ML20214P937
| ML20214P937 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Indian Point, Cooper, Arkansas Nuclear, Cook, 05000000 |
| Issue date: | 11/21/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8612040432 | |
| Download: ML20214P937 (13) | |
Text
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. NOV 21 586 MEMORANDUM'FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE 0PERATING REACTORS EVENTS MEETING ON NOVEMBER 10, 1986 - MEETING 86-39 On November 10, 1986,~an Operating Reactor Events meeting (86-39) was held to
.brief the Office Director, the Division Directors and their representatives on-events which occurred since 'our last meeting on hovember 3,1986. The list of attendees is included as Enclosure 1..
The events discussed and the significant elements of these events are presented in Enclosure 2. N/ Gary M. - Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.: See Next Page DISTRIBUTION
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NOV 211986 Harold R..Denton i cc: R. Vollmer G. Gears I J. Taylor D. Muller ! R. Starostecki D. Clark C.'Heltemes M. Wegner D. Ross .- D. Jaffe T. Hurley, Reg. I
- A. Thadani J. Nelson Grace, Reg. II N. Thomasson J. - Keppler, Reg. III R. D. Martin, Reg. IV
.J. B. Martin, Reg. V W. Kane 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. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield G. Lainas E. Rossi V. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. ~ Arlotto l
r-NOV 211986 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS ~ BRIEFING (86-39)
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NOVEMBER 10, 1986 NAME DIVISION NAME DIVISION R. Vollmer- NRR J. Rosenthal IE/EAB M.J. Virgilio ORAS/NRR W. Haass IE/VPB D. Tondi ORAS/NRR S. Aggarwal RES/ DES D. Basdekas RES/RAB D. Muller DBL /NRR G. Bagchi PWRA/NRR. G. Plumlee PBF0/NRR D. Crutchfield -PWRB/NRR G. Cwalina DHFT/NRR C. Miller PWRB/NRR D. Allison EAB/IE G. Murphy NOAC/0RNL C. Cheng PWRB/NRR R. Weller PWRB/NRR B. Boger DHFT/NRR F. Brenneman ORAS/NRR T. Chang DSR0/NRR M. Chiramal AEOD J. Stewart IE/EGCB E. Weiss IE/DEPER A. Thadani PWRB/NRR R. Baer- IE/DEPER D. Humenansky OCM W. Swenson ORAS/NRR M. Wegner IE/DEPER G. Gears BWD2/NRR N. Thomasson AE0D D. Tarnoff ORAS/NRR L. Kelly PDB6/NRR
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ENCLOSURE 2 1 OPERATING REACTORS EVENTS BRIEFING 86-39 NOVEMBER 10, 1986 OTHER EVENTS OF INTEREST PEACH BOTTOM 3 CONTROL R0D-UNC0UPLING MILLSTONE 2 RESULTS OF EDDY CURRENT TESTING 0F STEAM GENERATOR
-TUBES DEFICIENCIES IN SEISMIC ANCHORAGE OF ELECTRICAL AND CONTROL PANELS 4
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IIT l OTHER EVENT OF INTEREST
'l PEACH BOTTOM 3 - CONTROL ROD UNC00PLING !
