ML20126G072

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Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430
ML20126G072
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/22/1992
From: Bevan R
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9301040051
Download: ML20126G072 (43)
v • d • e


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[p ua k UNITED STATES W i n NUCLEAR REGULATORY COMMISSION 3,h g  !

/ WASHINGTON. D C N%6

% , , , , , *# December 22, 1992 Docket No. 50-368 LICENSEE: Entergy Operations, Inc.

FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)

SUBJECT:

SUMMARY

Of MEETING ON DECEMBER 3, 1992, CONCERNING STEAM GENERATOR INSPECTION, TESTING, AND REPAIRS AT ANO-2

, Representatives of Entergy Operations, Inc., the licensee for ANO-2, met with the NRC staff on December 3,1992, to discuss the results of the ANO-2 steam generator (SG) tube examination during the most recent scheduled outage (2R9) and the licensee's plan for a "mid-cycle" tube inspection, scheduled to begin April 30, 1993. Meeting attendees are listed in Enclosure 1. Handout materials presented by the licensee during the meeting are contained in Enclosure 2.

By way of background, the licensee reviewed the recent history of SG inspections at ANO-2. During the 1991 planned inspection (2R8) many indications were found in both "A" and "B" SGs by eddy current testing. Using the bobbin coil method, both intergranular attack (IGA) and stress corrosion cracking (SCC) were found on the outside diameter (0D) of tubes, primarily in the tube support plate regions. Repairs were made by plugging defective tubes. However, in March 1992, primary-to-secondary leakage developed from a circumferential crack in the tube-to-tube sheet area, forcing an unplanned outage (2F92) for repairs to be made. During that outage, the expansion transition regions of the hot leg of all tubes (in both "A" and "B" SGs) were examined by eddy current testing using the rotating pancake coil (RPC), as were 20% of tubes in the sludge pile region (cold leg) of the "A" SG. No cold leg indications were found. Repairs were made to 488 tubes. Most repairs were made in "A" SG tubes, and most were repaired by sleeving rather than plugging.

In the most recent tube examination, performed during the 1992 scheduled outage 2R9 in September 1992, a 100% full length bobbin coil inspection was performed on both SGs, and a 100% RPC inspection was performed in the expansion transition region of the hot legs of both SGs. Again, RPC examination of a 20% sample of sludge pile reaions of both cold legs revealed no indications. Of the 199 tubes repaired (all by plugging),132 tubes were plugged in the "B" SG.

In addition, during 2R9, seven tubes were pulled for metallographic examination, chemical analysis, and physical 3roperties testing of tubing and  !

tube materials. Detailed information about tie physical and chemical properties of the tube samples was compared with the original specifications, procurement requirements, properties of similar Combustion Engineering (CE) SG tubes (high temperature mill annealed) and similar Inconel 600 tubing g

materials. A conclusion drawn by the licensee from the study was that 9301040051 921222 ADOCK 05000368 1, ')l i i

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P PDR L , , - -, .m rg 77

1 y o circumferential cracking found in ANO-2 tubes is similar to that found at other CE plants. Also, future cracking rates could be estimated by correlating ANO-2 and M111 stone-2 crack data. From such correlations, it can be shown that all cracks )rojected to be present at the end of the current operating cycle will not lave grown to beyond acceptable through-wall depth.

The case was made by the licensee that statistical projections of crack growth conservatively support a summer 1993 timeframe for mid-cycle shutdown (2P93) for further eddy current inspection. The licensee plans a "mid-cycle" inspection of tubes to begin April 30, 1993. At this time they will do a modified 100% RPC examination of the tube-to-tube sheet hot leg areas (the area of circumferential cracking) in both SGs. A bobbin coil examination of the two tubes that were missed during the 2R9 inspection will also be done.

The licensee appeared to have properly correlated ANO-2 data with that from other sources and to have come to technically supportable conclusions that justify continued operation until April 30, 1993.

