ML20045A470

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Summary of Operating Reactors Events Meeting 93-12 on 930331.List of Attendees,Significant Elements Discussed & Reactor Scram Statistics for Wk Ending 930328 Encl
ML20045A470
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 04/08/1993
From: Chaffee A
Office of Nuclear Reactor Regulation
To: Grimes B
Office of Nuclear Reactor Regulation
References
OREM-93-12, NUDOCS 9306100350
Download: ML20045A470 (12)


Text

APR 0 81993 7)

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MEMORANDUM FOR:

Brian K. Grimes, Director Division of Operating Reactor Support l

FROM:

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING MARCH 31, 1993 - BRIEFING 93-12 On March 31, 1993, we conducted an Operating Reactors Events Briefing (93-12) to inform senior managers from offices of the chairman, EDO, SECY, RES, AEOD, NRR, OE, and regional offices of selected events that occurred since our last briefing on March 24, 1993. lists the attendees.

presents the significant elements of the discussed event. contains reactor scram statistics for the week ending March 28, 1993.

No significant events were identified for input into the NRC performance indicator program.

- original signed by T. J Carter for -

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support-

Enclosures:

As stated DISTRIBUTION:

Central Files RDennig cc w/ attachments:

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OFFICIAL RECORD COPY DOCUMENT NAME:

ORTRANS.KAG (G:KAG) i 9306100350 930408 PDR ORG NRRB 7v } '

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T. Murley, NRR-(12G18)

R. Stransky (PDIII-3)

F. Miraglia, NRR (12G18)

J. Hannon (PDIII-3)

F. Gillespie, NRR (12G18)

J. Partlow, NRR (12G18)

S. Varga, NRR-(14E4)

J. Calvo, NRR (14A4)

G. Lainas, NRR (14H3)

J. Roe, NRR (13E4)

J. Zwolinski, NRR (13H24)

M. Virgilio, NRR-(13E4)

W. Russell, NRR (12G18)

J. Richardson, NRR (7D26)

A. Thadani, NRR (8E2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR (10H3)

F. Congel, NRR (10E2)

D. Crutchfield, NRR (11H21)

W. Travers, NRR (11B19)

D. Coe, ACRS (P-315)

E. Jordan, AEOD (MN-3701)

T.: Novak, AEOD (MN-9112)

L. Spessard, AEOD (MN-3701)

K. Brockman, AEOD (MN-3206)

S. Rubin,~AEOD (MN-5219)

M. Harper, AEOD (MN-9112)

J. Grant, EDO (17G21)

R. Newlin, GPA (2GS)

E. Beckjord,-RES-(NLS-007)

A.' Bates,.SECY (16G15)

G. Rammling, OCM (16G15)

T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Merschoff, Region II B. Davis, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV J.B. Martin, Region V K. Perkins, Region V bec:

Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway-Atlanta, GA 30339-5957

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-12)

MARCH 31, 1993 NAME OFFICE NAME OFFICE B. GRIMES NRR B. D. LIAW NRR A. CHAFFEE NRR J. HANNON NRR R. DENNIG NRR J.

ZIMMERMAN NRR K. GRAY NRR C. ORSINI NRR E. GOODWIN NRR G. MARCUS NRR C. BEARDSLEE NRR B. WETZEL NRR J. CARTER NRR J. TATUM NRR S. ROSENBERG NRR W. LEFAVE NRR J. SCHIFFGENS NRR M. LEACH OCM/IS W. SCOTT NRR W. MINNERS RES S. CONGEL NRR K. HART SECY D. BARSS NRR W. TROSKOSKI OE C. ROSSI NRR M. LESSER OEDO S. VARGA NRR V. BENAROYA.

AEOD TELEPHONE ATTENDANCE (AT ROLL CALL)

Recions Resident Insoectors Region I Region II Region III Region V IIT/AIT Team Leaders Misc.

