ML20148Q080

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Summary of Operating Reactors Events Meeting 88-03 on 880119.List of Events & Summaries of Presented Events & 1988 Scrams Encl
ML20148Q080
Person / Time
Site: Indian Point, Sequoyah, 05000000
Issue date: 01/21/1988
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-88-003, OREM-88-3, NUDOCS 8801290319
Download: ML20148Q080 (18)
v • d • e


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y. UNITED STATES j NUCLEAR REGULATORY COMMISSION

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. MEMORANDUM FOR: Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning. Chief i Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING

January 19, 1988 - MEETING 88-03 On January 19, 1988 an Operating Reactors Events meeting (88-03) was held to brief senior managers from NRR. RES. AE00 and Regional Offices on events which occurred since our last meeting on January 12, 1988. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 presents a tabulation of long-term followup assignments to be completed. a summary of reactor scrams, and a comparison of this week's statistics with industry averages. One significant event was iden-tified for input to NRC's performance indicator program. Enclosure 4 provides a 50.72 report tabulation and summary for January 1 through January 10. 1988.

ing. Chief Events Assessment Braq)

Division of OperationaT Events Assessment Office of Nuclear Reactor Regulation i

Enclosures:

. As stated cc w/ Encl.:

} See Next Page '

o- ,e f'; i f' V f'/yl#;p,g,f 8801290319 880121 NRRB 62f f

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T. Murley J. Sniezek l F. Miraglia N. Slosson E. Jordan R. Capra J J. Taylor E. Sylvester E. Beckjord E. Adensam

, W. Russell. RI 8.~0 avis RIII J. Nelson Grace. RII R. D. Martin RIV ,

J. 8. Martin, RV

! W. Kane. RI -

L L. Reyes. RII i C. Norelius, RIII J. Callan. RIV ,

1 D. Kirsch. RV i

S. Varga l O. Crutchfield j
8. Boger '
G. Lainas i G. Holahan  !

. L. Shao l

, J. Partlow

8. Grimes F. Congel ,

E. Weiss

. S. Black l 6 T. Martin J. Stone ,

R. Hernan j H. Bailey a J. Guttmann i A. Thadani S. Rubin

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-03) j.

January 19. 1988 1

'! NAME ORGANIZATION NAME ORGANIZATION

< W. Lanning NRR/00EA J. Sniezek NRR

- M.L. Reardon fiRR/00EA W. Minners RES/0RPS

0. Neighbors NRR/POR I-1 V. Benaroya AE00/OSP R. Scholl, Jr. NRR/00EA R. Lobel flRR/00EA j 8. Boger NRR/ADRI R.A. Capra NRR/PD I-1

, , E. Weiss AE00/00A E.G. Adensam NRR/PD 2-1 R. Dudley NRR/0RSP L. Engle OEDO E. Rossi NRR/00EA G. Lainas NRR/ADR II J. Roe NRR/DLPQ I

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ENCLOSURE 2 OPERATIt[G REACTORS EVENTS BRJEFING 88-03

.: TUESDAY, JANUARY 19, 1988 I

THIS INFORMATION MAY ALSO BE OBTAlfSD BY DIALING EXTENSION 27174.

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. .j l INDIAN POIf1T 2 STEAM GENERATOR BOILED DRY (AIT UPDATE) j BRUNSWICK 2 RECIRCULATION PIPE INDICATION 4

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BRUNSWICK UNIT 2 RECIRCULATION PIPE INDICATION JANUARY 11, 1988 PROBLEM ISI ULTRASONIC TESTit!G DETECTED 4.8 INCH LONG 85T THRU WALL CRACK IN SAFE END N0ZZLE WELD (WELD 2-B32-RR-12-ARES)(12 INCH DIAMETER, 0,875 INCH).

"1 1 CAUSE THE CAUSE IS UNKNOWN, BUT IT APPEARS TO HAVE STARTED AS INTERGRANULAR STRESS CORROSION CRACKING THE INCONEL. WELD CLADDING.

SIGNIFICANCE

. o THIS CRACK IS DIFFERENT FROM THE PREVIOUSLY REJECTED INDICATIONS

IN THAT IT HAS APPARENTLY PASSED THRU SOME OF THE LOW ALLOY STEEL I.E, NOT LIMITED TO WELD REGION, (A SIMILAR EVENT TOOK PLACE IN TAIWAN.)

