ML20214J499

Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl

ML20214J499
Person / Time
Site:	Calvert Cliffs, Peach Bottom, Oconee, Catawba, Vogtle, Clinton, San Onofre, Fort Calhoun, 05000000
Issue date:	05/15/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
TASK-A-44, TASK-OR OREM-87-009, OREM-87-9, NUDOCS 8705280073
Download: ML20214J499 (17)

Text

r 14M 151981 MEMORANDUM FOR: Charles E. Rossi. Director Division of Operational Events Assessment FROM: Wayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

OPERATING REACTORS EVENTS MEETING ON MARCH 30, 1987 - MEETING 87-09 On March 30, 1987 an Operating Reactors Events meeting (87-09) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which cccurred since our last meeting on March 16, 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. Enclosure 3 provides a summary of those presented events that will be input to NRC's performance indicator program as significant events.

C r!s tal 31snod by Wayuo D. Lenung Wayne Lanning Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION

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, s g MEMORANDUM FOR: Charles E. Rossi Director.

Division of Operational Events Assessment

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FROM: N Wayne Lanning, Acting-Chief

\ Events Assessment Branch Division of Operational-Events Assessment

'\ .

SUBJECT:

SL'MMARY OF THE OPERATING REACTORS EVENTS MEETING ON MARCH 30, 1987 - MEETING 87-09 l

On March 30, 1987 an Operating Reactors Events meeting (87-09) was _ held to t brief' senior managers from NRR, RES, AEOD and Regional Offices on events'which occurred since our last meeting on March 16, 1987. The list of attendees is <

included as Enclosure 1. -

\ .

4 The events discussed and the significant elements of these events are presented '

in Enclosure 2. Enclosure 3 provides a summary of those presented events that-

will be input to NRC's performance indicator program as significant events.

s

\

Wayne Lanning, Acting Chief

, Events Assessment Branch

\ Division of Operational Events Assessment i

! Enclosures. s

{ As stated \

! i cc w/ Encl.:

See Next Page

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, DISTRIBUTION j Central File \

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MEM0kNDUMFOR:Charles E. Rossi, Director .

Division of Operational Events Assessment FROM: s Wayne Lanning, Acting Chief

\ Events Assessment Branch

\'

Division of Operational Events Assessment

SUBJECT:

\

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON MARCH 30, 1987 - MEETING 87-09 On March 30, 1987'an Operating Reactors Events meeting (87-09) was' held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 16, 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. Enclosure 3 provides a summary of those presented events that

! will be input to NRQ's performance indicator program as significant events, i

\~ Wayne Lanning, Acting Chief s

i i Events Assessment Branch Division of Operational Events Assessment

\

Enclosures:

\

As stated i

\

cc w/ Encl.:

See Next Page i cc w/ Encl.:

See Next Page DISTRIBUTION i <

Central File NRC PDR EAB Rdg Swenson Rdg w/o Enclosure EAB Members 1

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i Those Listed MAY 151987 cc: T. Murley P. Sears J. Sniezek V. Nerses J. Taylor S. McNeil

, 'E. Jordan R. Capra E. Beckford K. Jabbour W. Russell, Reg. I B. J. Youngblood

, J. Nelson Grace, Reg. II J. Stone ,

B. Davis,' Reg. III

, R. D. Martin, Reg. IV J. B. Martin, Reg. V W. Kane, Reg. I L. Reyes, Reg. II C. Norelius, Reg. III E. Johnson, Reg. IV D. Kirsch, Reg. V R. Starostecki F. Miraglia '

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 E. Merschoff J. Guttmann 4

k a b f

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. r ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFIf!G (87-09)

MARCH 30, 1987 NAME DIVISION NAME DIVISION G. Holahan NRR G. Klingler IE E. Murphy NRR W. Haass IE R. Wright NRR E. Weiss IE -

K. Eccleston NRR E. Brown AEOD W. Regan NRR K. Jabbour NRR P. Sears NRR J. Rosenthal IE C. Schulten NRR T. Novak NRR R. Capra EDO C. E. Rossi NRR B. Boger NRR A. Thadani NRR V. Benaroya NRR T. Gwynn - 0CM G. Murphy ORNL F. Schroeder NRR J. Gutts IE F. Miraglia NRR H. Bailey IE R. Scholl NRR S. McNeil NRR W. Swenson NRR J. Stone IE k