Perry t

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ENCLOSURE'2 0

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OPERATING REACTORS EVENTS BRIEFING 93 L i

LOCATION:

10 Bil, WHITE FLINT WEDNESDAY, MARCH 31, 1993, 11:00 A.M.

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l PERRY, UNIT 1 SERVICE WATER PIPE. RUPTURE-j I

i PRESENTEDLBY:

EVENTS ASSESSMENT BRANCH DIVISION OF' OPERATING REACTOR SUPPORT,.NRR i

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93-12 PERRY, UNIT 1 SERVICE WATER PIPE RUPTURE 3

MARCH 26,.1993 1

4 ERDB1EM A RUPTURE OF A 30" FIBERGLASS SERVICE. WATER PIPE RESULTED IN LIMITED FLOODING IN ADJACENT BUILDINGS.

CAUSE NOT KNOWN AT THIS TIME.

SAFETY SIGNIFICANCE THIS IS THE SECOND FAILURE OF A LARGE FIBERGLASS. COOLING l

WATER PIPE WITHIN LESS THAN TWO YEARS THAT HAS RESULTED IN l

SOME FLOODING OF BUILDING AREAS.

WERE THE FIXES MADE TO l

PREVENT RECURRENT FAILURES AND FLOODING ADEQUATE?

j DISCUSSION l

o REACTOR WAS OPERATING AT 100% POWER.

AT 13:15-WATER WAS OBSERVED " WELLING" UP NEAR THE WATER l

TREATMENT BUILDING.

ESTIMATED TO BE ABOUT 100 GPM 7

.o TO IDENTIFY THE SOURCE OF THE WATER, LICENSEE BEGAN ISOLATING VARIOUS POTENTIAL SYSTEMS.

l CONTACT:

J. CARTER, NRR/0EAB' AIT:

YES

REFERENCES:

10 CFR 50.72 #25316 AND SIGEVENT:

TBD PN39319 i

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LPERRY, UNIT-1 93-12 l

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AT ABOUT 15:20, THE' GROUND IN THE. VICINITY' 0F THE

" WELLING" WAS OBSERVED TO ERUPT AND-A LOW PRESSURE ALARM FOR THE SERVICE WATER SYSTEM-WAS RECEIVED.

FOURTH SERVICE WATER PUMP STARTED o

POWER WAS REDUCED TO 66% AND THE REACTOR WAS SCRAMMED l

AT 15:26.

e ALERT DECLARED AT 15:35 EST.

o AT 15:38 SERVICE WATER SYSTEM WAS SHUT DOWN..

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BREAK IS IN 30" DIAMETER FIBERGLASS LINE LOCATED-ABOUT 15 FEET UNDERGROUND ADJACENT TO THE WATER TREATMENT-l BUILDING.

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LINE IS A SERVICE WATER SUPPLY LINE TO TURBINE BUILDING-FAILURE BLEW OUT DIRT AND PART OF PIPEL e

WATER WAS-SUBSEQUENTLY FOUND.IN. AUX. BUILDING, DIESEL i

ROOM, INTERMEDIATE BUILDING,'0FF GAS BUILDING, SERVICE l

BUILDING, RAD WASTE BUILDING, TURBINE BUILDING, AND CONTROL COMPLEX.

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NO REQUIRED SAFETY-REL.ATED EQUIPMENT OR ELECTRICAL POWER DISTRIBUTION WAS AFFECTED.

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'o-REACTOR COOLED DOWN BY-USING RCIC AND SRVs..

o LRHR-ALIGNEDLTOLSUPPRESSION POOL COOLING MODE-HEAT REMOVED BY UNAFFECTED EMERGENCY SERVICE WATER SYSTEM i

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PERRY,. UNIT:1 93-12 o

AN ESTIMATED 85,000-GALLONS ENTERED BUILDING AREAS:

j TECHNICAL SUPPORT CENTER NOT OCCUPIED DUE T0 WATER j

IN LOWER LEVELS OF SERVICE BUILDING

. EMERGENCY OPERATIONS FACILITY UTILIZED-o ALERT TERMINATED AT 01:05-ON 3/27/93; PLANT IN STABLE CONDITION.

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SIMILAR EVENTS o

A 36" FIBERGLASS CIRCULATION WATER PIPE RUPTURED 1

12/22/91..

IN 92-69 DISCUSSED EVENT.

i FOLLOWUP

o AUGMENTED INSPECTION TEAM (AIT) FORMED AND SENT TO

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' REGIONAL AND. HEADQUARTERS STAFFS AWAITING INFORMATION FROM AIT.