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Roby B an, Project Manager Project Directorate IV-1 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation

Enclosures:

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1. List of attendees
2. Handout cc w/ enclosures:

See next page DISTRIBUT10tj:

Docket file NRC & LPDRs PD4-1 r/f T. Murley/F. Miraglia J. Partlow J. Roe M. Virgilio J. Larkins R. Bevan T. Alexion R. Young P. Noonan 0GC E. Jordan B. D. Liaw G. Johnson K. Karwoski H. Rathbun H. Conrad ACRS (10)

J. Mitchell, EDO A. B. Beach, RIV n i n0 0FC LA:PD4d PE:PD4-[M ht:fSL BC:EMCBN D:PD4.J n NAME PNo'onadh'RYoung [RBeb:p#k JStrosn}b r JLkNs DATE Q /M /92 lk/fR92 11/t /92 2

l'2717/9Y /2 /2L/92 0FFICIAL RECORD COPY Document Name: AR2Dec3.mts

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  • j circumferential cracking found in ANO-2 tubes is similar-to that found at  !

other CE plants. Also, future cracking rates could be estimated by correlating ANO-2 and M111 stone-2 crack data. From such correlations, it can be shown that all cracks arojected to be present at the end of the current oaerating cycle will;not lave grown to beyond acceptable through-wall depth.

11e case was made by the licensee that statistical projections of crack growth conservatively support a summer 1993 timeframe for mid-cycle shutdown (2P93) for further eddy current inspection.- The licensee plans a "mid-cycle" inspection of tubes to begin April 30, 1993. At this time they will do a modified 100% RPC examination of the tube-to-tube sheet hot leg areas (the area of circumferential cracking) in both- SGs. A bobbin coil examination of the two tubes that were missed during the 2R9 inspection will also be.done.

The licensee appeared to have properly correlated ANO-2 data with that from other sources and to have come to technically supportable conclusions that justify continued operation until April 30, 1993.

hhtMw RobyBfvan,ProjectManager-Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1. List of attendees
2. Handout cc w/ enclosures:

See next page

, s 4

Entergy Operaticns, Inc. Arkansas Nuclear One, Unit 2 cc:

Mr. Donald C. Hintz, President Mr. John R. McGaha and Chief Executive Officer Vice President, Operations Support Entergy Operations, Inc. Entergy Operations, Inc.

P. O. Box 31995 P. O. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Robert B. McGehee Mr. R. A. Fenech Wise, Carter, Child & Caraway General Manager, Plant Operations P. O. Box 651 Entergy Operations, Inc. Jackson, Mississippi 39205 Route 3 Box 137G Russellville, Arkansas 72801 Mr. Charles B. Brinkman, Manager

! Washington Nuclear Operations Mr. Nicholas S. Reynolds ABB Combustion Engineering Nuclear Power Winston & Strawn 12300 Twinbrook Parkway, suite 330 l 1400 L Street, N.W. Rockville, Maryland 20852 1

Washington, D.C. 20005-3502 Admiral Kinnaird R. McKee, USN (Ret)

, Mr. Robert B. Borsum 214 South Morris Street

. Licensing Representative Oxford, Maryland 21654 B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Mr. James J. Fisicaro Rockville, Maryland 20852 Director, Licensing Entergy Operations, Inc.

Senior Resident inspector Route 3, Box 137G U.S. Nuclear Regulatory Commission Russellville, Arkansas 72801 1 Nuclear Plant Road Russellville, Arkansas 72801 Mr. Jerry W. Yelverton Vice President, Operations ANO Regional Administrator, Region IV Entergy Operations, Inc.

U.S. Nuclear Regulatory Commission Route 3 Box 137G 611 Ryan Plaza Drive, Suite 1000 Russellville, Arkansas 72801 Arlington, Texas 76011 Honorable Joe W. Phillips County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dieus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markhahi Street Little Rock, Arkansas 72205-3867

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Enclosure 1 December 3. 1992-Meetina Between Reoresentatives of Enterav Operations. Inc..and NRC Staff Steam Generators at Arkansas Nuclear One. Unit 2 List of Attendees Hamg Oraanization Roby Bevan NRR/PDIV-1 John T. Larkins NkR/PDIV-1 B. D. Liaw NRR/DE George Johnson NRR/DE Dale Powers NRC/ Region IV/DRS Ken Karwoski NRR/DE Cliff Eubanks Entergy Ops /;ngr. Programs Darol Harrison Entergy Ops /ANO .

Bill Eaton Entergy Ops /ANO James Fisicaro Entergy Ops /AN0/ Director, Licensing Randall K. Edington Entergy Ops /V-2 Plant Manager Donald B. Lomax Entergy Ops /ANO Richard S. Maurer ABB-CE/Mgr. NDE Technology William C. McKelvy Entergy Ops /AN0/ Chemistry Support Sterling V. Weems MPR Associates Lynn Connor STS Howard Rathbun NRR/PDIV-1 Craig Smith Baltimore Gas & Electric Paul Klein Baltimore Gas & Electric /Mtis. Eng.

Gerard Fink ABB-CE/ Corrosion Technology ,

Dale James Entergy Ops Ronald Young NRR/PDIV-1 H. F. Conrad NRR/EMCB M. Virgilio NRC/DRPW

i l ENCLOSURE 2  !

