ML20212N677

Summary of Operating Reactor Events Meeting 86-29 on 860818 to Discuss Events Which Occurred Since Last Meeting on 860811,including Improper Ring Settings on PWR Main Steam Safety Valves

ML20212N677
Person / Time
Site:	Arkansas Nuclear, Vermont Yankee, 05000000
Issue date:	08/25/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8608290114
Download: ML20212N677 (19)

Text

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Aug 2 31986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Rea . tor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON AUGUST 18, 1986 - MEETING 86-29 On August 18, 1986, an Operating Reactor Events meeting (86 29) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 11, 1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclosure 3 with regard to their respective responsibilities.

> Note that several assignments are a proaching the due date. Please be responsive andadviseORAS(D.Tarnoff,X27864 if the target completion date cannot be met.

M/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTIGN 3

' Central File' NRC PDR-ORAS Rdg ORAS Members 035 DTARNOFF:

BC:0 RWESSMAN D:0 RAS GHOLAHAN h ,;

3 /14/86 / /2 z./86 j/g/86 @A 09y 8608290114 860823 F

PDR ADOCK 05000271 S PDR

AUS 25 EES Harold R. Denton .

cc: R. Vollmer V. Rooney .

J. Taylor D. Muller '

C. Heltemes R. Lee ~

D. Ross J. Stolz T. Murley, Reg. I B. Doolittle J. Nelson Grace, Reg. II V. Noonan J. Keppler, Reg. III M. Miller R. D. Miirtin,' Reg. IV B. J. Youngblood J. B. Mo.-tin, Reg. V R. Starostecki, Reg. I ,

S. Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia

_ R. Berr.ero -

T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield '

. G. Lainas

~*

V. Benaroya W. Regan D. Vassallo

. E. Jordan E. Rossi R. Baer

~

E. Weiss R. Hernan S. Showe ,

S. Rubin c P. Baranowsky l

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AUG15 EEE ENCLOSURE 1 LIST OF ATTENDEES OP_ERATING REACTORS EVENTS BRIEFING (86-29)

AUGUST 18, 1986 NAME DIVISION NAME DIVISION '

G. M. Holahan NRR/0 RAS . R. Benedict hRR/F0B-B F. Cherny DSR0/EIB B. Riggs DSR0/SPEB R. Frahm DSR0/SPEB S. Black NRR/PPAS E. Butcher TSCB/DHFT G. Murphy ORUL/NOAC J. Stolz NRR/PBD6 C. Graves DLR/RSB V. Rooney DBL /PBD2 W. Paulson

{_ NRR/PBD2 .

D. Trimble RI/IE G. Klingler IE/DI

~

_ S. Rubin -AE00 J. Giitter' IE/DEPER -

A. Dromerick IE/DEPER M. Wegner IE/DEPER V. Benaroya NRR/PAF0 J. Henderson IE/EGCB W. Regan NRR/PBF0 M. Caruso NRR/0 RAS E. Doolittle NRR/DPLA H. Rood NRR/PWR7 W. Haass IE/VPB J. Ramsey NRR/PBD6 D. Crutchfield NRR/PWRB C. Miller NRR/PWRB

_ D. Humenansky OCM D. Muller NRP/ DBL

R. Houston NRR/ DBL W. Swenson NRR/0 RAS M. Virgilio NRR/0 RAS J. T. Beard NRR/0 RAS E. Rossi NRR/PWRA R. Baer IE/EGCB J. Rosenthal IE/EAB R. Starostecki .IE S. Varga NRR/ PAD 3 E. Jordan IE/DEPER D. Tarnoff NRR/0 RAS e

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, , ENCLOSURE 2

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OPERATING REACTOR EVENTS BRIEFING 86-29 AUGUST 18, 1986 p

s VERMONT YANKEE RECIRCULATION FLOW INSTABILITY w -

ARKANSAS NUCLEAR ONE' P0TENTIAL COMMMON MODE FAILURE OF EMERGENCY

.. DIESEL GENERATORS MULTIPLANT , , , IMPROPER RING SETTINGS ON PWR MAIN STEAM

' SAFETY VALVES

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VERMONT YANKEE - RECIRCULATION FLOW INSTABILITY AUGUST 11, 1986 (ERIC WEISS, IE)

PROBLEM: PERIODIC RECIRC. FLOW INSTABILITIES OF ABOUT 1% AFTER RECIRC. PIPE REPLACEMENT SIGNIFICANCE: .