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ENCLnSIIRE 2 OPERATING REACTORS EVENTS BRIEFING 87-09 MARCH 30, 1987 FORT CALHOUN STATION BLACK 0UT CALVERT CLIFFS 2 LOSS OF SHUTDOWN COOLING AFD LOW PRESSURE SAFETY INJECTIOM CATAWBA 2 LOAD REJECTION TEST PERFORMED-AFTEP OCCURRENCE-0F A RCS UNIDENTIFIED LEAK REQUIRING SHUTpnWN 4

OTHER EVENTS OF INTEREST MULTIPLE. INDUSTRY CHECK VALVE INITIATIVES CLINTON MULTIPLE CONTROL R0D DRIFT CAUSED BY LOSS OF

INSTRUMENT AIR m

, t MARCH 30, 1987 FORT CALHOUN - STATION BLACK 0UT MARCH 21, 1987 (P, SEARS, NRR)

PROBLEM 161 KV SUPPLY WAS LOST WITH PLANT IN REFUELING OUTAGE 345 KV SUPPLY WAS UNAVAILABLE DUF TO MAINTENAPCE EDG 2 OUT FOR MAINTENANCE EDG 1 IN MANUAL MODE ,

CAUSE MAINTENANCE ACTIVITIES ON BOTH ONSITE AND OFFSITE AC ELECTRICAL SYSTEMS, PERSONNEL ACCIDENTALLY TRIPPED THE OIL FAULT PRESSURE RELAY INSIDE TRANSFORMER WHICH TRIPPED BREAKER REMOVING 161 KV SOURCE SIGNIFICANCE STATION BLACK 0UT INDUCED BY MAINTENANCE DISCUSSION PLANT SHUTDOWN FOR REFUELING DIESEL GENERATOR 1 MANUALLY STARTED 3 MINUTES AFTER LOSS OF 0FFSITE POWER SHUTDOWN COOLING WAS RESTORED 5 MINUTES AFTER LOSS OF 0FFSITE POWER 161 KV SUPPLY WAS REGAINED 41 MINUTES AFTER LOSS OF POWER EDG 2 WAS INOPERABLE AT THE TIME BECAUSE A NEW TURB0 CHARGER WAS BEING INSTALLED FOLLOWUP NRR WILL REVIEW FORT CAlll0UN TECHNICAL SPECIFICATIONS REGARDING DIESEL GENERATOR OPERABILITY DURING REFUELING REGION IS FOLLOWING PLANT ACTION

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!! ARCH 30,1987 CALVERT CLIFFS 2 - LOSS OF SHUTDOWN COOLING AND LOW PPESSURE SAFETY INJECTION PARCH 24 AND 25, 1987 - (S. A MCNEIL, NRR)

PROBLEP: WHILE IN P0DE 6, ALL SHUIDOWN COOLING TO LEIT 2 WAS EQUIRED TO BE SECURED DUE TO A PIPE CRACK IN THE LOW PRESSUPE SAFETY INJECTION SYSTEN

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T* Wsl FOSSIBLE CAUSES:

P00R WELDING - BURN THROUGH ON INSIDE INADE0VATE PIPING SUPPORT - DISCHARGE PIPING EPANATING FROM PELIEF VALVE SUPPORTED BY ONLY ONE "U" CLAff SIGNIFICANCE:

POTE?fflAL FOR LOSS OF LOW PRESSUPE SAFETY INJECTION FOLLOWING LOCA RESULTING IN CORE UNCOVERING POTENTIAL FOR LOSS OF CAPABILITY TO C00LDOWN THE REACTOR COOLANT SYSTEM BELOW 300*F AT A C0hTROLLED RATE POTEhTIAL FOR SIMILAR SAFETY SYSTEM PIPING FAILURES DISCUSSION:

1300 PARCH 24 - PIN HOLE LEAKS DISCOVERED IN 3/4" PIE STUB TO RELIEF VALVE 2 RV 439 PIPING PAffJFACTURED, WELDED, TESTED AND INSPECTED IN ACCORDANCE WITH ANSI B31.7 PIE STUB C0ft0N TO BOTH SHUIDOWN COOLING SYSTEM (AND LOW PRESSURE SAFEIY INJECTION) HEADERS - CANNOT BE ISOLATED WITHOUT SECURING ALL SHUTDOWN COOLING (LOW PPESSUPE SAFETY INJECTIOFD

.- 1 i

i CALVERT CLIFFS 2 - (CON'T) 2330 - PIN HOLE LEAKS PROPAGATED INTO CRACK STARTING AT SOCKET WELD AND SPIRALLING UP PIPE STLB (150' CIRClWERENCE). WAS LEAKING WATER LICENSEE SECURED SHlITDOWN COOLING ADEQUATE DECAY HEAT REMOVAL WAS PROVIDED BY SPENT FUEL POOL COOLING SYSTEM 1015 MARCH 25 - REPAIRS INITIATED - REPLACING PIR Wilh STUB TUBE WITH WELDED ENDCAP 1230 - PEPAIRS C&PLETE. SHllTDOWN COOLING RESTORED LOCA - DESIGN BASES DURING DBA ARE KT WITH THE OPERATION OF THE SAFETY INJECTION TANKS AND ONE HIGH-PRESSURE (740 GPM) AND ONE LOW-PRESSUPE (f4500 GPM) SAFETY INJECTION Pl&

FOLLOWUP:

LICENSEE: - REPLACE STUB TUBE /ENDCAP WITH PIPING WITH RELIEF VALVE

- DETERMINE CAUSES OF MATERIAL FAILUPE NRR: - REVIEW MATERIAL FAILURE CAUSE FOR SAFELY IMPLICATIONS, BOTH PLANT-SPECIFIC AND GENERIC

- INVESTIGATE SAFETY SIGNIFICANCE OF POTENTlhl FOR LOSS OF ALL LOW

. PRESSURE SAFETY INJECTION DUE TO A PASSIVE FAILUPE l

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MARCH 30, 1987 CATAVBA 2 - LOAD REJECTION TEST PERFORMED AFTER OCCURRENCE OF A PCS t!NIDENTIFIED LEAV REQUIRING SHUTDOWN MARCH 23, 1987 - (K. JABBOUR, NRR)

PROBLEM: A 100% POWER LOAD REJECTION TEST PERFORMED AFTER THE OCCURRENCE OF A RCS LEAK IN THE RANGE OF 1.5 TO 2 GPM CAUSE: LICENSEE ASSESSED LEAKAGE AND PERF0PMED TEST WITHIN THE 4 HOUR WINDOW ALLOWED BY TECHNICAL SPECIFICATIONS, SIGNIFICANCE: POTENTIAL FOR INCREASING THE RCS LFAK DUE TO INCREASE IN PRIMARY PRESSURE SEQUENCE OF EVENTS:

LICENSEE WAS WAITING FOR AN OPPORTilNITY TO PERFORM THE 100% LOAD REJECTION TEST PRIOP TO A PLANNED REACTOR SHUTDOWN. LICENSEE'S PERSONNEL WERE TRAINED TO PERFORM THE TEST.

AT 12:05, 3/23/87, UNIDENTIFIED LEAK GREATER THAN 3 GPM (I.E., 1.5 - 2 GPM)

LICENSEE ASSESSED THE OPERATIONAL AND DESIGN ASPECTS (I.E., WORK REQUESTS ON NON-SAFETY VALVES, LOG ON SAFETIES, STRESS CORROSION,

~

. LEAK BEFORE BREAK, TRENDING OF THE LEAK), THEN DECIDED TO PUN THE 100% POWER LOAD REJECTION TEST.

AT 15:20, MAIN GENERATOR BREAKER OPENED.

TURBINE CONTROL VALVES CLOSED AS DESIGNED.

OIL PRESSURE WENT DOWN CAUSING STOP VALVE TO CLOSE.

REACTOR TPTPPED THEN TURBINE TRIPPED. PLANT IN HOT STANDPY (MODE 3)

PRIMARY PRESSURE INCREASED FROM 2250 PSIG TO 2280 PSIG.