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) INFORMATION UPDATE CONCERSING THE l ANO-2 STEAM GENERATORS i

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DECEMBER 3,1992 l

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OPERATIONS l

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'l AGENDA-

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STEAM GENERATOR MEETING

DECEMBER 3,1992 1

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I. INTRODUCTION R. EDINGTON i-

, II. OVERVIEW C. EUBANKS i III.

SUMMARY

/ CONCLUSIONS C. EUBANKS 4

4 IV. TECHNICAL EVALUATION D. HARRISON

V. ENIIANCEMENTS C. EUBANKS VI. INSPECTION SCOPE FOR 2P93 C. EUBANKS l VII. OVERALL CONCLUSIONS R. EDINGTON i

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REVIEW OF PREVIOUS INSPECTION DATA I I

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3 % INSPECTION SAMPLES (BOBBIN) THROUGH 2R7 (1980 - 1989)

I REPAIRS THROUGH 2R7 (1989) WERE ASSOCIATED l WITH PRESERVICE REPAIRS AND WEAR AT THE i

B ATWING SUPPORTS (14 IN "A" AND 36 IN "B")

INSPECTIONS DURING 2R8 (1991)

BEGAN WITH 3% BOBBIN ECT IN EACH STEAM GENERATOR FOUND TUBE SUPPORT PLATE (TSP) DAMAGE IN

! "B" (OD - IGA AND SCC)

I EXPANDED TO 100% IN "B" AND 9% IN "A" 73 TUBES REPAIRED IN "B" AND 0 IN "A" (ALL TUBES PLUGGED) l l

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i INSPECTIONS DURING 2F92 (1992)

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  • OUTAGE DUE TO LEAKING CIRCUMFRENTIALLY i CRACKED TUBE AT THE TUBE-TO-TUBE SHEET INTERFACE l
  • MRPC FOR 100% OF BOTH HOT LEGS IN

! EXPANSION TRANSITION REGION

  • MRPC FOR 20% OF SLUDGE PILE REGION IN l COLD LEG OF "A"' STEAM GENERATOR IN

! EXPANSION TRANSITION-REGION-i NO COLD LEG INDICATIONS L

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INSPECTIONS RESULTED IN REPAIRS TO 488 L TOTAL TUBES L

! SG "A -

SG "B" i

NUMBER PLUGGED 29 11

. NUMBER SLEEVED 392 5_f TOTAL 421 ;67 j .

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i INSPECTIONS DURING 2R9 i .

100% BOBBIN FULL LENGTH "A" AND "B"* STEAM

! GENERATOR 100% MRPC OF BOTH HOT LEGS IN EXPANSION l TRANSITION REGION i

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20% MRPC OF SLUDGE PILE REGION IN BOTH l COLD LEGS IN EXPANSION TRANSITION REGION i

NO COLD LEG INDICATIONS i .

INSPECTIONS RESULTED IN REPAIRS TO 199 j TOTAL TUBES (ALL PLUGGED) i SG "A" SG "B" l CIRC INDICATIONS ** 17 8 l OTHER 1Q 124 l TOTAL- 67- 132 a

NO CRACKS EXCEEDED REG GUIDE 1.121 ACCEPTANCE CRITERIA BASED ON RPC DATA i

AND TUBE PULL EXAMINATION f

  • 'Two tubes in "B" steam generator not bobbin coil tested. Both were tested during 2R8 (Spring 1991) with no detectable degradation
    • Based on Millstone data, ANO had projected to have between 7 and 89 circumferential cracks during 2R9
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6 DRAFT REGULATORY GUIDE 1,121 ACCEPTANCE CRITERIA 4

FOR 2R9 CIRCUMFRENTIAL CRACKS t

BURST PRESSURE MUST BE > 3 AP (3AP FOR ANO-2 = 4,050 PSI) l FROM ANALYSES,79% AVERAGE THROUGHWALL PENETRATION OVER i ENTIRE CIRCUMFERENCE WITH AXIAL

EXTENT LIMITED TO 0.25 INCH l

BURST TEST DATA SUPPORTS RG LIMIT j

DAMAGE MECHANISM

)

OUTER DIAMETER STRESS CORROSION CRACKING l

-- .-- . . ~ - . ,

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INSPECTION AND REPAIR HISTORY SG 'A' SG 'B' i YEAR EFPY OUTAGE INSPECTED PLUGS SLEEVES INSPECTED PLUGS SLEEVES i 1978 0.00- MFG 2250 15 0 2250- 29 0 .'

