ML20006E725

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Summary of Operating Reactors Events Meeting 90-03 on 900207.List of Attendees & Viewgraphs Encl
ML20006E725
Person / Time
Site: Susquehanna, Rancho Seco, 05000000
Issue date: 02/12/1990
From: Baranowsky P
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-90-003, OREM-90-3, NUDOCS 9002260277
Download: ML20006E725 (19)
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Feb'ruary 12,-1990 r:

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1 LMEMORANDUM FOR:

Charles E. Rossi Director Division of Operational Events Assessment FROM:

Patrick W. Baranowsky, Acting Chief Events Assessment Branch Division of Operational Events Assessment-

SUBJECT:

-THE OPERATING REACTORS EVENTS MEETING February 7,1990 - MEETING 90 03 On February'7, 1990,-we conducted an Operating Reactors Events meeting

'(90-03) to brief senior managers from NRR, AE0D, ACRS, Commission staff, and

' regional offices on selected events that occurred since our last meeting on January 24.-1990.- Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the weeks ending.

02/04/90 and 01/28/90. No significant events were identified for input into the NRC performance indicator program.

/s/

e Patrick W. Baranowskyi Acting Chief-Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

-See Next Page

-DISTRIBUTION

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.c .;3 of - N( f /" ". 0 UNITED STATES NUCLEAR REGULATORY COMMISSION h' jg 'I.. WASHINGTON, D C. 20555 - g f .. i4 Fcbruary 12,'1990 j i L 1 MEMORANDUM FOR: Charles E. Rossi, Director Division of.0perational Events Assessment' b "FROM: Patrick W. Baranowsky, Acting Chief L Events Assessment Branch L Division of Operational Events Assessment I

SUBJECT:

THE OPERATINC REACTORS EVENTS MEETING L February 7,1990 - MEETIllG 90-03 On February 7, 1990, we conducted an Operating Reactors Events meeting- '(90-03).to brief senior managers from NRR, AEOD, ACRS, Commission staff, and i regional. offices on_ selected events that occurred since our last meeting-i on January 24, 1990. Enclosure-1 lists the attendees. presents the significant elements of the discussed events. L contains a summary of reactor scrams for the weeks ending L 02/04/30 and 01/28/90. No significant events were identified for input 'l into the NRC performance indicator program. M Patrick W. ~Baranowsky, Acting ief Events Assessment Branch Division of' Operational Events-Assessment .l

Enclosures:

As stated-u cc w/ Encl.:- [ See Next Page L I h l l' l. t

= 7 (,1 w 3 y- ,-,i If ' ,k l l W i T. Murley NRR-. S.,Reynolds, NRR 'cc:: F.;Miraglia, NRR F. Hebdon, NRR- ' t - J.-Sniezek, NRR '.A. Thadani, NRR-J. Partlow, NRR W. Butler, NRR LE.. Jordan, AEOD N J. Taylor,-EDO- 'E. BeckJord, RES W. Russell, RI-S.. Ebneter, RII 5 B. Davis, RIII-LR.D. Martin, RIV- -J.B. Martin, RV: -9 W. Kane, RI .L. Reyes,'RII: -w E.;Greenman, RIII-J.;Milhoan,.RIV. R. - Zinnerman, RV s O S. Varga,'NRR B. Boger, NRR-' G. Lainas, NRR~ J >:F. Congel, NRR-E. Weiss, AEOD' B. Clayton, EDO n ..J.i !.ieberman, OE : J. Guttmann, SECY' lA..Thadani',1NRR e ~J. Richardson. NRR S.' Rubin,'AE0D J. Forsyth, INPO 4 R. Barrett, NRR. - t "; Harper,.AEOS th. Newlin, GPA J. Roe, NRR-H. Alderman, ACRS -}e i >[. m;jn 5% e f n w

l - */ J 1 ENCLOSURE 1 i LIST OF ATTENDEES l OPERATING REACTORS EVENTS BRIEFING (90-03) U February 7, 1990 NAME ORGANIZATION-NAME ORGANIZATION iT. Murley NRR/DONRR J. Roe: NRR/DLPQ-W. Butler NRR/PD1 C..Hehl RII W. Haass-NRR/DRIS T. Novak AEOD i L. Norrholm -OCM/KC R. Tripathi GPA/CA .H. Alderman

