext Page l

L __ ___ ___  !

e .

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-12)

March 22, 1989 NAME ORGANIZATION NAME ORGANIZATION T. Gwynn OCM/LZ M. Davis NRR/PD5 H. Shaw NRR/ DEST H. Fields NRR/DSP J. Carter NRR/DOEA J. Mazetis RES/DSIR M. Harper AE0D/DSP B. Buckley HRR/PD2-2 H. Berkow NRR/PD2-2 G. Lainas NRR/DRP J. Clifford OEDO W. Troskoski OE D. Trimble OCH/JRC R. Capra NRR/PD1-1 V. McCree NRR/PD1-1 C. Haughney NRR/DRIS J. Zwolinski. NRR/DLPQ C. Rossi NRR/DOEA W. Lanning NRR/DOEA T. Silko AEOD M. Reardon NRR/D0EA P. Baranowsky NRR/DOEA R. Lobel NRR/DOEA i

l

)

ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 89-12 EVENTS ASSESSMENT BRANCH LOCATION: 12B-11, WHITE FLINT WEDNESDAY, MARCH 22, 1989, 11:00 A.M.

PALO VERDE UNIT 3 IN0PERABLE ADVs i'

SURRY UNIT 1 LOSS 0. SHUTDOWN COOLING NINE MILE POINT UNIT 2 . SERVICE WATER VALVE CLOSING LOGIC l

l NOTE: A VIDE 0 TAPE ON THE STEAM GENERATOR TUBE LEAK AT NORTH ANNA ,

UNIT 1 WAS *%C^ENTED AT THIS BRIEFING. THE SUBJECT HAD BEEN PREVIOUSLY BRIEFED ON 03/01/89 (89-09).

1 l  ;

s___--- --- -

. 1 9

.- ' 89-12 i I

i PALO VERDE _ UNIT 3 PLANTS WITH CCI ADVs SIMILAR TO PALO VERDE'S

)

PIBI ACTUATOR PLUG SIZE HARRIS ELECTR0 HYDRAULIC 8" WATERFORD 3 PNEUMATIC '10" ST. LUCIE 1/2 LIMITORQUE 8" CATAWBA 1/2 PNEUMATIC 8" SAN ONOFRE 2/3 8" V0GTLE 1/2 ELECTR0 HYDRAULIC 8" SOUTH TEXAS 1/2 ELECTR0 HYDRAULIC 8"

(

l . - - . - _ _ _ _ __ _ _. _ _ __ _ _ ___ _ __ _ ____

89-11 SURRY UNIT 1 LOSS OF SHUTDOWN COOLING MARCH 18, 1989 PROBLEM NO CCW FLOW PROVIDED TO RHR HEAT EXCHANGER WITH RHR FLOW FOR APPROX 10 HOURS.

.CAWif.

O INEXPERIENCED OPERATORS.

o LACK 0F INDIVIDUAL CCW OR RHR COMPONENT FLOW INDICATION.

SAFETY SIGNIFICANCE o POTENTIAL FOR REACTOR SYSTEM OVERPRESSURE AT LOW TEMPERATURE.

o LOSS OF CORE COOLING.

DISCUSSION o SURRY SHUTDOWN SINCE MID-SEPTEMBER 1988 - DECAY HEAT VERY LOW.

o EUS TESTING ON B-CCW TRAINS.

! O ALL AUX COOLING AND RHR C00 LING ON A-CCW TRAIN.

o B-RHR HEAT EXCHANGER DISCHARGE VALVE CLOSED, o AT COMPLETION OF BUS TESTING AUX COOLING LOADS RETURNED TO B-CCW TRAIN (NORMAL ALIGNMENT) B-RHR HEAT EXCHANGER DISCHARGE VALVE REMAINED CLOSEC (NORMAL ALIGNMENT).

o NEXT SHIFT (SWING) SR0 AND R0 BELIEVED BOTH RHR HEAT EXCHANGERS TO BE IN SERVICE AND ISOLATED CCW TO A-RHR HEAT EXCHANGER.

c INDIVIDUAL ELEMENT FLOW INSTRUMENTATION NOT PROVIDED FOR EITHER RHR OR CCW HEAT EXCHANGER FLOW.

o SWING SHIFT SR0 AND R0 DID NOT KNOW LOCAL MANUAL VALVE CLOSED AT B-RHR HEAT EXCHANGER DISCHARGE - DID NOT CHECK VALVE ALIGNMENT SHEET.

o NEITHER SWING SHIFT OR NIGHT SHIFT MADE UP OF NORMAL CPERATING PERSONNEL.

O HEAT UP RATE OF APPROXIMATELY l'F/HR.

o NOT CORRECTED TILL 0912 FOLLOWING SHIFT TURNOVER WITH EXPERIENCED ,

CPERATORS.

[0LLOWUP REGION TO FOLLOWUP LICENSEE'S ACTIONS.

CONTACT: W. JENSEN SIGEVENT: _hD_

REFERENCE:

10 CFR 50.72 # 15051 i

- ~ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _

P l

l l p .Zs cla t ed CC W v- -), \

j 1f h.. --DI Q--

- Pwm! A -# X L e. w a w w/-/ ,9

' Hl.'

--+

h Ik '

8-PwP O ~NY V V. -.

loop l

' ' #5 Hor L.e y S u rry RHR -

.- 89-12 NINE MILE POINT UNIT 2 SEEVICE klaTER VALVE CLCSING LOGIC FEBRUARY 23, 1989 PROBLEM LOSS OF 0FF-SITE POWER WITH A SINGLE FAILURE (0NE DIESEL) COULD LEAD TO INADECUATE COOLING WATER FLOW TO THE OTHER DIESEL.