1981 0.89 2RI 450 0 0 320 0 0 1982 1.69 2R2 839 0 0 820 1 0 1983 2.33 2R3 300 0 0 232 0 0 1985 3.31 2R4 400 0 0 400 0- 0  !

'1986 .4.16 2R5 400 0 0 400 0 e i

1988 5.38 2R6 656 0 0 926- 6 0 ,

1989 6.52 2R7 386 0 0 396 0 0  ;

I j .1991 7.67 2RS 792 0 0 8375 73 0 f

1992 8.51 2F92 8396 '29 392- 8302 11 56

! .1992 8.85 2R9 8367 67 '4

- 8291 132 0-

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! CUMULATIVE REPAIR STATUS i

j SG W SG 'B' i

hWfBER PLUGS 111 252-

! hMIBER SLEEVES 388 56 SLEEVE EQUIVALENT PLUGS 20 3 TOTAL TUBES PLUGGED 131 255-l.

PERCENT PLUGGED 1.56 % 3.04 %

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DEFECT LOCATION CAUSING REPAIR

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SG 'A' SG 'B' -

l* EXPANSION TRANSITION 416 67 f

4 EGGCRATE SUPPORTS 30 147 BATWING SUPPORTS 10 46-4

', SLUDGE PILE - 31 19 PRESERVICE 15. 29 i T 9

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/ CONCLUSIONS l

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i ANO-2 CIRC CRACKING IS SIMILAR TO THAT p FOUND AT OTHER CE PLANTS ALL CIRC CRACK INDICATIONS HAVE BEEN  :

l - IDENTIFIED AND REPAIRED NO SECONDARY SG ACTIVITY SINCE 2R9 i

l CONSERVATIVE STRUCTURAL A.NALYSES SHOWED THAT WORST CASE 2R9 SG CRACKS MET RG 1.121 STRUCTURAL REQUIREMENTS i .

PAST CRACK. NUMBER PREDICTIONS IN l

REASONABLE AGREEMENT WITH FINDINGS -

i FUTURE CRACKING RATES.HAVE BEEN-

[ ESTIMATED BASED ON ANO-2 & MP-2 l

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WITH VERY HIGH CONFIDENCE, ALL OF THE l CRACKS PROJECTED TO BE PRESENT AT 2P93 l- WILL HAVE AN EQUIVALENT DEPTH LESS j THAN THE CALCULATED RG LIMIT OF 79% TW l

AVERAGE DEPTH I

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l TUBE MATERIAL and PROPERTIES l

l INCONEL 600 MILL ANNEALED AT GREATER THAN 1800 F l

THE MICROSTRUCTURE ANALYSIS OF SIX OF l THE SEVEN PULLED TUBES IS CONSISTENT i '

WITH THAT OBSERVED FROM OTHER CE STEAM

! GENERATORS, INDICATING THAT THE TUBES ARE HIGH TEMPERATURE MILL ANNEALED j -

MODIFIED HUEY TESTS INDICATE THAT THE

TUBES ARE NOT SENSITIZED l .

MICROHARDNESS TEST RESULTS ARE CONSISTENT WITH THOSE FROM OTHER CE

! PLANTS TENSILE TEST RESULTS ARE WITHIN THE l

ORIGINAL PROCUREMENT REQUIREMENTS j .

THE CHEMICAL COMPOSITION OF THE SEVEN l PULLED TUBES CONFORM TO THE l REQUIREMENTS OF THE ORIGINAL SPECIFICATION l

ONE OF THE SEVEN TUBES PULLED EXHIBITED A. i l MICROSTRUCTURE MORE TYPICAL OF'-

l WESTINGHOUSE TYPE (LOW TEMPERATURE

[ MILL ANNEALED) INCONEL 600 t

  • PRELIMINARY DATA INDICATES THAT ONE TUBE FAILED DUE TO CAUSTIC INDUCED SCC.

j ADDITIONAL TESTING ON THAT TUBE IS CURRENTLY IN PROGRESS

- _ _ _ . _ . _ . _ _ .. _ . _ ...~. -

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[ CHEMICAL ANALYSIS l OF FLAWS SULFUR AND LEAD WERE ASSOCIATED WITH l THE DEFECT REGIONS ANALYZED

! - COPPER, WHILE PRESENTIN NOTABLE i AMOUNTS, DID NOT APPEAR TO BE ASSOCIATED l WITH THE DEFECTS SILICA AND, TO A LESSER DEGREE, CHLORIDES

! WERE ALSO FOUND IN MANY LOCATIONS l

l CAUSTIC SPECIES SUCH AS SODIUM AND l POTASSIUM HAVE NOT BEEN FOUND IN l SIGNIFICANT AMOUNTS i

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NICKEL DEPLETION IN THE OXIDES AND THE

LOW NI/CR RATIO FOUND IN THE DEFECT l REGIONS IN FIVE OF THE SEVEN TUBES ARE CONSISTENT WITH A POSTULATED ACIDIC j ENVIRONMENT l

THE PRESENCE OF LEAD AND ABSENCE OF l TRANSGRANULAR ATTACK IS CONSISTENT.

