ML20216C685

Summary of 870609 Operating Reactors Events Meeting 87-018 W/Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870602 Meeting.List of Attendees Encl

ML20216C685
Person / Time
Site:	Turkey Point
Issue date:	06/12/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-87-018, OREM-87-18, NUDOCS 8706300331
Download: ML20216C685 (10)

Text

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JUN i 21987 q

MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment {

1 FROM: Wayne Lanning, Acting Chief 1 Events Assessment Branch Division of Operational Events Assessment {

3

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING JUNE 9, 1987 - MEETING 87-18 I

On Tuesday, June 9,1987, an Operating hactors Events meeting (87-1S) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events I which occurred since our last meeting on June 2,1987. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. During the past week, there were no significant events for input to NRC's performance indicator program.

Original Signed *oy Wayne D. Lanning Wayne Lanning, Acting Chief-Events Assessment Branch l Division of Operational Events Assessment j

Enclosures:

As stated ,

cc w/ Encl.:

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Charles E. Rossi JUN111187 cc: T. Murley D. Mcdonald J. Sniezek L. Rubenstein R. Starostecki J. Taylor E. Jordan E. Beckjord W. Russell, Reg. I J. Nelson Grace, Reg. II B. Davis, Peg. III R. D. Martin, Peg. IV J. B. Martin, Reg. V W. Kane, Reg. I -

L._Reyes, Reg. II C. f;orelius, Reg. III E. Johnson, Reg. IV D. Kirsch, Reg. V S. Varga D. Crutchfield B. Boger, G. Lainas G. Holahan F. Schroeder L. Shao J. Partlow B. Grimes F. Congel H. Miller E. Weiss S. Black T. Martin, EDO F. Miraglia E. Merschoff R. Hernan

r ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-18)

JUNE 9, 1987-NAME DIVISION NAME DIVISION J..Sniezek NRR R. Starostecki. NRR-

0. Gormley NRR W. Haass DISP-

'P. Clayton' DEDR0 'M. Miller NRR-V..Benaroya AE00 :F. Schroeder NRR

- J. Partlow NRR L. Shao NRR L. Marsh NRR R. Baer- RES J. Thompson NRR B. Boger; NRR E. Baker NRR A. Thadani NRR C. Berlinger. NRR S. Varga NRR W. Lanning' NRR i.

ENCIOSURE 3 0PERATING REACTORS EVENTS MEETING 87-18 JUNE 9, 1987 TURKEY POINT 3 BORIC ACID SYSTEM COMMON MODE FAILtJRE STATUS OF NRC/ INDUSTRY CHECK VALVE INITIATIVES S

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TURKEY POINT 3 8 4 LOSS OF BORIC ACID FLOWPATH TO UNITS 3 8 4

.PROBLE.M. LOSS OF BORIC ACID FLOWPATH TO UNITS 3 AND 4 CAUSE FAILED WATER SEAL IN. BORIC: ACID PUMP 4B SIGNIFICANCE

- COMMON MODE FAILURE CAUSED LOSS OF ABILITY TO EMERGENCY-BORATE TO MAINTAIN SHUTDOWN MARGIN.

DISCUSSION-THE SEAL WATER TANK SUPPLYING COOLING-T0 THE BORIC-ACID PUMP- 1 SEALS HAS N g OVERPRESSURE AT 40 PSI.-

FAILED BORIC ACID PUMP #4B WATER SEAL. '

4 No LEAKED INTO ENTIRE BORIC ACID SYSTEM FOR BOTH UNITS.

UOl'T3RWSTFLOWPATHUNAVAILABLEDUE'TOLOWLEVELFROM ..

REFUELING OUTAGE.

1 FOLLOWUP  !

LICENSEE HAS ISOLATED PUMP.4B AND PLANS TO REPLACE WATER SEAL.

INCORPORATE A DAILY SIGHT-GLASS CHECK'.ON THE SEALL i

WATER TANK, REVIEW OPERATING PROCEDURES.AND DETERMINELIF"A PREVENTIVE  :

MAINTENANCE PROGRAM IS REQUIRED,- "

INSTALL A 40 PSI FULL LENGTH SIGHT LEVEL GLASS ~0N THE: , ,

SEAL WATER TANK, REGIONAL INSPECTORS ARE FOLLOWING THE EVENT,AND THE LICENSEE'S' j CORRECTIVE ACTIONS. i l

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w STATUS OF NRC/ INDUSTRY CHECK VALVES INITIATIVES l

.i PROBLEM . .

CHECK VALVE MALFUNCTIONS HAVE CAUSED PLANT-AVAILABILITY OR CONTRIBUTED: ,

TO PLANT TRANSIENT SEVERITY.

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VALVE TESTS'DO NOT INDICATE DISC-INTEGRITY NOR IS' PREVENTIVE MAINTENANCE PERFORMED 0N.'A MAJORITY OF THE VALVES, SAFETY SIGNIFICANCE i

• 2 LOSS 0F REDUNDANCY LOSS.-0F-FUNCTION.DUE'TO SHORT CIRCUlTING FLOW' .

j DISCUSSION SAN ON0FRE LOSS OF POWER AND WATERHAMMER EVENT,fNOVEMBER:21, 1985, INPO SOER 86-3 "CilECK VALVE FAILURES OR. DEGRADATION" ISSUED 0CTOBER 15, 1986.