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'I PERRY. SERVICE WATER OVERVIEV SERVICE VATER PIPE BREAK 3/26/93-NDTES:

ROLL UP DDDRS (LARGE. DDDRS)=====--e 36 INCH VIDE PERSONNEL DDDRS 0:-

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e REACTOR SCRAM Reporting Period: 03/22/93 to 03/28/93 YTD YTD LA.II PLANT & UwIT ABOVE BELOW YTD g

g g3)23g ComptiCAflowl j}3.

313 12T&

03/23/93 HADDAM NECK 1 100 SM Equipment Falture NC 1

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03/23/93 MONTICELLO 1 16 SA ' Operating Error No 1

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_1 C3/24/93 MONTICELLO 1 5

SM Equipment Failure NO 1

1 2

03/26/93 PERRY 1 100 SM Equipment Falture NO 1

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03/26/93 LIMERICK 2 100 SA Equipment Falture NO 2

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C3/28/93 POINT BEACM 2 100 SA operating Error NO

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Cot 03 tear To Date (YTD) Totals include Events Within The Calender Year Indicated By The Erd Date of The sp eporting Period'

. Ets 10 Page:1 04/05/93

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COMPARISON OF WEEKLY SCRAM STATISTICS WITN INDUSTRY AVERAGES PERIOD ENDING 03/28/93 NUMBER 1993 1992 1991*

1990*

1989*

OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)

POWER GREATER THAN OR EQUAL 10 15%

EQUIPMENT FAILURE

  • 3 2.7 2.6 2.9 3.4 3.1 DESIGN / INSTALLATION ERROR
  • 0 0.2 OPERATING ERROR
  • 2 0.5 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
  • O 0.6 0.4 EXTERNAL
  • 0 0.2 0THER*

0 0.0 0.2 0.1 Subtotal 5

4.2 3.4 3.5 3.9 4.2 POWER LESS TRAN 1$%

l EQUIPMENT FAILURE

  • 1 0.3 0.4 0.3 0.4 0.3 DESIGN /lNSTALLATION ERROR
  • 0 0.0 -

OPERATING ERROR

  • 0 0.2 0.1 0.2 0.1 0.3 MAINTENANCE ERROR
  • 0 0.0 0.1 EXTERNAL
  • 0 0.0

.CTHER*

0 0.0 0.1 P

$4totat 1

0.5 0.7 0.5 0.5 0.6 TOTAL 6

4.7 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 No. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERACE (YTD)

YOTAL AUTOMATIC SCRAMS 3

3.3

' 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 3

1.4 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF

  • Detailed brfrekdown not in database for 1991 and earlier

- EXTERNAL cause included in EQUIPMENT FAILURE

- MAINTENANCE ERROR and DESIGN / INSTALLATION ERROR causes included in OPERATING ERROR DTHER cause included in EQUIPMENT FAILURE 1991 and 1990

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.ETS 14 Page: 1 04/05/93

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NOTES

!1 41 PLANT. SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR-THE F

WHICH RESULT IN ROD MOTION,;AND EXCLUDE ~ PLANNED TESTS-OR SCRAMS AS PART '

l

-PERIOD OF INTEREST.

SCRAMS'ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS l

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'-OF PLANNED SHUTDOWN IN.ACCORDANCE WITH A PLANT PROCEDURE..

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} 2. -

COMPLICATIONS: RECOVERY COMPLICATED'BY EQUIPMENT FAILURES OR' PERSONNEL'-

ERRORS UNRELATED TO CAUSE OF SCRAM.

13.

SA = Scram Automatic; SM = Scram Manual OEAB SCRAM DATA J

' Manual and Automatic Scrams for-1987 -----------------

435 Manual and Automatic Scrams for 1988 ------------------ 291

~ Manual and Automatic Scrams for. 1989 -------------------252

-Manual and Automatic Scrams for 1990 ------------------ 226 Manual ~and Automatic Scrams for 1991 ------------------ 206 Manual and-Automatic Scrams'for-1992 ------------------ 212

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-Manual and~ Automatic Scrams-for 1993 --(YTD 03/28/93)-- 58 I

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