  • ACRS W. Troskoski OE J. Carter' NRR/D0EA P. Baranowsky NRR/DOEA f

J. Dyer OEDO R. McIntyre NRR/DRIS S. Reynolds-NRR/PD K. Naidu NRR/RVIB R. Erickson NRR/DREP H. Ornstein AEOD/ROAB G. Lainas NRR/DRP R. Perfetti 10E D.'Fischer-NRR/DOEA M. Reardon NRR/DOEA ,R. Woodruff NRR/DOEA L. P11sco NRR/DONRR

31. Chiramal AEOD/ROAB C. Thomas

'NRR/DLPQ. L ': j ;

i*,l JM ENCLOSURE 2- ^) + ,m t h 0PERATING REACTORS EVENTS BRIEFING 90-03 EVENTS ASSESSMENT BRANCH LOCATION:- 12B-11, WHITE FLINT-WEDNESDAY, FEBRUARY 7,.1990,-11:00 A.M. f RANCHO SECO TRANSFER OF SPENT FUEL POOL WATER TO THE BWST 7 SUSQUEHANNA UNIT 1 LOSS OF SHUTDOWN COOLING i - GENERIC ISSUE. . SOLEN 0ID VALVE PROBLEM - ,i AVC NOTIFICATION .[ t 1 l,

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[ 03-Y RANCHO SECO . TRANSFER OF SPENT FUEL POOL WATER-TO THE BWST JANUARY. 27, 1990 ,o PROBLEML WATER FROM:THE SPENT FUEL POOL WAS INADVERTENTLY TRANSFERRED TO THE-B0 RATED WATER' STORAGE TANK. CAUSE' IMPROPER VALVE ALIGNMENT. SAFETY SIGNIFICANCEJ o POTENTIAL TECHNICAL SPECIFICATIONS VIOLATION.

o. EVENT P0INTS OUT INATTENTIVENESS OF-OPERATING PERSONNEL.
DISCUSSION o FOR A?TWO HOUR PERIOD ONLJANUARY 27, 1990, APPROXIMATELY 20,000 GALS OF B0 RATED WATER FROM THE SPENT FUEL P0OL (SFP) WAS DISCHARGED TO THE B0 RATED WATER STORAGE TANK.(BWST)'.

o TRANSFER OCCURREDEDUE TO: IMPROPER ALIGNMENT OF SFP AND THE BWST. DEMINERALIZER SYSTEMS VALVES :(VALVE MISALIGNMENT INVOLVING THESE-TWOLSYSTEMS ALSO OCCURRED ON 12/21/89, BUT NO INVENTORY TRANSFER RESULTED). 0: THEl LEVEL IN THE SFP DECREASED 2 FT (FROM.38 FT TO 36 FT). 'o RADIATION: LEVELS REMAINED-AT LESS THAN-1 MR PER HOUR. Lo TECH SPECS REQUIRE 23 FEET OF WATER (37 FT LEVEL) AB0VE TOP 0F FUEL DR RAD LEVELS BELOW 2.5-MR PER HOUR AT THE P0OL SURFACE. o BECAUSE 0F A' FAILED. ANNUNCIATOR CONTROL SWITCH IN THE CONTROL ROOM,'N0. LOW LEVEL ALARM WAS RECEIVED, AS EXPECTED, WHEN POOL -LEVEL DECREASED BELOW 37 FT. o THE LONE CONTROL ROOM OPERATOR ~BECAME AWARE OF LEVEL DROP WHEN THEY OBSERVED THE VIDE 0 CAMERA WHICH WAS MONITORING THE SFP LEVEL; -CONTACT: N. FIELDS SIGEVENT: N0

REFERENCE:

MORNING REPORT OF FEBRUARY 5, 1990 3

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s. c f Tc.c ; RANCH lSEC0!