DISCUSSION o NEW INSPECTION TECHNICUE (SAME AS BEING REQUIRED FOR ALL BWR IN I l-GENERIC LETTER NOW BEING PREPARED) WAS USED, l o REVIEW 0F 1986 AND 1984 DATA SHOWS THAT THIS IS NOT A NEW INDICATION, j o BECAUSE OF OLDER TEST TECHNIQUES, PREVIOUS TESTS DID NOT SHOW THE

-! COMPLETE CRACK. THEREFORE, IT WAS PREVIOUSLY CLASSIFIED AS A SUB-SURFACE INDICATION, 1 FOLLOWUP j 7 o BRUNSWICK UNIT 1 ISI DATA IS GOING TO BE REVIEWED FOR SIMILAR

PROBLEMS, o BRUNSWICK UNIT 2 DATA IS BEING REVIEWED. SEVEN OF TEN RISER l WELDS HAVE BEEN INSPECTED WITH ONLY THIS ONE REJECTABLE INDICATION. THE OTHER THREE RISERS, BOTH CORE SPRAY N0ZZLES

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] AND BOTH JET PUMP INSTRUMENT N0ZZLES WILL BE INSPECTED. BOTH l 28" SUCTION N0ZZLES HAVE BEEN INSPECTED WITHOUT REJECTABLE

-' INDICATIONS, h CONTACT: R SCHOLL t.._._........_...........

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RECIRCULATICLPIPE INCICATION (CONTINUED) o THE REPAIR HISTORY OF THE CRACKED WELD WILL BE REVIEWED AS WELL AS PAST RADIOGRAPHY FILMS,

, o C,Y, CHENG, CHIEF, MATERIALS ENGINEERING BRANCH IS RESPONSIBLE FOR LONG TERM PROGRAM DEVr'_0PMENT AND FOLLOWUP OF THIS EVENT.

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't CONTACT: R. SCHOLL (01/15/88) .

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ENCLOSURE 3 LONGTEPM FOLLC'WUP ASSIGNMEfiq TO BE COMPLETED ORGANIZATION LONGTERM FOLLOWUPS OUTSTANDIt!G 01/05/88 01/12/88 01/19/88 SPLB 6 6 6 EMTB 1 1 1 OGCB 5 5 5 RVIB 4 4 4 SRXB 2 2 2 I PD2-3 1 1 1 OSP 2 2 2 ESGB 2 2 2 AE00 2 2 2 SIC 8 3 3 3 4 SEL8 6 6 6 I P02-2 2 1 1 PDS 3 1 1 SIC 8 3 3 3 i

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!. PLANT SFECIFIC CATA l

! ATE SITE 'JNIT PCiEP. SIGNAL CAU3E CCP.?LI- YTD YTL YTD ,

l CATIONS AEC'!E !! LOW TOTAL 151 15; l

01/12/E3 .905'.'!EE 2 100 M EC'J!? MENT NO 1 0 1 01/1;/93 NORTH ANNA 1 15 A ECJIPMENT YES 1 1 2 01/13/E3 C0CK 1 90 A PERECNNEL ND 1 0 1 01/13/E3 TURKEY POINT  : 0M EQ'JIPMENT N3 0 1 1 ,

l 01/16/E3 CATAWiA 1 0A EQUIPMENT N3 0 1 1 N0 0 1 l 01/17/83 VC5TLE 1 100 A ECUIPMENT 1 l

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OF COMPLICAi!0NS SITE UNIT CCMPLICATIC.15 l l

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1. PLANT SPECIFIC DATA BASED CN INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF :f!TEREST. PERIOD IS MIONIGHT SUtDAY THROUGH MIDNIGHT: SUNCaY SCRAF.S ARE DEFINED AS REACTOR PROTECTIVE <

ACTUATIONS WHICH RESULT IN R00 MOTION. AND EXCLUDE PLANNEC l TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCCRDANCE WITH A PLANT PROCECUPE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.  :

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2. COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM. l l
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.

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FLA:i! NA?.E EtlENT EVENT IESCRIPTICN QTR SIENIFICXCE I

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9RUNSWICX 2 01/02/53 FRI?ARY CCNTAIN?.ENT !!CLATIGN VALVES IN TW3 LRAIN 1 POTENTIAL FCR CR ACTUAL CEERADATION TRANSFER LINES FAILD TO CLCEE OF CCNTAIN?.ENT CR SAFETY-RELATED STRUCTURES l

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33 3rtu 3n333 3 33 3 3 3nnu==un--------Sn. ,

, CCCKET EVDT EVDT FACILITY N'JMBER EMBER DATE 21333333333333333333333333333333333333333333 316 ROCK POINT 1 155 11123 01/05/88 BRCHS FEMY 1 259 11164 01/07/SS 1

, CAT 4u!A 1 413 11190 01/10/88 i

CCCK 1 315 11134 01/06/88 01A91.0 CANYC4 1 275 11170 01/09/88 KARRIS 1 400 11159 01/07/88 MAARIS1 400 11173 01/09/88 MILLSTCkE 2 3!6 11126 01/05/E8 PEACH 10TTCM 2 277 11162 01/07/88 ,

t FEACH BOTTOM 2 277 11174 01/09/88 i CEWCYAH 1 327 11122 01/05/88 1 SE000YAH 1 327 11125 01/05/88 .

