ML20245H801

From kanterella
Revision as of 21:43, 14 February 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl
ML20245H801
Person / Time
Site: Browns Ferry, Zion, 05000000
Issue date: 02/23/1989
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-89-008, OREM-89-8, NUDOCS 8903060009
Download: ML20245H801 (13)


Text

_.

.J- ..

.4 f, ;

-n , -FEB t? 16 :

e MEM0R' ANDOM '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 z":

. February 22, 1989 - MEETING 89-08 On February 22, 1989, an Operating Reactors Events meeting (89-08) was held to brief senior managers from NRR, AE0D, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on February 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 one significant. event identified for input to NRC's performance indicator program and'a sumary of reactor scrams for the week ending 02/19/89.

p,41W &L- .,

.. n , ,, ,-

Wayne D. Lanning, Chief >

Events Assessment Branch ~

Division of Operational Events Assessment 9

Enclosures:

.As stated cc w/ Encl.:-

See Next Page DISTRIBUTION .

$Centralfilew

-EAB Reading File l / ,/ 'h. ).'.

Circulating Copy EAB Staff MLReardon, EAB D0udinot, EAB T I' .;

LKilgore, SECY- / /-

PDR / j}4'jf]'i j?!

0FC :EAB :C  :  :  :  :  : -

.- :. g:EAB/DDEA ..:.........-..:..--....-..

NAME :ML ardon- :WDLanning.  :  :  :

tDATE :02/2 7./89 :02////89  :  : J OFFICIAL RECORD COPY 0903060009'890223 PDR ORG NRRB-PDC

-

  • 1

!' t 5 ,

.CC:' .

l I

T. Murley, NRR G. Gears, NRR .

F. Miraglia, NRR_ D. Muller, NRR

J. Sniezek, NRR S. Black, NRR~

E. Jordan AEOD C. Patel, 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,.R1  !

L. Reyes', RII E. Greenman, RIII L. Callan, RIV' D. Kirsch, RV S. Varga, NRR D. Crutchfield, NRR B. Boger, NRR G. Lainas,llRR G.'Holahan,ilRR-L. Shao,-NRR B.' Grimes, NPR.

F. Congel, NRR E. Weiss, AEOD

'T. tiartin, EDO .

J. Lieberman, OE J.= Gu_ttmann,'SECY A. Thadani, NRR

-S. Rubin, AE0D:

J. Forsyth', INPO R. Barrett,llRR

- M. Harper, AE00 R. Newlin, GPA

6' UNITED STATES

(; '

4 NUCLEAR REGULATORY COMMISSION 5 ;j' WASHINGTON, D. C. 20S$5 i

\, . . . . /

r y p, y

  • ib MEMORANDUM FOR: Charles E. Rossi, Director

-Division of Operational Events Assessment .

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

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING February 22, 1989 - MEETING 89-06 ,

On February 22, 1989, an Operating Reactors Events meeting'(89-08) was held to brief senior managers fron NRR, AE0D, RES, Commission Staff, and Regional' Offices on events which occurred since our last meeting on February 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 one significant event identified for input to NRC's performance indicator program and a summqry of reactor scrams for the week ending 02/19/89. /

/ d 21 Way n h

D. Lanning, Chief -

Events Assessment Branch Division of Operationa% vents Assessment Enclosut es:

As stated

. cc w/ Encl.:

See flext Page

ENCLOSURE 1 LIST 0F ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-08)'

February 22, 1989-NAME- ORGANIZATION' NAME ~0 ORGANIZATION ~

M. Harper ~ AEOD P. Baranowsky~

NRR/00EA

-J. Guillen -NRR/DOEA C. Rossi -NRR/DOEA G. Holahan- NRR/DRSP W. Minners RES/DSIR M. Reardon NRR/DOEA E. Adensam NRR/DRP E. Murphy' 'NRR/ DEST L. 2 err NRR/DRSP C. Haughney NRR/CRIS -D. Trimble OCM/JRC W. Lanning NRR/DOEA D. Muller NRR/DRSP B. Grimes. NRR/DRIS C. Patel NRR/DRSP D. Moran. NRR/OSP l

l i l

\

1 l _

\

.c 3.. .