2-90-03 /r

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2*F0LLOWUPL ~o:TtlE: REGION-IS FOLLOWING LlCENSEE'S ACTIONS FOR ADDRESSING THE-CAUSES F0P,;THE-IMPROPER VALVE LINEUPS, ,J - o N0: ADDITIONAL FOLLOWUP BY NRR 1S' CONTEMPLATED, m.. s h o -q i .l L:' 'I s ,.. # \\ 5,

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kg 4 j $L 90-03: SUSQUEHANNA UNIT 1 LOSS 0F SHUTDOWN-C00Lilin 1 2/3/90 PROBLEM- ,? TWO DAYS AFTER SHUTDOWN, SHUTDOWN COOLING WAS LOST. CAUSE A DEGRADED NON-1E CIRCulT BREAKER CAUSED LOSS OF POWER TO RPS 7 BUS "B".-. SAFETY SIGNIFICANCE MAX RCS-TEMPERATURE AND PRESSURE WERE 252 F AND 31 PSIA. DISCUSSION 0-ON'02/01/90, UNIT-1 WAS SHUTDOWN TO CORRECT AN EHC LEAK TO AN-INTERCEPT--VALVE. o AT 5:25 P.M. ON-02/03/90, DURING SURVEILLANCE OF ALTERNATE POWER TO RPS BUS'"B", INCREASED-LEAKAGE CURRENT TO GROUND THROUGH A DEGRADED INSULATOR ON-A LOAD BREAKER CAUSED' LOSS OF THE BUS, o RPS "B" SUPPLIES POWER TO THE LOGIC FOR GROUP B ISOLATION VALVES. o THE lSOLATION VALVES IN-THE RHR: DROP LINE CLOSED AND COULD NOT-7 BE RE0PENED REMOTELY.- o TEMPERATURE ROSE AT 32 F/ HOUR, AND1AN ALERT WAS DECLARED AT 5:53 P.M. .o MAKEUP WAS PROVIDED BY THE CRD' PUMPS. oil', 2 AND THEN 3 SRVs WERE OPENED TO RELIEVE RCS PRESSURE TO THE A . SUPPRESSION P00L. .o SUPPRESSION POOL COOLING WAS INITIATED. o_AT.7:45 P.M., THE' DEGRADED BREAKER WAS REPLACED AND POWER WAS RESTORED TO RPS "B". CONTACT: R. WOODRUFF SIGEVENT: NO s

REFERENCES:

10 CFR 50.72 # 17688 AND PNO-1-90-08

jSS0VEHANNA1 UNIT 1 90-03 i ' DISCUSSION (CONTINUEDb o THE RHR. FILL AND' VENT PROCEDURE WAS EXECUTED AND SHUTDOWN COOLING: WAS RESTORED AT 11:02 P.M. o AT 12:15 A.M.,:RCS TEMPERATURE WAS REDUCED TO LESS THAN 200 F, o AT.12:25 A.M., THE ALERT WAS TERMINATED, o PREVIOUSLY, THERE HAD BEEN THREE OTHER INSTANCES OF INSULATOR' l DEGRADATION,ON THE,SAME.OF SIMILAR: LOAD BREAKERS. FOLLOWUP 'THE REGION IS-DISPATCHING AN ELECTRICAL SPECIALIST TO-THE SITE. 7 ,4 ?

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SOLEN 0ID OPERATED VALVE PROBLEM - AVC NOTIFICATION FEBRUARY-1, 1990 m-u P_RQE 21 ALDIFFERENT FAILURE MECHANISM WAS FOUND'FOR S0LEN0ID OPERATED' VALVESL(S0Vs) USED T0. CONTROL SAFETY-RELATED COMP 0NENTS.