~i V06TLE 1 424 11138 01/06/88 .

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! Plant c;trations D Design / Mfg /Censtr Icatequacy CM Systessi e;ui;sent, and/:r struttures (cund 2 Radiel:;::al ::trels CR Flant Oeiiniti:n act to be designed, Requiresentsinadequacy manafactured, a ::: :ati:9al rad safety CE Cesi;n Errer :r inade;uacy c nstru:ted, er installed t rad eas:e sana;eatat CM ?f; Err:t :r inadequacy in att:rda9:e etta e rad eff!.ent ::ntrol n' OC C:nstr Ert:r cr inadequacy a;;reved plant dest;n senit: ring DI Other s;ecifications.

d rat tat'l trans;:rtatien e eater thetistry centrols E Atneraal Envirensental Stress EA  !!F actuation - aut:satic El ESF actuatici - ,

3 Maintenance EE EM Interfereece inadvertent er spuri:us I EM 420 (spray, il::d, etc.) EM E!F attuatten - sanual )

4 Suritillan:e EF Fire EF EEF failute ET Teep (en:tsal high cr ED  !!F de;radati:n 5 Fire Fr:te:ti:n 1: 1 El External event (e.g.

ER Radicattive Radiation fire, earth:uake) i f 6 E.ser;encyrre;aredness EC Cheaical Reacticas  !

EV Vibratien L: ads FR Fell:e up re;crt

7 Settrity E! Insatt Leads

] EH Hunan-caused External lhF0 Infernation report only 9 Outates Event EN ac ts of Nature LCO, Entry into an LCD sith  :

9 halttyFr:;rans actica statetent of I I Internal h:urs/ days. (e.g. (C Mh i 10 Licensing Activities represents entry into an l IC Interaal to C:P: nent LCD eith a 2 h:ur acti:n 1 11 Trainteg IE en tient Env Stress statenenti LC07d a:uld be )

f:r a 7 day a:ti:n la Engineering su:ccrt H %ean Actions, Plant Staf f statteent) 1 l

hP Failure to F:llce NON! No istediate effect On j Precedures plant M Misdia;ncsis (foll: sed at:rg P1 Feuer redutti:n -

.; ;r::thre) intenti:nal j "A accidental acti:n HI Other FS F:eer re httten -

+

aut:aatic truntack)

M "aintenance RA Radicattivity release :r .

4  ?! 3:tedFrevsaint c:ntantnati:n event l

(including surv tests '

j and calib) SA Scrae - aut:tatic j  ?! Fer:e! Faint (ft: alt iAE 5: rat - aut:satic e/E!F ,

.j af a kn:wn fail f el 4:tuati:n I terae - sanual s/!!F

.i 7 Fr::thras lr.a:ena:y 4:tuati:n

taebi;u
:.s, i:c:::lete, SM Scras - easual 1 'tr:r':as) SS Scrai itinal - no red l q n:vetett/r:ds already

.3 F0 tefectiveC;er inserted 4

Pretekre FM Oefective "u nt IS Tech !;ec viclati:n Frt:thre PC CeJectiveCalit/ Test UE Unusual Event declared

] Pr:tedure a PI Otrer 11 Citerts:crtable

) CCCurrence

]. Q l'a h en i -. .c . . . , . .,.,;.-, .y -

....,z .. . , . . , , . . . . . . . . _ _ .

f% .

e e MEMORANDUM FOR: Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation f

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING January 19. 1988 - MEETING 88-03 On January 19, 1988 an Operating Reactors Events meeting (88 03) was held to brief senior managers from NRR. RES AE00 and Regional Offices on events which occurred since our last meeting on January 12. 1988. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 presents a tabulation of long-term followup assignments to be completed. a summary of reactor scrams, and a comparison of this week's statistics with industry averages. One significant event was iden-tified for input to NRC's performance indicator program. Enclosure 4 provides a 50.72 report tabulation and summary for January 1 through January 10, 1988.

Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ Encl.:

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