STEAM DUMP AND ATMOSPHERIC DUMP VALVES OPENED.

SYSTEMS FUNCTIONED AS DESIGNED, ONLY ANOMALY WAS 2 ADVs WERE-SLOW TO CLOSE. LICENSEE IS ADJUSTING THESE VALVES.

4:00, 3/24/87, LEAK IDENTIFIED IN PRESSURIZER PORV PACKING.

LICENSEE IS REPA! RING THE VALVE, BROKEN STEM REPLACED, FOLLOWUP: .

RESTART PLANNED FOR 4/5/87.

NRR AND REGION II WILL FOLLOWUP ON COPRECTIVE MEASURES.

PARCH 30,:1987 OTHER EVENT OF INTEREST INDUSTPY CHECK VALVE INITIATIVES (J. STONE, IE)

1. IMP 0 SOER 86-3 ISSUED OCTOBER 15,.1986 UTILITIES TO IDENTIFY VALVES BASED Oil THEIR EXPERIEtlCE AS WELL AS VALVES IN IDENTIFIED SYSTEMS.

UTILITIES TO DEVELOP ENHAt!CED TEST AtlD IriSPECTION PROGRAM PERIODIC OPERATIONAL TEST (BOTH DIRECTI0tlS)

SURVEILLANCE MONITORING (ACOUSTIC ATJD VIBRATI0t: ANALYSIS)

~

DISASSEMBLY II. INP0 FOLLOWUP INCLUDE ON-SITE EVALUATIONS I

START AFTER APRIL 1, 1987.

ItJITIAL EVALUATIONS EXPECT AS A MINIMUM

PLAN FOR IDENTIFYING CHECK VALVES AND SOME PROGRESS TOWAPD-IDENTIFICATION REASONABLE SCHEDULE FOR IMPLEMENTillG STAFF RESPONSIDLE FOR IMPLEMEllTATION PREPARING FOR ACTION.

AS EVALUATIONS PROCEED EXPECT MORE IN WAY OF IMPLEMENTATION INPO EVALUATIONS ON 18-M0!!TH CYCLE. EXPECT FULL IMPLEMENTATION AT END OF CYCLE.

EVALUATIONS WILL EXAMINE DATA BASES TO IDENTIFY PROBLEM SYSTEMS Ot! A PLANT SPECIFIC BASIS AtlD PROBLEM VALVE-TYPES GENERICALLY 111. DESIGN / APPLICATION GUIDE OWrJERS GROUP TASK FORCE OVEPSEEING DEVELOPMENT.

EPRI SERVING AS CONTRACT MANAGEP.

CONTRACTOR SELECTED.

DRAFT EXPECTED IN AUGUST, 1987.

FINAL EXPECTED IN OCTOBER, 1987.

ESTIMATED TO TAKE l-YEAP TO IDENTIFY DESIGN DEFICIENCIES.

ESTIMATED TO TAKE 3-YEARS TO COMPLETE CORRECTION OF IDENTIFIED

. DESIGN DEFICIEtlCIES.

MARCH 30,-1987 2

IV. OTHER ACTIONS INP0

- PORKSHOP ON CHECK VALVES IN ATLANTA, OCTOBER 30-31.

-- GOOD UTILITY REPRESENTATION.

REGIONAL WOPKSHOPS ON CHECK VALVE ISSUES BEING CONSIDERED.

GATHERING UTILITIES.WITH PROGRAMS WITH GOOD FEATURES TO WRITF l GOOD PRACTICES BEING CONSIDERED.

SOER ON SURRY PIPE WALL THINNING. -

NRC

- LETTER, DATED FEBRUARY 27, 1987, TO OWNERS GROUP TASK FORCE URGING SCHEDULE ACCELERATION.