. ENCLOSURE 2-4 I '.

..(

_0PERATlhG REACTORS EVENTS BRIEFING 89-08 EVENTS ASSESSMENT BRANCH

-LOCATION: 10E-11, WHITE FLINT' WEDNESDAY, FEBRUARY- 22, 1989,.11:00 A.M.

BROWNS FERRY UhlTS 1, 2, E 3 EMERGENCY EQUIPMENT COOLING WATER DISCHARGE PIPING ZION UNIT 2 PROBLEMS AT Z10N UNIT 2 GENERIC ISSUE PART 21 UPDATE ASEA BROWN BOVERI K-LINE Cir.CUIT BREAKERS i

89-08

- BROWNS FERRY UNITS 1, 2, 8 3 EbERGENCY EQUIPhENT COOLING WATER DISCHARGE PIPING FEBRUARY 8, 1989 EBDBLER EFFLUENTS FROM CERTAIN EECW CHILLERS AND AIR CONDITIONING UNITS ARE ROUTED TO RAW COOLING WATER AND CIRCULATING WATER PIPING WHICH IS NOT SEISMIC CLASS 1.

CAUSE BREAKDOWN OF GA DURING FLANT DESIGN AND CONSTRUCTION.

SAFETY SIGNIFifjE E CERTAlh 4160 AND 480 V BOARDS AND CERTAIN CORE SPRAY, RHR, RHR SERVICE WATER, AhL FIRE PUMPS WERE DECLARED IN0PERABLE FOR THE VARIOUS UNITS. FOR UNIT 2, CERTAIN ECCS MOVs AND THEREFORE ECCS WERE DECLARED INOPERABLE.

DISCUSS 10h o FSAR 10.10.2.2 COMMITS TO SEISMIC CLASS 1 DESIGN FOR THE EECW SYSTEM.

O AS A RESULT OF THE DESIGN BASIS VERIFICATION PROGRAM, THE LICENSEE FCUND THAT THREE OF SEVERAL TRAINS OF EECW DISCHARCE TO STEEL, VITRIFIED CLAY, AND CONCRETE PIPING THAT HAS NOT BEEN QUALIFIED AS SEISMIC CLASS 1.

c THE RAW C0 CLING WATER AND CIRCULATING WATER SYSTEMS DO NOT HAVE SAFETY-RELATED FUNCTIONS OTHER THAN TRANSPORT OF EFFLUENT FROM THESE THREE TRAINS OF EECW.

o THIS PROBLEM WAS DISCOVERED AS PART OF THE LICENSEE's DESIGN BASELINE VERIFICATION PRCCRAM, o THE LICENSEE IS DEVELOPING SOLUTIONS TO THIS AND OTliER PROBLEMS.

o THE LICENSEE's ACTIONS ARE LNDER ACTIVE REVIEW BY OSP.

EDLLDEDE THE PROJECT MANAGER OF ERChNS FERRY HAS CONTACTED THE RESIDENT INSPECTOR FOR PEACH E0TT0h TO DETERMINE WHETHER PEACH BOTTON HAS THE SAME PROELEN.

R. WOODRUFF SIDEVELJ YES CON 1ACT:

REFERENCE:

1C CFR 50.72 # 146L5 1


y-------_ _ , _ _ _ _ , . . _ _ __ _ _ _ _

e

, i p i I.'N Y '

a f

g.

.s d d v

a v.

- c g ,e y y E

[

6 5

$a { ,c _______

-  : j t________ g

) ___

g -

8

-__-_b_g__ _c pi m y __

g y '

u. d M- , ,

g g) st..----___ ..1 y U

I e a 3 E J gg g

w3n -l 7 e

j $,

5 .

L _ _ _.. _ _ __ _j h l e s" l 6 v3

- p.u 1

t Q  !

i e e I I 6 4 ,

l li l

I g% l g l )2 p . as \

m o!s 3 j a

! x u.

s

.gs J

t k a

i 89-08 {

~

Z10N UNIT 2 PJLOREMS AT ZION UNIT 2 PROBLEMS o S/G TUBE NOT STABIllZED BEFORE PLUGGING.