SAFETY SIGNIFICANCE OF OSCILLATIONS IS UNDER REVIEW CIRCUMSTANCES:

PLANT STARTUP ON 7/2/86 FOLLOWING RECIRC PIPE REPLACEMENT FLOW AN0 MOLY NOTED IN "A" LOOP ONLY

[_ TOTAL CORE FLOW INCREASES ABOUT 0.33%, 3 OR 4 TIMES PER HOUR -

~

APRM LEVELS INCREASE IS LESS THAN 1%

NO CHANGE IN M/G SET SPEED OCCURS IN NEW PIPE BECAUSE OF MINOR CHANGES IN:

DIAMETERS'; SM0OTHNESS; LENGTH SIMILAR PHENOMEN0N AFTER RECIRC PIPE REPLACEMENT AT PILGRIM

. AND SANTA MARIA DE GARONA (SPAIN)

_ . CAUSE IS FLOW INSTABILITY IN " CROSS" 0F RECIRC RISER HI-LOSS / LOW-FLOW REGIME DOMINANT LOW-LOSS /HI-FLOW REGIME OCCURS RANDOMLY (4 PER HOUR)

FOLLOWUP:

NRR EVALUATING PHENOMENON VIA CONTRACT WITH EG8G NRR PREPARING ANSWERS FOR SPANISH INQUIRY .

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JUNE 26, 1986 (R, LFE, NRR)

PROBLEM 1 LARGE AMOUNT OF SLUDGE / SEDIMENT IN EDG FUEL SYSTEM SIGNIFICANCE DEGRADATION OF EMERGENCY POWER SUPPLY POTENTIAL COMMON MODE FAILURE OF EDGs -

WEAKNESS IN TECH SPEC FUEL OIL SURVEILLANCES

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• GENERIC APPLICABILITY

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CIRCUMSTANCES UNIT 2 IN REFUELING OUTAGE; UNIT 1 OPERATING AT POWER UNIT 2 EDG NO, 2 18-MONTH LOAD TEST TERMINATED NEAR THE END OF 24-HOUR RUN DUE TO FUEL STARVATION; TEST FAILURE NOT CONSIDERED REPORTABLE, UNIT 2 EDG N0, 1 TESTED SUCCESSFULLY FOR 24 HOURS INVESTIGATION REVEALED FUEL STARVATION CAUSED BY CLOGGED-UP

i. STRAINER IN EDG FUEL SYSTEM INSPECTION OF DAY FUEL TANK ASSOCIATED WITH EDG N0, 2 REVEALED LARGE AMOUNT OF SLUDGE / SEDIMENT, THE OTHER UNIT 2 DAY FUEL TANK AND l

UNDERGROUND FUEL STORAGE TANKS HAD LESSER AMOUNT OF SLUDGE / SEDIMENT .

l TECH SPEC SAMPLING & TESTING OF DIESEL FUEL FAILED TO DETECT. PROBLEM i

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ARKANSAS NUCLEAR ONE - CONTINUED .

