NUREG-1192, Summary of Operating Reactor Events Meeting 87-37 on 871027. Viewgraphs & Summary of Reactor Scrams Encl

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Summary of Operating Reactor Events Meeting 87-37 on 871027. Viewgraphs & Summary of Reactor Scrams Encl
ML20236J279
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 10/28/1987
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
REF-GTECI-102, REF-GTECI-NI, RTR-NUREG-1192, TASK-102, TASK-OR IEIN-82-30, OREM-87-037, OREM-87-37, NUDOCS 8711050243
Download: ML20236J279 (20)


Text

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NUCLEAR REGULATORY COMMISSION wasmNotos,o e som g s. j L

OCT88 W i

' FEMORAf!DUM FOR: Charles E. Ross.1,' Director-Director of Operational Events Assessment i

FROM:

Wayne Lanning, Chief Events Assessment Branch Division of Operational Events' Assessment'

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING OCTOBER 27, 1987 - HEETING 87-37 On October 27; 1987 an . Operating Reactors Events meeting (87-35) was held to brief senior managers from NRR, RES,' AE00 and Regional Offices on even_ts which~

occurred since our last meeting on October. 20, 1987.

included as Enc.losure 1. The list of attendees is The events discussed in Enclosure and the significant elements 'of these events are presented

2. The Enclosure 3. provides a summary of reactor scrams and a comparison of this week 's statistics with industry. averages. One significant-event was identified for input to NRC's performance indicator program.

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anning, Ch e Events Assessment Branch Division of Operational tvents Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page 1

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MEMORANDUP FOR: . Charles E. Rossi,. Director.

Director of-Operational Events Assessment FRCit: ' Wayne Lanning, Chief 1

Events Assessment-Branch j tivision of Operational Events Assessment .  ;(

SUBJECT:

THE OPERAT NG REACTORS E\TNTS MEETING i OCTOBER 27, 1987 - MEETING 87-37 On October T7, 1987 an Operating Reactors Events meeting (87-35) was held to. i brief senior managers from NRR, RES, AE00 and Regional Offices on events which-occurred since our last neeting.on October 20, 1907. The' list cf attendees is. )

included as Enclosure 1. -

l The. events discussed and the significant elements of these events 4re presented in Enclosure ~2. The Enclosure.3 provides a summary of' reactor scrams and.a comparison of this week's . statistics with industry averages.. ' One significant event was identified for input to NRC's performance indicator program.

1 Wayne Lanning, Chief I Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated

.. cc w/Er,c1.:

See Next Page

.j DISTRIBUTION Central File NRC PDR EAD Reading File EAB Staff )

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AffE :MLReardon :WL ng  :  :  :  :  :

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0FFICIAL RECORD COPY

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T. Murley E. Adensam J. Srierek E. Reeves F. Miraglia G. Requa R. Starostecki D. Persinkc .

i E. Jcrdan J. Taylor.

E.-Beckjord W. Russell, RI J. Nelson Grace, RI!

8. Davis, RI!I

~

R. D. Martin, RIV J. 8. Martin, RV W. Kane, RI L. Reyes, RII C. Nore'lius, RIII J. Callan, RIV D. Kirsch, RV S. Varga D. Crutchfield B. Bcger .

G. Lainas G. Holahan L. Shao J. Partlow' B. Grimes F. Congel i

E. Weiss I S. Black T. Martin l

. J. Stone '1 R. Hernan l

H. Bailey J. Guttmann l

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) i ENCLOSilRE I 1

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LIST OF ATTENDEES t

OPERATihG REACTORS EVENTS BRIEFING (87-36)

October 20, 1987-HA!1E ORGAN 1?ATI0h

-]

NAME ORGAN!ZATI,0,N l

s1. Snierek NRR/DONRR 'I F. Miraglia .NRR/ADP l

i C.E.-Rossi NRR/DDEA R. Lobel NRR/DOEA P. Baranowsky,- NRR/00EA '

J. Partlow NRR/DRIS l 1

G. Cwalina NRR/LPEB l

A.'J. Mendiola NRR/LOLB l

D. Persinke NRR/LPEB-G. KLingler '

NRR/PMAS. .