CAUSE A DESIGN DEFICIENCY IN THE CONTROL LOGIC KEEPS VALVES OPEN WHICH SHOULD CLOSE TO ISOLATE TWO DIVISIONS OF SERVICE WATER FROM ONE ANOTHER.

SAFETY SIGNIFICANCE THE LOSS OF 0FF-SITE POWER WITH A SINGLE FAILURE COULD LEAD TO A  !

STATI0ll BLACK 0UT.  ;

DJSfUSSION o ORIGINAL DESIGN INTENDED THAT ISOLATION VALVES G0 CLOSED ON LOSS OF PCWER. )

o LOGIC CHANGED (Ill JULY 1986) T0 KEEP VALVES OPEN.

o DURING CURRENT SHUTDOWN LICENSEE IDENTIFIED PROBLEM ASSOCIATED WITH VALVES REMAINING OPEN ON LOSS OF ONE DIESEL.

O LICENSEE IDENTIFIED THAT CONTROL CIRCUITS FOR SOME SERVICE WATER VALVES NOT SINGLE FAILURE PRC0F.

o LICENSEE IS DESIGNING FIX AND WILL COMPLETE PRIOR TO RESTART.

EDLLDElE PM AND RESIDENT TO ASSESS LICENSEE'S FIX.

CONTACT: J. CARTER SIGEVENT: _YES_

REFERENCE:

MORNING REPORT 2/23/89

O! vision 1 6 OIVISION 11 28WP '

23WP 28WP S 25WP op1A 25WP 2SWP

  • PIC = Pit *PIB 'P10 *P1F 3r u ir a a ir v v

[_

I fd MOV50A WW MOV508 l _ __ 3 l '

MOV3A II MOV38

V32 gg4 .._....)<

V202A2 , , , , ,

2 V1027 MOVS3A l DIV. I HOVS3B !

& Ij! b 4 i VSSSA -

/0 S I LEGENO

p. g .I J O!Y. 1 -

CH L ER l ,

Olv. !! -

l l 8.0.P.----

X@'sn a p _ . z..; . .V)5,5 j KVS59A l DI5 CHARGE l

BAY FM-% !  ;

V54A V47A c -- * - s MOV!9A I V17 1,

....................)(

SUILQlNG MOV599K-11 V2828

,p4 O!V. hjl f l t- N -4 .

l v3868 k >4 CHILLER I

' I r - N---- 4 Nh'!gh 8

VSS2 VS59B $

t . g. g 4 O!SgARGE V473 V548 l NINE ttILE POINT UNIT 2

"A" RMR "B" RHR '

@V1924 U/C 4134 U/C 4138 DIV. 11 & ,

! O!V. 1&

111 O/O' S 111 O/O' S '

@ " A" CHILLER "B" CHILLER , , .

M0VG7A 9 f

1 uis nec 3x;#y ENCLOSURE 3 (D EElf n/10ie9 l 1

I. rut 9fCIFlC CATA CUE 5!iE LN!i e m 3; m m cgg. ,9 ,3 ,3 CAIDG !04 :ECW TOTA

!!1 151

':r!4'i' G!if 2 in' A EEFOT T 2 0 2 S/14 i' fiM5 1 D)A D,[Fei ic $ 0 $

0l!/94iCCOOP. 1 10A D; N T e 0 1 1 d,

k. la

f;

,'e

.y . ,

i i

1 I

, II . LO f 4~ 193 3 3' EB LY 5 TAT 15 TICS WITH If EU517-Y AtEF, E 5 -

'ECFN'G FCF '4 Et: ENDItG 03/ le/97

'iOW Cit'iE FGER r LMEEP 1;S9 1%E4 1997 1% 1035 CF LG L r te L f LEB LY VEB LY '49 L f SCF4 6. 5) AEKE s.EsE R.EFKE JWJWE A(Ei KE v1 D (3)(43 iiiioi

    • i-uER 15:'.

E'.UI F . AELATED 215'. 2 7.5 3.1 3.9 4.3 5.4 FEFS. FELsED( 5 ) :- l b>. O 1.4 1.0 1.3 1.8 2.0

'N e OD EP(71 > 15. O O.1 0.5 1.2 0.4 0.6 d ** Subtotal **

.19

q. . 2 5.0 4.6 c.4 6.5 8.0 h)

.'.,cf, , . *

  • FGER 15'/.

^p ED.IP. FELATED 4.15% 1 0.3 0.5 1.2 1.4 1.3

  • 1

, FEES. FEMED .15% 0 0.6 0.3 0.5 0.8 0.9 OWER <15%

. 0 0.0 0.1 0,3 0.2 0.2

    • s.ttotal **

1 U.9 0.0 2.1 2.4 2.4

  • Tctel ***

3 5.9 5.5 8.5 6.9 10.4 t% 04 US WJIO SCFW13 DFE r t.f EER AG9W 1% 6 1C97 1cE6 ivc <5

'F

. LEE}:LY ' G LY G LY LED LY kEE}rLY SO4("E H &Fi& A'4FRE A\EFKE A'.EFiE A%EFNE iTD W( Lit. Rbriti s.' O.4 1v 1.4 1.0 1.0 v4JTCMJiC SCFH G  ; 5.0 4.5 7.0 7.9 9.4 l

l l

l l

l l

1 1

NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH 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 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.

1 l

L _ _ _ _ _ _ _ _ - _ _ - - _ _ - _ _ - _