SURRY FEEDWATER LINE RUPTURE,' DECEMBER 9, 198G.-

EDO COMMITMENT TO COMMISSION T0' PERFORM SEVERAL INSPECTIONS OF.

LICENSEES CHECK VALVE PROGRAMS, MARCH 30', 1987; VIB INSPECTION OF MILLSTONE llNIT:1, APRIL ~20 - 2I4,1987.

VIB INSPECTION OF TROJAN, MAY 22, 1987, REVIEW'0F'FARLEY'S RESPONSE T0 INP0s SOER -

FOLLOWUP INFORMATION: PAPER TO COMMISSION DUE JUNE.15,21987' OWNER'S' GROUPS.T0 ISSUE DESIGN GUIDANCE AUGUST 1987-VIB TO PERFORM ADDITIONALLINSPECTIONS .T0' ESTABLISH INDUSTRY:

RESPONSE lTOLSOER AND DESIGN GUIDANCE'

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REV. 1 REACTOR SCRAM

SUMMARY

WEEK ENDINS 06/07/87

!. PLANT SPECIFIC DATA LATE SITE UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD CATIONS APOVE PELOW T0TAL 151 15%

06/01/87 BEAVER VALLEY  ! 95 A UNXNOWN k ', 3 0 3 06/01/B7 COOK 2 90 A PERSONNEL ND 1 1 2 06/02/57 SALEM 1 100 A EQUIPMENT / ELECT N0 1 0 1 Oe/02/S7 C00K 2 4A PERSONNEL. ND 1 2 3 06/03/67 VDSTLE 1 100 A , EQUIP / ELECT. NO B 6 14 06/04/B7 EDPINSON 2 0A EQUIPMENT / ELECT NO O 2 2 06/04/B7 CODL 1 90 A EQUIPMENT NO  ! 0 1 06/05/B7C00E 1 0A EQUIP / MECH ND 1 1 2 06/06/B7 VOSTLE 1 0A PERSDNNEL NO E 7 15 06/07/67 VE3TLE 1 18 A UNKNOWN NO 9 7 16 06/07/37 VDSTLE 1 4A EQUIP / MECH. ND 9 B 17 e ,,

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i II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGEE SCRAMS FOR WEEK ENDING 06/07/B7 ECRAM CAUSE POWER NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE .

YTD (3) (4) (S) (9)

• • POWER >15%

EQUIP. RELATED >15% 3 3.9 4.3 5.4 PERS. RELATED(6) >15%

• 1 1.5 1.S 2.O OTHER(7) '> 15 % 2 1.2- O.4 0.6

• • Subtotal **

6 6.5 6.5 E.O j

• • POWER <15%

EQUIP. RELATED <15% 3 1.2 1.4 .1. 3 ]j PERS. RELATED <15% 2 O.8 O.S 0.9 j OTHER <15% 0 0. 3 0.2 0.2  !

• • Subtotal ** 'l 5 2.3 2.4- 2. 4 l

• • • Total ***

11 B.8 8.9- 10.4 i l

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TYPE NUMBER 1987 1986 1cES OF WEEKLY WEEKLY 'WCEKLY SCRAMS AVEPAGE. AVERAGE AVERei3E YTD i i

1 MANUAL SCRAMS. O 1.5 1.0 1.0 'l AUTOMATIC SCRAMS 1.1 7.2 7.9 9.4 I 6

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL PEVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS PIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFIllED AS REACT 0P. PROTECTIVE ACTUATIONS WHICH RESULT IN R0D POTION, AND EXCLUDE PLANNED TESTS OR SCRAPS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLAtlT PROCEDURE.

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2. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL EP.R0RS UNRELATED TO CAUSE OF SCRAM.

3. 1986 INFORPATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

4 IN 1986. THERE WERE-AN ESTIMATED TOTAL OF 461 AUTOMATIC AND mat!UAL UNPLANNED REACTOR TRIPS AT 104 PEACTORS (HOLDING' OPERATINGLICENSES). THIS YIELDS'AN AVERAGE RATE OF 4.4 TPIPS-PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK.

FOR ALL REACTORS.

5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

6. PERSONNEL PELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR. LEVEL CONTROL PROBLEMS.

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE. .,

8. 1985 INFORMATION DERIVED FROM AN'ORAS STUDY OF UNPLANNED REACTOR' TRIPS' IN 1985. WEEKLY DATA DETERMINED BY TAKillG TOTAL TRIPS ~IN A GIVEN  :;

CATEGORY AND DIVIDING BY 52 WEEKS / YEAR. f l

9. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC' AND MANUAL '

UNPLANNED REACTOR TRIPS AT~93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATF OF. 5.8 TRIPS PER REACTOR q YEAR'AND AN AVERAGE RATE OF 10.4 TRIPS PER VEEK'FOR ALL REACTORS. . ,

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