UNIT 2 EDG FUEL TANKS DRAINED AND CLEANED ,

. SAMPLES FROM UNIT 2 SENT FOR DETAILED ANALYSIS VISUAL OBSERVATION OF SAMPLES FROM UNIT 1 DAY FUEL TANKS DID NOT INDICATE SIMILAR PROBLEM REGION IV REPORTED OCCURRENCE TO HEADQUARTERS ON AUGUST 12, 1986 ABOUT 8,000 GALLONS OF FUEL FROM EACH UNIT 1 UNDERGROUND STORAGE TANK WERE RECIRCULATED THRU 5 MICRON FILTER TO BULK STORAGE TANK. FILTER ELEMENT BEING INSPECTED SAMPLE FROM DAY FUEL TANK WILL BE TAKEN AND ANALYZED WHENEVER FUEL IS TRANSFERRED FROM UNDERGROUND FUEL STORAGE TANKS T0 e- DAY FUEL TANK -

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UNIT 1 FUEL TANKS WILL BE DRAINED AND CLEANED IN UPCOMING REFUELING OUTAGE EXPECTED TO BEGIN ON THE FIRST WEEK 0F SEPTEMBER 4

FOLLOW-UP PROJECT MANAGER TO INITIATE REVIEW 0F TECH SPECS

. REGION IV AND NRR WILL REVIEW LONG TERM CORRECTIVE ACTIONS REGION IV IS FOLLOWING UP ON THE REPORTABILITY OF THIS EVENT

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IE CONSIDERING NEED FOR IE INFORMATION NOTICE

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MULTI-PLANT: IMPROPER RING SETTINGS ON PWR MAIN STEAM SAFETY VALVES (M. CARUS 0, NRR)

PROBLEM: RECENTTESTSANDINSPECTIONREVEALIMPROPERRIkGSETTINGSON

. INSTALLED AND T0-BE-INSTALLED PWR MAIN STEAM SAFETY VALVES (MSSV) ,

SIGNIFICANCE:

P0TENTIAL INADEQUATE OVERPRESSURE PROTECTION POTENTIAL LEAK PATH FROM STEAM GENERATOR GENERIC PROBLEM BACKGROUND: .

BASIC FUNCTION OF RINGS 1982 EPRI TESTS SHOW LESS THAN FULL LIFT ON DRESSER PRESSURIZER CODE SAFETY VALVES PLANTS WITH DRESSER VALVES REQUIRED TO PROVIDE JC0 AND CHANGE

[_ RING SETTINGS AT NEXT OUTAGE -

EARLY 1985 - TESTS OF SEABROOK STEAM SAFETY VALVES (CROSBY)

.f SHOW'LESS THAN FULL LIFT WITH FACTORY RING SETTINGS; SETTINGS MODIFIED BASED ON ADDITIONAL FULL FLOW TESTS EARLY 1986 - IE INFORMATION NOTICE 86-05 ISSUED RECENT EVENTS:

MILLSTONE 3 -JUNE / JULY 1986

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INSPECTION PER NOTICE 86-05 REVEALS RING SETTINGS ON ALL 20 VALVES SUBSTANTIALLY DIFFERENT THAN FACTORY RECOMMENDED SETTINGS (DRESSER)

QA/ COMMUNICATIONS BREAKDOWN ALL VALVES RESET TO FACTORY SETTINGS V0GTLE - JUNE 1986 FULL FLOW TESTS SHOW LESS THAN FULL LIFT WITH FACTORY SETTINGS SETTINGS MODIFIED SUBSTANTIALLY BASED ON ADDITIONAL FULL FLOW TESTIN3 BY. VALVE VENDOR (CROSBY)

FOLLOWUP:

INFORMATION NOTICE ON MILLSTONE 3 AND V0GTLE BEING PREPARED DRAFT GENERIC LETTER REQUESTS BASES FOR SAFETY VALVE CAPACITY USED IN ASSURING THAT PLANT DESIGN MEETS GDC 15  :

BROUGHT TO ATTENTION OF ASME CODE COMMITTEE; CODE BEING REVISED TO REQUIRE EACH VALVE TO BE FULL-FLOW, FULL-PRESSURE TESTED BY MANU?ACTURER PRIOR TO SHIPMENT.