O RCS LEAKAGE THROUGH PRESSURIZER SPRAY VALVES DUE TO LOOSE PACKING.

MFETY SIGNIFICANCE o POTENTIAL FOR NON-STABILIZED PLUGGED TUBE TO CAUSE DAMAGE TO ADJACENT LlVE TUBES.

c fl0N-ISOLABLE RCS LEAK.

DISCUSS 10B o ON JANUARY 15, 1989, STEAM GENERATOR TUBE LEAK RECulRED UNIT 2 SHUTDOWN.

ENHANCED EDDY CURRENT TESTING IDENTIFIES THROUGH WALL CIRCUMFERENTIAL CRACK IN R0W ONE OF S/G 2A U-BEND.

LICENSEE PLUGGED TULE WITHOUT STABILIZING IT. UNIT 2 RESTARTED ON JANUARY 30, 1989.

LICEllSEE TO SUBMIT ANALYSIS Oh ABOUT FEBRUARY 28 AND CLOSELY N0NITOR PRIMARY TO SEC0hDARY LEAKAGE BY DAILY SAMPLING.

PRINARY TO SECONDARY LEAKAGE TECH SPECS LIMITS ARE 500 GALLONS PER DAY. h0 ADMINISTRATIVE LIMITS FOR LEAKAGE.

o FEBRUARY 20, IS89, RCS LEAKAGE OF 9.2 GFM FROM PRESSURIZER SPRAY VALVE PACKING RECblRED UNIT 2 SHUTDOWN.

TIGHTENING OF THE PACKING ON BOTH PRESSURIZER SPRAY VALVES STGPPED THE LEAK.

UNIT 2 RESTARTED ON FEBRUARY 22, 1589.

~

_ FOLLOWUP o MATERIALS ENGINEERING TO REVIEW LICENSEE's ANALYSIS FOR CONTINUED OPERATION UNTIL NEXT REFUELING OUTAGE.

l 0 REGION 111 h0NITCRING LICENSEE's ACTION.

C0hTACT: L. OLDINOT SIGEVENI _10_

REFERENCE. 10 CFR 50.72 616804 AN1' MORNING REPCRTS 01/25/85 AhD CE i/' l /89 l

_ _ _j

, .. . l 89-08

)

GENERIC ISSUE 1 PART 211 UPDATE - ASEA BR0hN BOVERI K-LINE'CIRCulT BREAKERS PROBLEM '

. POTENTIAL FAILURE OF ASEA BROWN B0 VERI K-LINE CIRCulT BREAKERS

.(CBs) TO CLOSE DURING SEVERE SEISMIC CONDITIONS-(ELECTRICALLY- 1 OPERATED K-225 THROUGil K-2000 CBs),

f CAUSE 1 MOVEMENT OF SLOW h.0SE LEVER COULD JAh CIRCulT BREAKER CLOSING MECHANISM,

' SAFETY SIGNIFICANCE FAILURE OF SAFETY-REL ATED CIRCUIT BREAKER TO CLOSE ON DEMAND. l 1

DJSCUSSION o BROWN'B0 VERI SULMITTED ADDITIONAL INFORMATION RECARDING DEFICIENCY IN K-LINE CBs DATED FEBRUARY 16, 1989, e ' EXTENSIVE TESTING CONDUCTED AT WYLE LAB 3 IN 1974 GN SAMPLE K-LINE CBs.

o TESTING PROGRAM CONSISTEL GF 123 TEST RUNS WITH VARYING SIESMIC CONDITIONS.

o DURING-TEST RUN NUMBER 100, Ot.E K-1600 CB JAMMED WHEN DEMANDED l TO CLOSE (KhlCB C0f!SISTED OF SIDE-TO-S!DE SINE DWELL AT 23 hEETZ, APPLITUIE 0.5 G, DURATION GREATER THAN 20 SECONDS),

o DURING TEST RUN NUVEER 101, A SECOND K-1600 CL FAILED TO CLOSE ON DEMAND (h'HICH CCNSISTED OF SIDE-TO-SIDE SINE DWELL AT 30 HERT2, ,