W. Troskoski OE00 E. Weiss .AEOD/IRR E. Reeves- NRR/PDP-1 H.L. Reardon NRR/00EA i

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y TUESDAYLOCT0AER 27',-1987,~11 d 4

4 l-l THE AGE 6'PA INFORMATI0ff MAY- ALSO PE CBTAINEDfBY DI ALIN 4

FARLEY'2 LOOSE;PART IN PEACTOR VESSEL I

1 GENERI.C..JSSUES.

o WP0NG UNIT /WPCh'G TRAIN / WRONG COMPONENT EVENTS GENERIC ISSUE 102/(NUREG-1192) e f 4 o

INDUSTRIAL FATALITIES AT OPERATit!G NUCLEAR POWER-PLANTS

.o FITNESS FOR DUTY

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FAPLEY ? - LODSE,PART lN RE/CTOP VEEF. ELL PROBLEM THEPMAL SLEEVE FOUND IN PEACTOR VESSEL DUR!NG REFliELING .0UTAGE..

CAUSE- ,

WELD FAILURE, SIGNIFJ.CAEf o

POTENTIAL DAMAGE T0 INTEPNALS $ 0W Tile LOWEP COPE PLATE, 0

POTENTl/L PARTlAL FLOW 0PSTPUCTION THROUGH LOWEP COPE FLATE ..

DISCUSSJ.0D

  • o 10/19/87 UNIT IN REFUELING OUTAGE, FUEL PEMOVED.

o VISUAL INSPECTI0tl DISCOVERED FOREIGN DEJECT PESTING ON CORE SUPPORT FORGING, o '

PAPT IDENTIFIED AS SAFETY lNJECTION SYSTEM LOOP "B" THERMAL SLEEVE, o

LICENSEE REMOVED LOWER CORE INTERNALS ON 10/21/87 - At.'D RETRIE THERMAL SLEEVE, o

o SIZE OF THERMAL SLEEVE (12" XL6*) KEPT IT BEL' OV LOWER CORE PLA

.. NO DAMAGE TO INTERNALS, TilERMAL SLEEVE DENTED BUT INTACT,

, o LOOSE PARTS MONITOR ALARMED IN SEPTEMP.EP 1986' o SIMILAR OCCURRENCE IN MAPCP 1983 AT FARLEY 1, o

SAFETY ANALYSIS DID NOT. IDENTIFY SAFETY PROBLEM. ANALYSIS WAS- '

NOT REVIEWED BY NRC, o

SUBSECUENT INSPECTION AT BOTH UNITS-lN 198? SHCWED BROKE THIS THERMAL SLEEVE, o

DCT0PER 1983 SER REQUIRED INSPECTION EVERY CYCLE AT 'WES PLANTS WITH THERMAL SLEEVES INCLllDING FARLEY, o ,

LOSS OF THERMAL SLEEVES COVEREP PY IE NOTICEL82-30 IS'SliED 07/?6/02, o

LICENSEE PROCEEDING WITH REFUEllNG,. CRITICAL PATH NOT AFFECTED, FOLLOWUP-o LICENSEE REVIEWit'G LOOSE PARTS MONITORING SYSTEM RECORDS, c  :

REGION !! IS! SPECIALIST REVIEWED-RAD 10GRAPHIES.  !

o EAB IS STILL FOLLOWING UP EVENT, 1

CONTACT: D. OUDINOT -

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i WPONG UNIT / WRONG TRAjti/WPDNG C0t'FONENT EVFNTS EENERIC ISSUC 102/(NUPFG-11W)

PROBLEM f

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PFPSONt!El ACTIONS PERFCFFED ON WP0tlG UNIT OF % Pt'Lii-UNIT SilE OR  !

ON WPONC TFAIN'OR WRONG COMPONFPT OF SINGLE OR. MULTI-UNIT SITES', -

CAUSE 1<

LAPELING (5 0 32%) M'IADSET. 07,5, ~ J IT;)

1 TRAINING / INEXPERIENCE LAYCL'T/EOUIPMENT DESIGN (435, 14%) J (17!!, 11%)

PROCEDURES (37%, 14T) I RUSHED (1]?;, CQ -

Ph/SICAL. STRESS (265, 37) ]

DPAWINGS (67;, 37)

COPML't!ICATIONS (17%, 9T) It,'TEPPUPTION OF' WORK (6%, 3T) l l l SIGN I F.l cat;CF '

0 ' l LOSS OF SAFETY SYSTEM FUNCT10t' '

i o PERSONNEL HAZAPD  !