DSR0 510DY OF RISK SIGNIFICANCE ONG0ING

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7 REACTOR SCRAM

SUMMARY

WEEK ENDING 08/17/06 -

I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RFS CAUSE CCMiLI-YTD' 'YTD YTD -

CATIONS ABOVE"BELOW TOTAL 15% 15%

08/11/06 FEACH BOTTOM 3 86 A EQUIP / ELECT. NO 3 2 5 03/11/06 DRESDEN 2 91 A UNKNOWN NO 3 1 4 08/12/96 MILLSTONE 2 97 A EQUIP / ELECT. NO 2 0 2

- 08/12/06 MCGUIRE 2 100 A PERSONNEL NO 3 2 5 09/12/96 SAN ONOFRE 2 100 A UNKNOWN NO 5 2 7 08/13/06 TURLEY POINT 3 55 A LIGHTNING NO 4 1 5 08/13/06 COOPER 1 90 A UNKNOWN NO 2 0 2 08/14/06 NORTH ANNA 1 OA PERSONNEL /CALIB NO 4 2 6 08/15/96 PALO VERDE 1 50 A UNKNOWN NO 8 0 8 08/17/86 MILLSTONE 3 11 A COUIP/MFW CONTP NO 3 8 11 09/17/86 MILLSTONE 3 20 A EQUIP /MFW CONTR NO 4 8 12 C-

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.a II. COMPARISON OF WEEKLY STATISTICE WITH INDUSTRY AVERAGES

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SCRAMS FOR WEEK ENDING 08/17/86 SCRAM CAUSE POWER NUMBER 1986 1985 ,

OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE YTD (3) (4)

• • POWER >15%

EDijlP. RELATED >15% 3 4.5 5.4 (68%)

PERS. RELATED(6) >15% 1 . 2.0 2.0 (25%)

OTHC3(7) >15% 5 0.6 0.6 ( 7%)

oo Seatotal **

9 7.1 8.0

• POWER R 15%

EQUIP. RELATED (15% 1 1.5 1.3 (54%)

.PERS. RELATED <15% 1 1.0 0.9 (38%)

_OTHER <15% 0 0.2 0.2 ( 8%) '

ET Subtotal **

2 2. 7- 2.4 f** Total ***

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11 9.8 10.4 MANUAL VS AUTO SCRAMS

' TYPE NUMBER 19G6 1985

- - OF WEEKLY WEEKLY

- SCRAMS AVERAGE AVERAGE YTD MANtJAL SCRAM 5 O O.8 1.0 AUTOMATIC SCRAMS 11 9.0 9.4

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NOTES

1. PLAfd SKCIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 KPORTS '

FOR TE WEEK OF INTEREST, PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGiT SUNDAY SCRAMS nE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SlUIT,0WN IN ACCORDANCE WITH A PLANT PROCEDURE, t

2. KC0VERY C0FPLICATED BY EQUIPENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM, 3, 1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF

.f UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR, -

4. IN 1985, THEE WERE AN ESTIMATED TOTAL OF 541 AlITOMATIC AND

. MAN'JAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5,8 TRIPS KR REACTOR KR YEAR AND AN AVERAGE RATE OF 10,4 TRIPS KR WEEK FOR ALL REACTORS.

5. BASED ON 100 REACTORS HOLDING A PJLL POWER LICENSE,

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

7. "01ER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIR0tifNTAL CAUSES (LIGHINING), SYSTEM DESIGN, OR UNKNOWN CAUSE, _

~

Page No. .I ENCLOSURE 3

, 09/20/06 OPERATING REACT uS EVENTS MEE!!NS FOLLOWu? ITEMS AS OF MEETING 96-29 DN AUGUST 19,1986-IIN ASCENDIN6 MEETING DATE, NSSS VENDOR, FACilliY ORDER)

RESFDNSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS MEElINS FACILITY DIVISION / COMPLET. BY DOCUMENT, QMBER/ NSSSVENDOR/

INDIVIDUAL DATE(S) MEETING,ETC.

MEETIN3 EVENT DESCRIP.