NOVEMBER 5, 1986, (G, GEARS, NRR) PROBLEM: UNCOUPLING 0F CONTROL R0D (CR) FROM CONTROL R0D DRIVE DETECTED BY OVERTRAVEL CHECK AT POSITION 48 (FULL OUT) CAUSE: PROBLEM WITH IMPROPER FILTER ENGAGEMENT AS DISCUSSED IN EARLIER GE SERVICE INFORMATION LETTER SIGNIFICANCE: SMALL POTENTIAL FOR R0D DROP ACCIDENT DISCUSSION: UNIT 3 WAS IN EARLY START-UP PHASE WITH ONLY ONE CR OUT CONTROL R0D NO 10-47 INDICATED UNC00PLING AT POSITION 48 AFTER OVERTRAVEL CHECK. R0D COUPLINGS VERIFIED AS RODS ARE WITHDRAWN TO FULL OUT POSITION. R0D WAS INSERTED AND THEN DISARMED ELECTRICALLY PER TECH SPECS REACTOR PLACED IN COLD SHUTDOWN _ CR # 10-47 TESTED AND COUPLING WAS AGAIN ESTABLISHED CONTROL ROD PATTERN ADJUSTMENTS BEING INVESTIGATED TO PERMIT CONTINUED FULL POWER OPERATION FOLLOWUP: REGION FOLLOWING LICENSEE ACTIONS
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4 OTHER EVENT OF INTEREST MILLSTONE 2 - RESULTS'0F EDDY CURRENT TESTING'(ECT) 0F STEAM GENERATOR' TUBES IN NOVEMBER 1986 1 (M' WEGNER, IE) [' '
. PROBLEM:
1986 FOLLOWUP 0F EXPERIMENTAL CHEMICAL CLEANING DONE IN MARCH 1985 AND SUBSEQUENT INSPECTION FINDS DEGRADATION OF STEAM GENERATOR TUBES-CAUSE: CORROSION
. SIGNIFICANCE: RATE OF STEAM GENERATOR TUBE DEGRADATION DISCUSSION:_
MILLSTONE 2'HAD A HISTORY OF STEAM GENERATOR TUBE DEGRADATION IN 1983, TUBES WERE REMOVED AND EXAMINED FLAWS WERE FOUND IN THE SLUDGE PILE AREA 0F THE TUBES WHICH CORRESPONDED TO DIST0RTED EDDY CURRENT SIGNALS, INDICATING THAT THE SLUDGE WAS MASKING EDDY CURRENT SIGNALS IN 1985, CHEMICAL CLEANING'0F THE STEAM GENERATORS WAS CONDUCTED TO REMOVE THE SLUDGE WHOSE PRINCIPAL COMPONENTS WERE IRON AND COPPER, 85 0UTAGE RESULTS S/G 1 S/G 2 PLUGGED 23 TUBES 40 TUBES SLEEVED HOT LEG COLD LEG HOT LEG COLD LEG 591 ENDS 1116 ENDS 143 ENDS 1068 ENDS FLAWS WERE CHARACTERIZED AS PITTING IN THE SLUDGE PILE REGION, i TOTALS PRIOR TO 1986 0UTAGE
- S/G 1 S/G 2 PLUGGED 967 TUBES 799 TUBES
[ SLEEVED H0T LEG COLD LEG H0T LEG COLD LEG 591 ENDS 2007 ENDS 143 ENDS 2187 ENDS TOTAL SLEEVED 2598 ENDS 2330 ENDS
2
- MILLSTONE 2 ,
i DISCUSSION: CONTINUED !' INFORMATION NOTICE 85-37 ISSUED WHICH DISCUSSED CHEMICAL CLEANING AND SLEEVING AT MILLSTONE 2-SLUDGE LANCING DONE IN 1986 REMOVED SIMILAR AMOUNT AND TYPE OF SLUDGE AS F0UND IN 1985 TESTING IN PROGRESS - TO BE COMPLETED AB0VT 11/16 (INCLUDING ANALYSIS OF ECT TRACING)
' RESULTS AS OF 11/06 S/G 1 - 12,250 0F'12,500 TUBE ENDS EXAMINED
- 8,170 ANALYZED
- 352 DEGRADED, TO BE SLEEVED S/G 2 - 9,500 0F 13,100 TUBE ENDS EXAMINED
- 6900 ANALYZED
- 125 DEGRADED, TO BE SLEEVED 3 TUBES DEGRADED BEYOND SLEEVING' LIMITS FOUND IN 100% TUBE LENGTH-TESTS IN S/G 1 - TO BE PLUGGED FLAWS'ARE CHARACTERIZED AS PITTING IN THE SLUDGE PILE REGION REPLACING CONDENSERS - USING TITANIUM TUBES TO REPLACE COPPER-NICKEL ALLOY-WHICH REPLACED ADMIRALTY METAL FEEDWATER HEATER TUBING ORIGINALLY ADMIRALTY METAL, NOW 304 OR 409
- STEEL, EXCEPT 7TH STAGE '
i FOLLO'WUP: ! IE WILL CONTINUE TO EVALUATE LICENSEE'S REPORT l A FOLLOWUP INFORf1ATION NOTICE MAY BE WR'ITTEN'F0LLOWING EVALUATION OF THIS OUTAGE i-1 i