WITH AN ACIDIC ENVIRONMENT

. THE PRESENCE OF COPPER, BUT THE; LACK OF .

[ PITTING, SUGGESTS THAT THE ENVIRONMENT L WITHIN THE CREVICES IS ONLY SLIGHTLY

, ACIDIC-i l

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STEAM GENERATOR I BULK WATER CHEMISTRY
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REANALYSIS OF MULTEQ DATA SUGGESTS THAT ,

i THE STEAM GENERATOR BULK WATER HAS

! REMAINED SLIGHTLY ALKALINE TO NEUTRAL i SINCE 1986

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THE ACIDIC ENVIRONMENT WHICH INITIATED THE DAMAGE MECHANISM OCCURRED PRIOR

! TO 1986 CONTINUOUS CHEMISTRY PROGRAM IMPROVEMENTS SINCE THATTIME HAVE RESULTED IN DRAMATICALLY REDUCING IONIC IMPURITIES TO THE CURRENTINDUSTRY STANDARD AND FAR BELOW-THE EPRI GUIDELINE ACTION LEVEL RECOMMENDATIONS REMOVAL OF Cu FW HEATERS OXYGEN CONTROL MODS ON CST & CONDENSERS.

CONDENSER CHEMISTRY CONTROL TO MITIGATE PITTING PH CONTROL IMPROVEMENTS MAKEUP WATER TREATMENT SYSTEM BORIC ACID TREATMENT

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i l INSPECTION TECHNIQUE USED 3 FOR CIRCUMFRENTIAL CRACKS i

IS MRPC i

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INSPECTION OF 100% OF BOTH HOT LEGS INSPECTION OF 20% SLUDGE PILE REGION OF l COLD LEGS i

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TESTING IS PERFORMED USING SAME

! PARAMETERS AS USED AT MAINE YANKEE, l MILLSTONE, AND ST. LUCIE I

FREQUENCIES

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CALIBRATION STANDARDS PRODE TYPE i

L UPGRADED ECT ANALYSIS GUIDELINES AND I

TRAINING / TESTING PROGRAM IMPROVES

QUALITY OF DATA RECENT NRC TEAM INSPECTION YIELDED' FAVORABLE COMMENTS ABOUT OUR PROGRAM L

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! MRPC / TUBE PULL CORRELATION

FOR TUBESHEET INDICATIONS, MRPC VERSUS METALLOGRAPHY SHOWS EXCELLENT
CORRELATION FOR AVERAGE THROUGHWALL DEPTH 4

s

SUMMARY

OF 2R9 NDE DATA

SG ROW LINE PRE PULL POST PULL METALLO-1 MRPC MRPC GRAPHY s

A 79 83 0.99 VOLTS TUBE 360' AVE. 44.6%

87% TW, FAILED DURING j OVER 130'; 360* TUBE PULL AVE. 44.7%

4 A 64 48 6.34 VOLTS 30.4 VOLTS 360* AVE. 65.1%

87% TW, 95% TW, j OVER 239'; 360' OVER 271*; 360' AVE. 58% AVE. 72%

i CE SG TUBING RPC vs. WET LAB RESULTS 103 ,

90

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  • ANO-2 TUBES s .7 _

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./ 8 WP 2 TUBES 30 / + WY PWSCC SAMPLES 0 / .

0.00 20.00 40.00 60.00 80.00 100.00 RPC AVERAGE DEPTH A

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! IN SITU PRESSURE TEST l TUBE 64-48 (WORST CASE FLAW) i .

AS-FOUND CONDITION OF CRACK, PER MRPC l WAS 6.34 VOLTS,87% TW OVER 239 ,360

AVERAGE 58% TW PRESSURIZED TO 4700 PSI FOR 10 MINUTES TUBE DID NOT BURST OR LEAK i .

i l LABORATORY BURST TEST i

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TUBE 64-48 (WORST CASE FLAW) l .