DATE 96-10 OYSTER CREEK NRR / HOUSTON W RESOLVE THE CUESTION OF THE 10/30/96 0 FEN / / FOLLOWUP ACTION TO

/ ACCEPTABILITY OF BLIND SWITCHES / / BE INCORPORATED IN 03/31/06 GE / LEVEL AND DELET10N OF DAILY CHANNEL / / REVIEW OF JUNE SWITCH SETPOINT CHECK 1,1986 EVENT AT DRIFT LASSALLE 96-21 VERMONT YANKEE NRR /HOLAHAN E. DETERMINE STATUS AND 09/30/96 0 FEN / /

06/23/B6 GE / FRDBLEMS / EFFECTIVENESS OF STAFF AND / /

WITH SCRAM LICENSEE ACTION ON / /

SOLEh01D VALVES FOST-MAINTENANCE TESilNG (SL B3-2Bl. DEVELOP RECOMMENDAT10NS

- F03 FURTHER ACTION C-96-21 TURlrEY F0thi hRR / ROSA F. CONSIDER REVIEWING ELECTRICAL 09/30/96 0 FEN / /

- 06/23/96 W / POTENTIAL / SYSTEM 0F FLANT WITH SIMILAR / /

FAILUPE OF ALL SWING BUS DESIGN / /

EMERGENCY O!ESEL GENERATORS ,

66-23 PERRf NRR / HOUSTON W. OBTAIN AND' REVIEW INFORMAT10N 09/29/06 0 FEN / /

07/07/B6 GE / FIRE IN / RELATED TO RECURRENCE OF FIRE / /

. GFFEAS CHARC0AL ANDINVEST14ATEFROFDSED / /

EEDS ACTIONS 66-23 MULTI NRR / HOUSTON W. LETERMINE AFFROPRIATE 09/30/E6 0 FEN / /

. 07/07/E6 NA / / REGULATORY REQUIEEMENTS BASED / /

EWRS-FESIEUAL ON RECOMMENDATIONS DISCUSSED AT / /

HEAT FE"0 VAL ERIEFING Fl;MP/WELR RING FAILUPES -

FOLLOWUP E6-23 MULil NRR /SEALINSER C. AS60RE NkR AND IE COORDINATION 08/30/06 0 FEN / /

07/07/96 NA / / TO DETERMINE THE NEED FOR AN !E / /

FWRS-!NACEDUATE BULLETIN / /

DESIGN OF ECCS PUMP MINIMud FLOW FATHS

66-26 RA%CHO SECO I hRR /REGAN W. FIND OUT IF FUMPS ARE bSED IN 08/30/96 CLO5ED 08/19/06 07/26/06 EW / EDTH TFAINS / OTHER SYSTEMS AT RANCHO SECO 'I / AUGU6T 19, 1996 0F DECAY HEAT . / / MEMQD.

CRUTCHFIELD TO REMOV4L DECLARED TECHhlCALLY

6. H. HOLAHAN INOFERAELE

Page No. 2 3-08/20/96 c GPERATING REACTORS EVENTS MEETINB FOLLOWUP ITEMS AS CF MEETING 96-29 DN AUGUST 18,1986 l.

(IN AECENDING MEETING DATE, hSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESP 0t.SIBLE TpSKDFSCRIPTION SCHEDULE CLD5ED DATE COMENTS NUMBER / NSSS VENDOR / DIVIS!:M/ '

COMFLET. BY DOCUMENT, MEETING EVENT DESCRIP. INDIVII,UAL DATE(S) MEETING,ETC.

DATE E6-26 RANCHO SECO 1 NRR /REGAN W. FULL 0d!!P DN USE OF FERMINITE IN 02/30/96 CLOSED 08/1Bf86 07/29/96 BW / EDTH TFAINS / FUMPS DRAIN LINE / / AUGUST 19,1986 0F DECAY HEAT / / MEC D.

^

REMOYAL DECLAFED ~

CRUTCHFIELDTO TEthMICALLY 6. H. HDLAHAN

INOFERAELE 26-28 SRAND GULF IE / JORDAN E. ASSESS POTENTIAL FOR SENERIC 09/30/06 0 FEN / /

02/11/E6 SE / CONTROL ROD / APPLICAilLITY / /

WITHDRAWAL l' /

- PROBLEM G-

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