.CAUSE-MAINTENANCE PERFORMED ON S0Vs DID'NOT UTILIZE THE PROPER PROCEDURE '0R EQUIPMENT FOR THE S0V/ PARTS INVOLVED. SAFETY SIGNIFICANCE- .A-POTENTIAL ~ COMMON MODE MECHANICAL BINDING 0F-0NE REDUNDANT ,S0V-IN THE ENERGlZED POSITION COULD OCCUR DURING MAINTENANCE LAND MAKE.AN MSIV OR MSRV IN0PERABLE. i< ! DISCUSSION-o'S0Vs USEDLTO CONTROL OPERATION OF:MSIV/MSRV. 1 .o-MSIV/MSRV ARE SAFETY-RELATED COMP 0NENTS. ~o-S0V-DESIGN WAS CHANGED. REQUIRED USE OF SPANNER WRENCH. -t e-- Lo AEVISED MAINTENANCE PROCEDURE AND REQUIRED EQUIPMENT'NOT SENT' [ iT.0 LICENSEES. ,'o:INCOMPATIBlLITY OF A LUBRICANT WITH ALUMINUM.. ?o SOVs ARE ONE PART 0F Al COMPLEX PROCUREMENT PROCESS PACKAGE. oiTHIS PACKAGE NAY NOT BE FULLY INTEGRATED: LOUALIFICATION CERTIFICATION b, EQLLOR k.

INLBEING PREPARED

'AE0D CASE STUDY NEARLY COMPLETE .POSSIBLE ADDITIONAL VENDOR INSPECTION . CONTACT: J. CARTER t

REFERENCES:

10 CFR 50.72 #17676 h :

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90-03; 1

a LS_IV'0R>MSRV SUPPLIER; b 3 SOURCE-0F SUPPLY:. DIRECT FROM VENDOR-GENERAL ELECTRIC-g 1 STEAM CONTAINING VALVE BODY: . CROSBY 3.. ATWOOD & MORRILL

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PNEUMATIC-CONTROL ASSEMBLY:- AUTOMATIC VALVE CORP 3 SOLEN 0ID OPERATED' VALVE: AUTOMATIC: SWITCH CO-i SNAP-TITE C0 j b LL'0BRICANTi-HOUGHTON: H-620 DOW 550 OR 200 1 PARKER.SOPER0-LUBE = CONFIGURATION TEST: WYLE p GENERAL ELECTRIC p APPLICABILITY: PART-21 i L APPENDIX "B" VEND 0RS' SPECIFICATIONS' INDUSTRY STANDARDS

ADDITIONAL' DETAILS:

TYPE 0F SEALS: "0" RING VS "U" CUP ELASTOMER SEAL / SEAT MATERIAL VITON VS OTHER w I l x c +

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a 2 fTEIn LDW4.M0w.C4488 IS--lTFA).M) $[ %:WEENCH.ELATS i-SPRIN& LM6 No 444M 15 17EA1 12) l, W '0" RIN& L.Dl3 NO. C4QL5 ITE01lll) i c l , f'. PLllN4ER__(.DlD4 No._ _C49BB IS ITER $. Il ) Y. -101EN0/D M7HIFDLD. ._e L- /[ ~ t Av.VnbEQ.FIC.E .50nblii55N5 Hnc ISt.% D INTO TH$.50dN0lb

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SUMMARY

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WEEK EJ1'3 02/M/90, i.

i .c "h* 5 ENCLOSURE:3 3,. PLANT SPECIFIC MTAc i HTE - $11E ' UNIT PONER SIGNAL' CAUSE : COMPLI- ' yid ' Y1D : yid g

CATIONS AB0VE DELON TOTAL

-3 : i 151'. 151; o 02/02/90 SDUTHTEIAS

2 100 A.