POST-PULL CONDITION OF CRACK INDICATED

) DAMAGE DURING PULL. POST-PULL MRPC WAS j 30.4 VOLTS,95% TW OVER 271,360 AVERAGE--

! 72% TW -

I-DAMAGED TUBE BURST AT 5815 PSI-(4986 PSI l WHEN ADJUSTED FOR TEMPERATURE i CORRECTION TO 650 F)

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DEMONSTRATED BURST PRESSURE ON WORST-i CASE FLAW WELL ABOVE THAT REQUIRED BY R.G.1.121, EVEN AFTER DAMAGING TUBE DURING PULL.

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Phase II Results Adjusted To MP2 Operating Temperature 22000 21000 -~~-:

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Average Depth (Mft)

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F CIRCUMFERENTIAL CRACKING j EVALUATION l

BASED ON MILLSTONE-2 AND ANO-2 DATA:-

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DISTRIBUTION OF FLAW SIZE IS NOT

! DEPENDENT ON TIME l -

LARGEST CIRCUMFERENTIAL CRACKS j WERE FOUND DURING FIRST " CIRC l CRACK OUTAGE" LARGEST CIRC CRACK FOUND DURING.

! SUCCESSIVE OUTAGES TENDS TO

DECREASE IN SIZE l

NO CRACK IS EXPECTED TO BE PRESENT

! DURING 2P93 THAT EXCEEDS RG 1.121_ LIMITS, j WITH A GREATER THAN 95% CONFIDENCE LEVEL i

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. PROJECTIONS DO NOT CONSIDER THOT REDUCTION i

. PROJECTIONS UTILIZE THE LARGE

CONSERVATIVE NUMBER OF INDICATIONS L

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l WORST CASE CRACK I

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i OUTAGE = 2F92 2R9 l

TUBE NO. = 13 - 147 64-48 4

i ARC LENGTH * = 360 360 l

AVE TW* = 94 % 65 %

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* - Based on Met Lab results i

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i I ANO-2 vs. WP-2 WORST CASE CRACK

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1 CIRCUWFERENTIAL CRACK LENGTHS l ANO 2 STEAM GENERATOR TUBES f

J j 25 ,,,,, ,i i i ., ,i i,

$ I ]2F92 20 - -- -

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2F92 GAWWA DIST. ~

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l CIRCUMFERENTIAL CRACK EXTENTS l MILLSTONE 2 STEAM GENERATOR TUBES 4- MUWBER OF CRACKS

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MACROCRACK CIRCUMFERENTIAL EXTENT l

l

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! CIRCUWFEREKTIAL CRACK DEPTHS ANO-2 STEAW GENERATOR TUBES l 35 30 I- l2F92 25 _ -- -

2R9 -

U20 - - - -

GAWWA DIST -

j @i5 r_ _ _ _ n_.

30 j _ _ __ _ _ _' _f 1 ...~

I 5 0- E E " " D '" ~

l E$RNRRS?S$8 ERaaRE8 -

AVERAGE CRACK DEPTH (% TW)

CIRCUMFERENTIAL CRACK DEPTHS MILLSTONE 2 STEAM GENERATOR TUBES

NUMBER OF CRACMS

, p M TOTAL UT CRACKS f M OCT 1989 INSPECTION E MAY 1990 INSPECTION l'

30 ! '

f)l M SEPT 1990 INSPECTION 25-F C JUNE 19911NSPECTl0N

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O 5 10 15 20 25 3035404550556065 70 75 80 859095100 EQUIVALENT CRACK DEPTH (% THROUGHWALL)

l 1

CIRCUMFERENTIAL CRACK EK1'ENTS ARKANSAS NUCLEAR ONE UNIT TWO NORMALIZED GAWWA DISTRIBUTIONS l

l l l l 1 1 I I I I I I f I

j% 2F92 GAWWA DIST. [

' / cs 2R9 GAWWA DIST.

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] 1 i i F- 8  : : !B!!!.RH!RRRHXX WACROCRACK CIRCUWFERENTIAL EXTENT CIRCUMFERENTIAL CRACK EXTENTS MILLSTONE UNIT 2 STEAM GENERATOR TUBES MORMAllZED O AWW A DISTRIBUTION i

I

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- .EPT

- JUM. 1 .

9 4 e

4 i i!ii!ii!ie i ie ii!ii!e i i i i s'"4 1 4 MACROCRACK CIRCUMFERENTIAL EXTENT

j .