AKPLITULE 0.36 G, DURATION GREATER THAN 20 SECONDS).

c TEST CONDITIONS WERE VERY SEVERE, NOT ORDINARILY PERFORMED DURING SEISKlC TESTING, t.ND NOT LIKELY TO BE ENCOUNTERED IN KGST LOCATIONS.

o BROWN B0 VERI LATER DETERhlfiED THAT CB FAILURES DljE TO VIBRATION INDUCED MOVEFENT OF SL0h' CLOSE LEVER TilAT JAMMEE THE CLOSING MECHANISI'..

CONTACT: J. GUILLEl;

REFERENCE:

10 CFR PART 21 fl0llFICATICtS, 10 CFR EC.72 # 14743 i

GENERIC ISSUE ' 89 ,

o BROWN.BOVERI HAS INFORMED-UTILITIES WHO PURCHASED SUBJECT K-LINE Cbs AS' SAFETY-P. ELATED OF. DEFICIENCY.VIA' JANUARY 23 AND FEBRUARY'16, 1989 LETTERS.

o -BROWN E0 VERI RECOMMENDS THAT REB 0UND SPRING BE ADDED TO SLOW CLOSE LEVER ON CBs DELIVERED PRIOR TO MID-197Li TO AVOID ANY POTENTIAL MALFUNCTION.

E0LLOM!E GENERIC COMMUNICATIONS PREPARING INFORMATION NOTICE TO INFORM ALL LICENSEES 0F DEFICIENCY, SPECIFICALLY COMMERCIAL GRADE CUSTOMERS-e 1

-- .--- - - - - - - - - - - _ - -- _ --------_- -_-_ _ _ _ _ _ _ D

~

Pi;r N
,'  ! ,

)

.:02/:lllI9.

FERFCR3ANCE INDICATCRS SIGNIFICANT EVENTS ENC 1.0SURE 3

)

~FLANT NA.92 E'!ENT EVENT EE5CRIFTICN GTR SIGNIF CANCE we f, i IRC AS FEkRY 1,2, I 02/05/89 ALL FARTS OF THE EMEEBE'CY EG31FMENT CC11NS WATER SYSTEM 5 0 FDIENTIAL FOR DR ACT' L LESRCATICN

!. ARE NOT SEISMIC CLASS I FER THE CCMMITMENT IN FSAR DF SAFETY-RELATED EC'JIFMENT, 10.10.2.2 k

{

l, e

d I

l

?? 4-qy %c  ; '

c. ,

. 3 .,. w _n a: .

~

t

' g_)

Y ,

1EACTOR SCRAM

SUMMARY

.y.

WEEK ENDING 02/19/89;

1. PLANT SPECIFIC DATA DATE : ' SITE' '0N11 PDWER S]GNAL CAUSE COMPLI- YTD' YTD YTD CAilDNS ABOYE BELON '101AL-W ,151 151 02/13/E9'BEAVERVALLEY l' 90 A EDUIPMENT, NO-- 2' 0 '2-02/16/89 FALD VERDE . 2 100 A E00lPMENT NO -1 0 ~1
02/10/B9 SALEM.. '1 0A PERSDNNEL- ND 1 1 '2 I

1.

4 O

fa

_ _ - _ - - . = _ _ - _ - _ _ _ _ _ _ - _ - - - _ _ _ _ _ _ _ _ - __ _ _ _ _ - - _ - - - - _ _ . __ _ __ ._

. NOTES 1

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

MIDNIGHT SUNDAY. SCRANS ARE DEFIt;ED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION,-AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLAN!4ED SHUTDOWN IN ACCORCANCE l WITH A PLANT PROCEDURE. THERE AD.E 111 REACTORS HOLDING AN

. OPERATING LICENSE.

)

2. COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3. PERS0fillEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4. "0THER" INCLUDES AUTOMATIC SCR/(MS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNItG), SYSTEM DESIGH, OR UNKNOWN CAUSE.

4 i

l

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