( OTHER EVENT OF INTEREST DEFICIENCIES IN SEISMIC ANCHORAGE OF ELECTRICAL AND CONTROL PANELS (N. THOMASSON, AE0D) PROBLEM: INADEQUATE SEISMIC ANCHORAGE 0F ELECTRICAL AN CONTROL PANELS CAUSE: INSTALLATION ERROR AND INADEQUATE QA SIGNIFICANCE: REPORTED DEFICIENCIES ARE WITH ELECTRICAL AND CONTROL SYSTEMS THAT ARE ASSOCIATED WITH REDUNDANT AND DIVERSE SAFETY SYSTEMS DEFICIENCIES INVOLVE TOTAL ABSENCE OF SEISMIC ANCHORAGE DEFECTS EXISTED SINCE ORIGINAL CONSTRUCTION ORIGINAL DESIGNS SPECIFIED ANCHORAGES DISCUSSION: LER DATA
- DRESDEN (1/2/3) - NONE OF THE CONTROL ROOM PANELS WERE ANCHORED TO THE FLOOR (4/86)
- COOPER - SWITCHGEAR GENERATOR OUTPUT BREAKER CABINETS FOR BOTH EMERGENCY DIESEL GENERATORS LACKED ANCHORAGE TO EMBEDDED CHANNELS (3/86)
- DAVIS-BESSE - CABINETS FOR ESSENTIAL INSTRUMENT 120 VAC POWER LACKED BOLTS TO HOLD D0 ORS SHUT (2/86); AUXILIARY SHUTDOWN PANEL TERMINAL NOT SEISMICALLY MOUNTED (12/82)
- COOK - SWITCHGEAR CABINETS, REACTOR TRIP AND BYPASS BREAKER CABINETS LACKED SUFFICIENT RESTRAINTS (8/81 & 8/83)
_ - BROWNS FERRY - EIGHT LOCAL REACTOR PROTECTION PANELS IN EACH UNIT NOT CONSTRUCTED PER DRAWINGS OR DOCUMENTATION WAS LACKING (1/85)
- ANO-] LACKED ANCHORS FOR ALL CONTROL ROOM PANELS ADDITIONAL FINDINGS FROM A-45 RESOLUTION
, - TWO PLANTS LACKED ANCHORAGE FOR 4 KV SWITCHGEAR BUSES l - TWO PLANTS LACKED ANCHORAGE ON BUS SWITCHGEAR AND MOTOR l GENERATOR SETS
- THREE PLANTS HAD INADEQUATE SUPPORT FOR BATTERY RACKS AND LACKED ANCHORS IN THE RACK SUPPORTS FOLLOWUP:
NRR GENERIC LETTER FOR THE 70 USI A-46 PLANTS TO BE ISSUED IN THE l NEAR FUTURE (~ DEC.1986) INFORMATION NOTICE TO ALL PLANTS ON SEVERAL DEFICIENCIES IDENTIFIED TO DATE RECOMMENDED BY AEOD TO COMPLEMENT THE GENERIC LETTER
I I~ . - - - . - . ~ . . .. REACTOR SCRAM
SUMMARY
WEEK ENDING 11/09/06 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD YTD CATIONS ADOVE EELOW TOTAL WITH 15% 15% FR C'ES 11/04/86 PEACH BOTTOM 3 1A EQUIPMENT NO 5 3 8 0 11/06/E6 INDIAN POINT 2 97 A EQUIPMENT NO 10 1 11 0 me
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. s II.2 COMPARISON OF1 WEEKLY. STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK'ENDING
. 11/09/86
, , SCRAM CAUSE~ ' POWER NUMBER 1986 -.'1985 lF O WEEKLY - WE EKLY SCRAMS.(5) AVERAGE AVE AGE YTD- (: :) (4) i oo POWER >15% EQUIP. RELATED >15% -- i
-PERS. RELATED(6) >15%
4.5 5.4-(68%) 0 1.9 .2.0.(25%)- OTHER(7) >15% O- 0.5,
## Subtotal ** 0.6-( 7%)
1 6.9 :8.0
. en: POWER <15%
. EQUIP. RELATED <15%
PERS. RELATED <15%. 1 1.4 1.3 (54%) O O.8 0.9 (35%)
!OTHER <15% 0 0.2' co-Subtotal 1** O.2 ( 8%)
1 2.4
, 0 ** Total *** 2.4 2 9.3 10.4 MANUAL VS AUTO SCRAMS
~ TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE' YTD
' ' MANUAL SCRAM 3 O 1.0 1.0 AUTOMATIC SCRAMS 2 8.3 9.4 h
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C NOTES , i
- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF 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),SYSTEMDESIGN,ORUNKNOWNCAUSE.
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