CIRCUWFERENTIAL CRACK DEPTHS

ARKANSAS NUCLEAR ONE UNIT TWO e

. NORMALIZED GAMMA DISTRIBUTIONS

' N I I I I I I i 1

/' Q

~

2FS2 GAWWA DIST.

i // \ 2R9 GAWWA DIST.

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22RNRE%WSE33RRS RE8 -

AVERAGE CRACK DEPTH % TW 1

i CIRCUMFERENTIAL CRACK DEPTHS MILLSTONE 2 STEAM GENERATOR TUBES

NORM Al.l!ED DISTRIBUTION j 0.4 e

i TOTAL GAMMA OtST JUNE 19910AMMA DIST l 0.3 -

- SEPT 1990 GAMMA DIST i

MAY 1990 OAMMA DIST OCT 1989 OAMMA DIST 0.2 -

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0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95100 i EQUIVALENT CRACK DEPTH (% THROUGHWALU 5

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! PROBABILITY OF A CRACK EXCEEDING A GIVEN AVERAGE DEPTN PROJECTION 37 CRACKS AT 2P93 l PROBABILITY EXPECTED NUWBER l 100 1 90 -

0.9 80 5;T '~'7.h  ; I s: 0.8 70 g.

60 -

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ENHANCEMENTS 1

4

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4 ENHANCEMENTS 1

N-16 MONITORS TIIE ABILITY TO DETECT, QUANTIFY, AND TREND PRIMARY'IO SECONDARY SO LEAKAGE IS SIGNIFICANTLY ENHANCED WITH MAIN STEAM LINE N 16 MONITORS CONTINUOUS TRENDING CAPABILITY COMPUTER READOUTS IN CONTROL ROOM DEDICATED ALARMS FOR INCREASE IN ACTIVITY LEVEL DETECTION LIMIT APPROXIMATELY I OPD OTHER SECONDARY RADIATION MONITORS CONDENSER OFF.OAS MONITORS SG BLOWDOWN MONITORS MAIN STEAM LINE RADIATION MONITORS DEDICATED CONTINUOUS TRENDING, WITH CONTROL ROOM READOUT  !

PROCEDURALLY CONTROLLED ADJUSTABLE ALARM SETPOINTS ADMINISTRATIVE LEAK RATE LIMIT = 0.1 GPM (TECH SPEC LIMIT = 0.5 GPM)

UPON ANY CONTROL ROOM ALARM CHEMISTRY AND 0

OPERATIONS EACH ENTER ABNORMAL OPERATING PROCEDURES WITH LEAK RATE it 0.1 GPM, PLANT SHUTDOWN !S l PROCEDURALLY REQUIRED L

ANO IS SENSITIVE 'ID POTENTIAL RAPID PROOL.:.SION IN TUBE LEAKAGE AND PROCEDURALLY REQUIRES NECESSARY MEASURES TO MITIGATE TUBE LEAKAGE

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MORPHOLINE ,

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SECONDARY SIDE MORPHOLINE INJECTION ALLOWS US l TO RUN AT A HIGHER PH, THEREFORE REDUCING THE j TRANSPORT OF METALS TO THE SG AND THUS REDUCING ,

l THE SLUDGE LOADING AND ALLOWS HIGHER LEVELS OF BORIC ACID IN SECONDARY SYSTEMS

  • IN-LINS ION CHROMATOGRAPHY

}

SECONDARY SIDE CONTAMINANT DETECTION LIMITS

ARE SIGNIFICANTLY LOWER WTTH IN LINE IC

) .

ADDITIONAL MANAGEMENT INVOLVEMENT i -

SG EXECUTIVE COMMITTEE, SO INTEGRITY COMMITTEE, l: AND CORPORATE SG SPECIALIST THOT REDUCTION

[ -

REDUCED THOT FROM 607' TO APPROXIMATELY 599*

IS PROJECTED TO DECREASE CORROSION RATES, <

AND THEREFORE REDUCE THE 1DTAL NUMBER OF j DEFECTIVE TUBES 2

e i

~

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ARKANSAS NUCLEAR ONE Thct REDUCTION PROJECTIONS y