EQUIPMENT NO 1 0 r' k: h <f O i i PEACIDRSCRAM

SUMMARY

WEEK ENDIN6 01/28/90 i a L .l. PLANT SPECIFIC M TA .c MTE -l SITE ,UNiiPONERSIGNAL~CAUSE COMPLI ' YTD YTD YTD d 'CA110NS AB9VE DELON TOTAL. j 151. !!! t'i 01'/23/90 NORTH' ANNA 1.100 A : ' EQUIPMENT NO .1 0 1 'I ~ L ', ' ?01/24/90V067LE; ,1 90 A' EQUIPMENT' N0 1. 0 I r .01/26/90, DAVIS BESSE-- 1 ~-72A: EQUIPMENT NO. 1 0 1 j p 4' 01/27/90!!ON 'l'. 39A-PEHSONNEL YES' 1 0 1 .i H - 01/2B/90 PEACH BOTTOM: 3 50 M EQUIPMENT YES 1-0 1 .;g .y a-

SUMMARY

OF COMPLICAil0NS - ,f SliE UNIT COMPLICAtl0NS 1 I !!DN ' -.1 ROD POSli!DN INDICATION MALFLWCTION. 1 'PEACHBOTTOM - 3 RESETTING 0F PCIS FAILS TO SECURE STANDBY BAS FAN. DIFFICULTY IN ESTABLISHIN6 I CONDENSATE FLON TO THE REACTOR VESSEL'. ' ) ..n . i 1. f f a i {' l ^ ' - - - - - - - - - ^ ' ' ' ' ' - - ^ ^ " ' '

/ II. COMPARISON OF WEEKLY-STATISTICS WITH INDUSTRY AVERAGES. I SCRAMS FOR WEEK ENDING F O2/04/90 [j SCRAM CAUSE POWER ' NUMBER 1989 1988 1987 1986 1995 OF WEEKLY WEEKLY WEEKLY WEE LY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVER.oE AVERAGE YTD (3)(4) (8)(9) . * *: POWER'>15% EQUIP. RELATED >15% 1 3.0 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15%. O 1.0 1.0 1.3 1.8 2.O' OTHER(7) >15% 0 0.0 0.5 1.2 0;4 0.6

    • Subtotal **

1 4.0 4.6 6.4 6.5 8.0 ktLPOW(r,<15% ' EQUIP.!RELATED <15% 0 0.0 0.5 1.2 1.4 1.3 PERS. RELATED <15% 0 0.0 0.3 0.6 0.8 0.9 OTHER <15% 0 0.0 0.1 0.3 0.2 0.2

    • ' Subtotal **

O O.0 0.9 2.1 2.4 2.4

      • Total ***

1 4.0 5.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE = NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY BCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE VTD ..j MANUAL SCRAMS O 1.0 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS 1 3.0 4.5 7.0 7.9 9.4 5 t i '. - h?

11.. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERA2ES 6 SCRAMS FOR~ WEEK ENDING 01/28/90 r SCRAM.CAUSE' POWER NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMSf5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) (8)(9) ~** POWER >15%' EQU1P. RELATED >15% 4 3.5 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15% 1 1.2 1.0 1.3 1.8 2.0 -0THER(7) >15% 0 0.0 0.5 1.2 0.4 0.6

    • Subtotal'**

5 4.7 4.6 6.4 6.5 8.0 H**. POWER <15% EQUIP. RELATED <15% 0 0.0 0.5 1.2 1.4 1.3 PERS. RELATED <15% 0 0.0 0.3 0.6 0.8 0.9 JOTHER <13% 0 0.0 0.1 0.3 0.2 0.2

  • o Subtotal **

O O.0 0.9 2.1 2.4 2.4 .*** Total *** 5 4.7 5.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD . MANUAL SCRAMS-1 1.2 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS A 3.5 4.5 7.0 7.9 9.4 ..)

.o NOTES 1. PLANT SPECIFIC DATA BASED ON. INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH J MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE i ACTUATIONS WHICH RESULT IN ROD 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: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATID TO CAUSE OF SCRAM. h 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PRODLEMS. 4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTP,IBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. t OEAB SCRAM DATA Manual and Automatic Scrams for 1986 ----------------*- 461 Manual and Autoraatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 Manual and Automatic Scrams for 1990 (YTD 02/04/90) --- 21 e ,m_m m .}}

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