ML20210H034
| ML20210H034 | |
| Person / Time | |
|---|---|
| Issue date: | 09/23/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8609260043 | |
| Download: ML20210H034 (18) | |
Text
_
$(P 2 3 m MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON SEPTEMBER 15, 1986 - MEETING 86-32 On September 15, 1986, an Operating Reactor Events meeting (86-32) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 15, 1986. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events ere 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 approaching the due date.
Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
Af/
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page DISTRIBUTION Central File i
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3D 2 51986 Harold R. Denton cc:
R. Vollmer F. Akstulewicz J. Taylor C. Grimes C. Heltemes R. Hermann D. Ross J. Zwolinski T. Murley, Reg. I K. Jabbour J. Nelson Grace, Reg. II B. J. Youngblood J. Keppler, Reg. III R. Dudley R. D. Martin, Reg. IV G. Lear J. B. Martin, Reg. V M. J. Campagnone R. Starostecki, Reg. I D. Wagner S. Ebneter, Reg. I E. Adensam R. Walker, Reg. II B. Brady C. Norelius, Reg. III M. Williams E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero 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 P. Baranowsky
SEF 13196 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-32)
SEPTEMBER 15, 1986 NAME DIVISION NAME DIVISION H. R. Denton NRR R. Woodruff IE/DEPER R. H. Vollmer NRR B. Brady AEOD/PTB G. Holahan NRR/0 RAS C. Grimes NRR/ISAPD B. Boger NRR/DHFT D. Wagner NRR/BWD3 J. Clifford NRR V. Benaroya NRR/PAF0 D. Vassallo NRR/F0B C. Thomas NRR/PWRB G. Murphy ORNL/NOAC M. Williams AE00 D. Basdekas RES/RAB A. Dromerick IE/EGCB G. Klingler IE/DI/0RPB J. Stone IE/DQAVTP R. Hernan NRR/PPAS K. Jabbour NRR/PWRA J. Henderson IE J. Rosenthal IE/DEPER T. Novak NRR/PWRA C. Rossi NRR/PWRA F. Schroeder NRR/PWRB W. Swenson NRR/0 RAS F. Akstulewicz NRR/DPWRL-B M. Virgilio NRR/0 RAS J. T. Beard NRR/0 RAS E. Weiss IE E. Adensam NRR/BWR D. Tarnoff NRR/0 RAS
ENCLOSURE 2 OPERATING REACTOR EVENTS BRIEFING 86-32 i
SEPTEMBER 15, 1986 I
1 NINE MILE POINT'1 SCRAM OUTLET VALVE DIAPHRAGM FAILURE 4
CATAWBA 1 LOOSE PART IN REACTOR VESSEL 4
SAN ONOFRE 1 FEEDWATER PUMP FAILURE j
SUSQUEHANNA 2 RHR HEAT EXCHANGER INLET FLANGE EROSION 1
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OTHER EVENTS OF INTEREST i
HADDAM NECK MAIN FEEDWATER REGULATING VALVE FAILURE AEOD STUDY OF MAIN FEEDWATER REGULATING VALVE i
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NINE MILE POINT 1 - SCRAM OUTLET VALVE DIAPHRAGM FAILURE SEPTEMBER 8, 1986 (ERIC WEISS, IE)
PROBLEM:
THRU WALL CRACK 0F DIAPHRAGM IN SCRAM OUTLET VALVE CAUSES SINGLE ROD SCRAM SIGNIFICANCE:
i IF SCRAM INLET VALVE HAD THIS FAILURE AND OUTLET VALVE REMAINED CLOSED, THEN THE CRD COULD BE DAMAGED AND STUCK AGING MAY PROVIDE COMMON-MODE MECHANISM FOR THIS FAILURE (PRESSURE SPIKE IN AIR LINE COULD CAUSE MULTIPLE FAILURES)
PREVENTATIVE MAINTENANCE PRACTICES AND SHELF LIFE ARE NOT SPECIFIED BY GE GENERIC TO ALL GE BWRs CIRCUMSTANCES:
PLANT WAS AT 100% POWER SINGLE R0D SCRAMMED BECAUSE SCRAM OUTLET VALVE ON HCU OPENED PLANT DROPPED 30MWE (RATED 630 MWE)
HCU ISOLATED, PLANT CONTINUES OPERATION AT POWER THRU-WALL RADIAL CRACK IN 6" RUBBER DIAPHRAGM 0F SCRAM OUTLET VALVE LICENSEE EXAMINING 5 SETS OF VALVES WHILE PLANT REMAINS AT POWER PLANT CHANGED OUT 124 DIAPHRAGMS (62 CRDs) IN 1975 AND 10 MORE SINCE THEN; REMAINING DIAPHRAGMS ARE ORIGINAL TO THE PLANT SURVEY BY LICENSEE SHOWS OTHER PLANTS HAVE REPLACEMENT PROGRAM ESTIMATED SHELF LIFE OF 7 YEARS PRINTED ON PACKAGE CONTAINING REPLACEMENT DIAPHRAGM HYPOTHESIS FOR CRD DAMAGE RECOGNIZED BY RESIDENT INSPECTOR AND LISTED IN DAILY REPORT.