1 o Ut;NECESSARY DEMANDS ON PLAFT SYSTEMS" '

. r, l DISCUSSION .

o METHODOLOGY: FOLLOW-UP TO AEOD STUDY; INTEPVIEWS,'0BSERVAT!0NS ON 35 EVENTS AT 20 SITES; NOT ALL #ERE REPORTABLE; PRIMARY, SECONDAPY CONTRIBUTORS: NRR AND AE0D, e

LABELING, TRAINING, PROCEDURES PRIMAPY CONTPIEUTOR IN 60% OF EVENTS, c '

OPERATIONS PERSONNEL CAUSED MOST EVENTS (752),

c INTERACTION OF CONTRIBUTORS: MOST EVENTS COMF! NATION OF CONTRIBUTORS; ANY CONTRIBUTOR df}N CAUSE EVENT PY ITSELF, o DISCIPLINARY ACTION /PODIFY TRAINING, CONTACT: D. PERSINMD

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0 'NO C0f'PAPAPLE EFFORT IN LAEFLING

.1 FOLLOWh?

o D!SCUSSED Wi!/WT EVENTS,AND LABEL!iiG PITF -INPD; 9

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l c INPO PROGRAM FOR INVESTIGATING fiUPAN ERROR.

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CRYSTAL RIVER. 1/CE 2 DR0WNING IN INTAKE STRUCTURE

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SUPPY 12/86 la MAIN FEEDLINE j RUPTURE SURRY 10/83 1 FEEDLINE PUPTURE SUPPY 10/84 2 ELECTRICIAN DPILLING ,

INTO POWER LINE SUPPY 3972 2

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BY T00Lc i GINNA 2/79 1 ELECTROCUTED BY HAND TOOL PEACH BOTTOM 5/76 1. FALL '

CRYSTAL PlVER 4/79 1 FALL ,

DAVIS BESSE 1 11/84 ) FALL l

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i FITNESS F0P DllTY c

COMMISSTPF HAS' DEFERRED RULEMAVINC ON FFD IN RECOGNITION-0F INDUSTRY INITIAL!VE q

o POLICY STATFMENT ISSUED AUGUST 1986. CALLS FOR'18 MONTU EVALUATION PEP!0D (UNTIL FEBRUARY 19P8) o LICENSFFS FSTABLISH PROGRAM IAW OlllDELINES PUBLISHED BY EDISDN ELECTRIC INSTITUTE:

- POLICY - EAP - TESTING

- TRAINING - UNIONS - PENIAL OF ACCESS-

- PROCEDURES - CONTRACTORS c

MINIMUM TESTING IS " PRE EMPLOYMENT" AND "FOR CAUSE." SOME USE RANDOM / PERIODIC-c NRL HAS CONPUCTED FIGHT INSPECTIONS, ACCOMPANIED INPO, GATPErED INFO ON FFP CASES VIA RESIDENTS AND LICENSEES l

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INPO EVALUATIONS PAVE BEEN " PROGRAMMATIC," NOT PROBLEM /

PERFORMANCE ORIENTED .j o

MANY CASES OF DRUG INVOLVEMENT (INftllDE A FEW OPERATOFS) s c

OUR GENEPAL IMPRESSION IS THAT LICENSEES HAVE DONE A GPO JOB BUT RULEMAKINGMAYBE' APPROPRIATE (;gfLONG-TERM (COMMISSIO MEETING DECEMP,ER J) " ,

CONTACT: J. PARTLOW '

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MANUAL VS AUTO SCRAMS-TFE NUMPER 1987 1986 19:95 OC WEEl'LY WED LY WEE 5 .Y '

SCRAM 5 AVERAGE AVEFAGE AVEFAGE YTD MANUAL SCRAM 5 0 1,4 1,o 1,9 A'JT OMr,T. ! c ECF AME 4 7,5 y,9 e,4 l

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. 1 '

NOTES 9

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS l FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THRODGH ',

MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE i ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED j TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE  :

WITH A PLANT PROCEDURE, l

i E. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS j UNRELATED TO CAUSE OF SCRNI. 1

3. 1986 INFORMATION DEPIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETER) TINED 3Y TAK!tlG TOTAL TRIPS q IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR. j 1
4. IN 1986 THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND J RANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.0 TRIPS PER WEEK FOR All REACTORS.
5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.
6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

(

7. "0THER" INCLUDES AUT0tmTIC 50R AMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGiTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
8. 1985 INFORMATION DERIVED FROH AN ORAS STUDY OF UNPLANNED REACTOR TRIPS
  • IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEli CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
9. IN 1985, THERE VERE AN ESTItRTED TOTAL OF S41 AUTOMATIC AND MANUAL j

' UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER )

LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR  ;

YEAR AND AN AVERAGE RATE OF 10.8 TRIPS PER WEEK FOR ALL REACTORS. I s

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