1600 i ,,,,i 1400

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607 DEG ' .4

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y 1200<- *,,

" g-W $99 DEG ,. s 1000- -

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i ARKANSAS NUCLEAR ONE i

Thot REDUCTION PROJECTIONS 003

[ 57>

Gio 607 DEG 3 ..-

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f.OO 9 WC 10 EOC 10 OUTAGE

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! 2P93 INSPECTION SCOPE f

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! 2P93 ECT SCOPE 1

MODIFIED 100% MRPC TTS HOT LEG FOR BOTH 4 STEAM GENERATORS l

LIMITED TO AREA OF CIRCUMFERENTIAL i CRACKING l APPROXIMATELY 6000 TUBES PER STEAM GENERATOR I

  • BOBBIN COIL EXAM OF TWO TUBES TO
COMPLETE 2R9 C-3 INSPECTION 4

4

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CIRCUMFERENTIAL CRACKS O = 2F32 CIRC CHACKS (401) . = 2Re CIMC 08WES (171 inAt Tuees  : e411 2P93 INSPECTION PLAN Torat Tuscs Assiseco : 41s TIE RODSte)  : 7

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W 't NJ mN N %k N\ N N'N \ % l' **O,d t

i 'IN N N N N NN%WN-% "s NT N N Nh~N N N N N N \

IN's. N N N'.E Nm#N N N N N N ;k x NxN N N N N N\ *-

/N N N h N, NA N N *s N N N N N N A.N NM N N N N N % *

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/\ \ .N N MN N,.N N NN N N'NN NX N N N N N N's' N N N N N N N' N _N,N N N N '\

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TN \ \ M \ \ X LN N N N N.\ \? X i k '

M1 NE NN N N .\ \ N \ MN N'5V h*\

r A N N N N N N N MX 't N N N N N N N'N lN\-\NVN\NA \ N N \'\ \ \ N A N 4 &4 i i e i 4 4 i 4 & i & & & 6 i i i i 8 i i i i i i i i i i is

<_ u, _,.

^^"7 *2 CIRCUMFERENTIAL CRACKS s e e nTon: a

. - wie crac aucus em . - m crac owxs =

ToTat TueEs  : s4n 2P93 INSPECTION PLAN TOTAL TUBES ASSIGNED : 66 TIE RODS (t) -: 7

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l j -

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  • X\ \ .\ \ \n\ \ N \ \ \
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/ \ \ \ \ \ \ \ \ \ \ \ \ \'\ \ \ 't. \ \ %

  • A A ]s]4\ \f\ \ \, \ \lNy\j\ \ \ \ \\ \ \, \,N, s s s s s s s s s s s.s s s s s s s s s s b \ Y N \ \ \ \ \ \ \ N \ \ \ \ \ \ \ \ \ \ \ \

. ,i f

,A \ \,N JN? \ \ \ \\ \ A N N \ \ \ \ \ N \ 1 .\ NN s u s x x x x x x x x x s x x x x x x x x x x xs l*I ,

i b h \ h \ \ h 'h \ \ \ \ \ N \ \ \ \ b \ b \ \ \ \ k *

  • I

/\ NN \ \ % A.\ \ \ \ \ A \ \ \ \ \ N \ \ \ \ N N-N i

  • A N N NN N N N N \ \ \ \\ \\ \ \ \ \ \ \ \ N N \ M '*

' A N N "N N N N N N N % N N N N N N% N N \ N N N'N N N \

  • 4- /s \ \ N \ \ \ \ \ \ \ \ \ s \ \ \!N \ N \ A \ \ \ N\ i 1

cx xxx x xx x x x x x xxs s x xx x x x xS J \ \ \ \ \ \ \ \\ \ \ \ \ \ \ \ \ \ \ _\ \\ ~ "

l b\ \ \ \A \ V\ \ \ \ \ N'N N \ \ \ \ l '

~"

K $ N NN NN N NN N N N NN N NN N* ' t *t

! L X N N N N N N N N N N N N N N N N:\ N ,,

l \ \ \ \ \ \ \ \ \ N N \ \ \ \ \ \ \ N ,

A\\ NN\\NN' \\\\NN\\\\ '

4 4 i &46&44 446 & 44 ' A & 6 i & 8 i i 88888 I i 8 i i II 4" em)

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4 OVERALL CONCLUSIONS o

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CONCLUSIONS FORMAL EDDY CURRENT ANALYSIS GUIDELINES ARE CONSERVATIVE AND CURRENT WITH INDUSTRY LEADERS

  • 100% REPAIR OF ALL CIRCUMFERENTIAL CRACK INDICATIONS NO SECONDARY SG ACTIVITY STATISTICAL PROJECTIONS, WITH CONSERVATISMS APPLIED, SUPPORT MIDCYCLE -

(SUMMER 1993) TIMEFRAME FOR SHUTDOWN ,

EARLY SHUTDOWN SCHEDULED BEGINNING APRIL 30,1993 t

i i

- - - . - . - - . . . _ - . - . --_ -. . -. _ . - . .-

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