GE BELIEVES DIFFERENT SPRING RATES PREVENT DAMAGE.
LICENSEE ASKING GE TO TEST HYPOTHESIS, FOLLOW-UP IE CONSIDERING INFO NOTICE IE FOLLOWING LICENSEE ACTIONS WITH ASSISTANCE OF RESIDENT INSPECTOR
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CATAWBA 1 - LOOSE PART IN REACTOR VESSEL SEPTEMBER 5, 1986 - (K. JABBOUR, NRR)
PROBLEM:
ONE UPPER HEAD INJECTION (UHI) N0ZZLE DETACHED FROM THERMAL SLEEVE DURING FIRST CYCLE OF OPERATION SIGNIFICANCE:
POTENTIAL FOR DAMAGE TO RCS COMPONENTS GENERIC IMPLICATION REGARDING OTHER UHI FACILITIES SEQUENCE OF EVENTS:
FIRST REFUELING OUTAGE COMMENCED AUGUST 9, 1986, UPON REMOVAL 0F RV HEAD, AN UNIDENTIFIED OBJECT WAS'FOUND ON TOP 0F UPPER SUPPORT PLATE OBJECT WAS MOVED TO REACTOR CAVITY POOL AREA FOR INSPECTION INSPECTION REVEALED THE OBJECT TO BE ONE OF FOUR UHI N0ZZLES THREADS ARE APPARENTLY INTACT AND THE LOCKING PIN IS IN THE N0ZZLE INDICATIVE THAT N0ZZLE UNTHREADED N0ZZLE IS CONNECTED VIA THREADS TO THERMAL SLEEVE.
LOCKING PIN IS THEN INSERTED AND TACK WELDED DUKE DECONTAMINATED N0ZZLE AND IS INSPECTING IT TO DETERMINE ROOT CAUSE OF FAILURE PIN WAS BENT WHICH ALLOWED THE THREADS TO DISENGAGE LOOSE PARTS MONITOR DID NOT IDENTIFY ANY INDICATIONS OF A LOOSE-PART, POSSIBLY DUE TO LOW FLOW IN THAT REGION FOLLOW-UP:
l DUKE PLANS TO INSTITUTE APPROPRIATE CORRECTIVE ACTIONS SUCH AS PROVIDING ADDITIONAL TACK WELDS FOR ALL FOUR UHI N0ZZLES REGION II AND NRR ARE FOLLOWING UP ON DUKE'S INSPECTIONS AND CORRECTIVE ACTIONS NRR FOLLOW-UP ON APPLICABILITY TO OTHER UHI PLANTS l
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SAN ON0FRE 1 - FEEDWATER PUMP FAILURE SEPTEMBER 4, 1986 - (R. WOODRUFF, IE)
PROBLEM:
RECENTLY REPLACED SHAFT FOR WEST MAIN FEEDWATER PUMP FRACTURED SIGNIFICANCE:
LOSS OF ECCS RELIABILITY DISCUSSION:
DURING A LOCA, BOTH MAIN FEEDWATER PUMPS PERFORM AS INTERMEDIATE HEAD SAFETY INJECTION PUMPS APPROXIMATELY MAY 1985, THE ORIGINAL SHAFT IN THE WEST PUMP FRACTURED - THE SHAFTS IN THE EAST AND WEST PUMPS WERE REPLACED ON SEPTEMBER 4, THE REPLACEMENT SHAFT IN THE WEST PUMP FRACTURED DUE TO LOW STRESS, HIGH CYCLE FATIGUE THE FRACTURED SHAFT WAS ANALYZED BY FAILURE ANALYSIS ASSOCIATES LICENSEE IS PLANNING TO STARTUP THIS WEEK PENDING INFORMAL APPROVAL BY REGION V FOLLOW-UP:
REGION V IS FOLLOWING REPAIR AND INSPECTION OF PUMPS REGION FOLLOWUP ON ROOT CAUSE OF SHAFT FAILURE L
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SUSCUEHANNA 2 - RHR HEAT EXCHANGER INLET FLANGE EROSION SEPTEMBER 3, 1986 (D, WAGNER, NRR)
PROBLEM:
SEVERE EROSION IN THE SERVICE WATER INLET PIPE FLANGE TO BOTH RHR HEAT EXCHANGERS (HXs)
SIGNIFICANCE:
THROUGH-WALL EROSION ON BOTH RHR Hx INLET FLANGES WOULD CAUSE LOSS OF RHR HEAT REMOVAL CAPACITY DISCUSSION:
VISUALLY DETECTED FROM INSIDE "A" Hx PIPING DURING TUBE INSPECTION EROSION DAMAGE IS TO THE FLANGE TO WHICH THE INLET THROTTLE VALVE (BUTTERFLY VALVE) IS BOLTED "A" Hx METAL LOSS WAS APPR0XIMATELY 3/8" "B" Hx METAL LOSS WAS APPR0XIMATELY 1/2" (DETERMINED BY ULTRASONIC TESTING)
UNIT 2 "A" AND "B" RHR Hx SERVICE WATER INLET FLANGES REPLACED LICENSEE BELIEVES EROSION CAUSED BY THROTTLING FLOW WITH BUTTERFLY VALVE AT LOW FLOWS - REDIRECTING FLOW TO SIDE OF FLANGE WALL UNIT 1 BELIEVED NpT TO BE AFFECTED SINCE BUTTERFLY VALVES HAVE NOT BEEN USED AT SAME FLOW CONDITIONS 1
FOLLOW-UP:
LICENSEE INVESTIGATING OTHER POSSIBLE CAUSES OF PROBLEM RESIDENT INSPECTOR FOLLOWING UP ON LICENSEE'S ACTIONS NRR FOLLOWUP TO DETERMINE IF THIS PROBLEM IS RELATED TO ESSENTIAL SERVICE WATER (ESW) SYSTEM CORROSION PROBLEM WHERE ESW PUMPS HAD TO BE REPLACED i
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OTHER EVENTS OF INTEREST HADDAM NECK - MAIN FEEDWATER REGULATING VALVE FAILURE AUGUST 30, 1986 (F. AKSTULEWICZ, NRR)
PROBLEM:
THE LICENSEE EXPERIENCED A STEM TO PLUG WELD FAILURE OF THE #1 MAIN FEEDWATER REGULATING VALVE (MFRV).
SIGNIFICANCE:
THE FAILURE OF THE VALVE RESULTED IN ABNORMAL LEVELS IN THE STEAM GENERATOR AND A MANUAL PLANT TRIP.
SUBSEQUENT NORMAL PLANT C00LDOWN OCCURRED DISCUSSION:
VALVES ARE FISHER MODEL #657-AVR PLUG VALVES WELD INSPECTION REVEALED LACK OF FUSION GREATER THAN 50% IN SOME AREAS MFRV VENDOR CONCURS THAT MANUFACTURING DEFECT WAS THE CAUSE OF FAILURE ALL OTHER MFRVs INSPECTED AND NO DISCREPANCIES WERE FOUND CURRENT PREVENTATIVE MAINTENANCE PROCEDURES REQUIRE INSPECTION AND REBUILDING 0F MFRVs AND AIR OPERATORS EVERY OUTAGE FOLLOWUP:
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(B BRADY, AE0D BRIEFING SLIDE CONTAINS PROPRIETARY INFORMATION l
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SUMMARY
WEEK ENDING 09/14/86 I. PLANT SFECIFIC DATA
, DATE SITE UNIT POWER RPS CAUSE COMFLI-YTD YTD YTD I
CATIONS ABOVE BELOW TOTAL 15%
15%
I 09/09[86 INDIAN POINT 3
95 A EQUIP / MECH.
NO 6
2 8
09/09/86 CALLAWAY 1
100 A EQUIP / MECH.
NO 6
1 7
09/09/36 WATERFORD 0
100 A EQUIPMENT NO 4
0 4
09/10/86 RODINSON 2
99 A FERSONNEL/ TEST. NO 7
2 9
09/10/86 LACROSSE 1
OA EQUIPMENT NO 4
7 11 09/10/86 LACROSSE 1
1 A FERSONNEL NO 4
8 12 l 09/11/86 FALO VERDE-2 100 A EQUIFMENT NO 6
2
'8 i 09/11/86 SALEM 2
75 A EQUIP / ELECT.
NO 5
2 7
1 09/12/86 FALO VERDE 1
100 A EQUIPMENT NO 11 0
11 i 09/12/S6 CALVERT CLIFFS 2
100 M FERSONNEL NO 5
0 5
l 09/10/86 BRUNSWICK 1
100 A EQUIP / ELECT.
YES 4
1 5
09/10/86 SAN ONOFRE 2
60 A EQUIP / ELECT.
NO 6
2 8
j 09/10/96 LACROSSE 1
OA UNKNOWN NO 4
9 10 t 09/14/86 PEACH BOTTOM 50 M EQUIP /HI MS RAD NO 4
2 6
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4
SUMMARY
OF COMPLICATIONS i SITE UNIT COMPLICATIONS ERUNSWICK 1 SONICS INDICATED ALL SRVs CYCLED BUT TAIL PIFE TEMP-INDICATED 0 DID NOT LIFT i
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II. COMPARISON OF WEEl:LY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 07/14/86 SCRAM CAUSE POWER NUMBER 1996 1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAEE YTD (3) (4)
- POWER >15%
EC L' I P. RELATED
>15%
9 4.9 5.4 (68%)
PERS. RELATED(6) >15%
2 2.0 2.0 (25%)
OTHER(7)
>15%
0 O.6 O.6 ( 7%)
- + Subtotal *+
11 7.5 0.0
- + POWER <15%
EQUIP. RELATED
-:15%
1 1.5 1.3 (54%)
PERS. RELATED
'15%
1 1.0 0.9 (38%)
OTHER
<15%
i O.2 O.2 ( 8%)
- Subtotal **
3 2.7 2.4
- Total **+
14 10.2 10.4 MANUAL VS AUTO SCRAMS TYFE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2
1.O 1.O AUTGMATIC SCRANS 12 9.1 9.4
NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF 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, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
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Fage'No.
l' 09/23/96 0FERATINS REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETINS E6-32 CN SEPTEMIER 15,1996 (IN ASCENDIh5 MEETINS DATE, NSSS VENDOR, FACILITY ORDER) 9EETINS FACILITY RESPCNSIELE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUGEER/
NSSS VENDOR /
DIVISION!
COMFLET.
BY DOCUMENT, MEETINS EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
HTE E6-10 OYSTER CFEEK NRR / HOUSTON W RESOLVE THE QUESTION OF THE 10/30/86 0 FEN
/ /
FOLLOCP ACi!CN 10 03/31/E6 GE / LEVEL
/
ACCEPTAEILITY OF ELIND SWITCHES
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PE INCCFFORATED IN SWITCH SETPOINT AND DELET10N OF DA!LY CHANNEL
/ /
REVIEW 0F JL'NE DRIFT CHECK 1.19E6 EVENT AT LASSALLE E6-21 VERMONTYAktEE NER /HDLAHAN S.
EETERMlhE STATUS AND 09/30/26 CFEN
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06/23/E6 BE / FRDSLEMS
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EFFECTIVENESS OF STAFF AND
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WITH SCRAM LICENSEE ACTION ON
//
SDLENDID VALVES POST-MAINTENANCE TESilNS (BL 03-28). DEVELOP RECOMMENDAT!0NS FOR FURTHER ACTION E6-23 FEFRY hER / HOUSTON W.
OBTAIN AND REVIEW INFORMATION 09/30/66 CLOSED 09/15/96 07/07/06 EE / FIRE IN
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RELATED TO RECURRENCE OF FIRE 02/29/86 SEPTEMEER 0FFGASCHARC0AL AND INVESTIGATE FR0 POSED
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9,1996 MEMD J.
BEDS ACTIONS STEFAND TO 6.
HDLAHAN 86-23 MULT!
NER / HOUSTON W.
DETERMINE APPROFRIATE 09/30/86 CPEN
//
07/07/96 NA /
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RESULATORY REQUIREMENTS BASED
/ /
PWRS-RESIDUAL ON RECC".MENDAT!0NS DISCUSSED AT / /
HEAT REMOVAL ERIEFINS FUMP/ WEAR RING FAILURES -
FOLLOWUP 66-:S SRAND EULF IE / JORDAN E.
ASSESS PDTENTIAL FOR SENERIC 09/30/86 0 FEN
/ /
02/11/26 GE / CONTROL R0D
/
AFPLICAPILITY
/ /
WITHLRAWAL
/ /
PROBLEM 96-32 NINE MILE FT 1 NRR / ROSA F.
DISCUSS WITH LICENSEE AND 10/24/E6 0 FEN
//
09/15/26 GE / SCRAM hRR libOLINSKI J.
RESIGN LICENSEE'S
/ /
OUTLET VALVE IMPLEMENTATION OF GL B3-28 IN
/ /
DIAPHSRAM REFERENCE TO 09/09/96 EVENT FAILURE