3 .,

INCLUDED CHECK VALVES IN IN 86-106 SUPPLEMENT 1 ON SURRY EVENT BRIEF OF ACRS SUBCOMti1TTEE ON RELIABILITY SCHEDULED FOR-APRIL 8, 1987 INSPECTIONS AT SELECTED PLANTS TO DETERMINE STATUS AND

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ADEQUACY OF UTILITY ACTIONS ON CHECK VALVES DEVELOPING TEMPORARY INSTRUCTION FOR INSPECTING ABOUT

FIVE PLANTS J -

CONSIDERING PARTICIPATING IN INPO EVALUATION AS AN OBSERVER l

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0 t F. ARCH 30, 1987 OTHER EVENT OF INTEREST CLINT0, - MillTIPLE CONTROL R0D DRIFT CAllSED BY LOSS OF INSTRl! MENT AIR MARCH 22 1987 - (E WEISS, IE)

PROBLEM: SEVERAL CONTROL RODS BEGAN TO DRIFT IN CAUSES:

INSTRUMENT AIR ISOLATED OPERATORS DID NOT RESET ALARM FOR " SCRAM PILOT AIR PRESSURE LOW"

~

ROOT CAUSE OF CONTAINMENT ISOLATION IS STILL UNDER INVESTIGATION SIGNIFICANCE: ALARMS NOT RESET'CAN MISLEAD OPERATORS DISCUSSION:

INSTRUMENT " AIR PRESSURE LOW" ALARM ACKF0WLEDGED DAYS EARLIER BUT NOT RESET INADVERTENT CONTAINPENT ISOLATION OCCllRPED (MAY BE CAUSED BY ANALOG TRIP MODULE OR LOAD DRIVER DEVICE)

.. AIR PRESSURE DROPS LOW EPOUGH TO OPEN SCRAM OUTLET VALVES

~

WHILE VENT AND DRAIN VALVES REMAIN OPEP TIME (SECONDS) EVENT 0 RODS DRIFT 28 MODE SWITCH TO S/D (SCRAM) 31 "A" VENT.AND DRAIN CLOSE 43 SCRAM SIGNAL ON HI INSTR VOL(IV) 44 "B" VENT CLOSE 49 "B" DRAIN CLOSE AIR PRESSURE REGULATOR IS SET T0 79 PSI TOLERANCE AIR PRESSURE ALARM OCCURS AT 72 PSI AIR PRESSURE ALARM RESET REQUIRES 78 PSI TESTS SHOW AIR PRESSURE DROPS FROM 75 PSI TO 45. PSI IN 9 i MINUTES -

, l FOLLOW-UP:

UTILITY ADDRESSING CONCERNS RAISED IN READINESS INSPECTION MARCH 2 - 6, 1987 (MULTIPLE ALARMS IN CONTROL ROOM) l l

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S CR/W CAUEE COWEP tiUMBE' 1CE7- 1*E6 :9EE OF L,E El 'LY " WEEKLY .  !!IES :LY SCRAP:? 'Fi AVE:' AGE AVERAGE A'/EP A?E YTD (0) (4: , ( 9 ) ' 3 .'

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MANUAL VS AUTO E RAM 5 TYPE i! UMBER 1987 ice 6 19EE OF WEEFLY WEEKLY WEEV;. V SCRAMS- AVERAGE AVE *. AGE A'.ECA?E YTD a

MANUAL SCRAME O 1.3 1.0 1.O AL'TOMATIC SCRAMS 7 7.1 '7,9 9.4 I

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.9

3 e NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL. REVIEW OF 50.72 REPORTS ,

FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH i MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS kHICH RESULT IN ROD MOTION, AN'D EXCLUDE PLANNED 1 TESTS OR SCRAPS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

4

2. RECOVERY COMPLICATED ~BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNP. ELATED TO CAUSE OF SCRAM. .

0 -

3. 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR t

TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS

IN A GIVEN CATEGORY AND DIVIDING BY.52 WEEKS / YEAR.'

l l 4. IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND i MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING

! OPERATINGLICENSES). THIS YIEt DS AN AVEoAGE RATE Or 4.iTRIPS j PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK  !

. FOR ALL REACTORS.

t 5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

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

I 1

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL'

! CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

i

8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS f IN 1985. WEEKLY DATA DETERMINED RY TAKING TOTAL TRIPS IN A GIVEN.

j CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.  !

l

9. IN 1985. THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL l UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). TPIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

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