ML20046C645
| ML20046C645 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/06/1993 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9308110290 | |
| Download: ML20046C645 (50) | |
Text
{{#Wiki_filter:* prc% / t UNITED STATES [.hf j NUCLEAR REGULATORY COMMISSION ggg j WASHINGTON, D.C. 20556-0001 g j August 6, 1993 Docket No. 50-368 LICENSEE: Entergy Operations, Inc. FACILITY: Arkansas Nuclear One, Unit 2 (ANO-2)
SUBJECT:
SUMMARY
OF MEETING ON JULY 15, 1993, CONCERNING EDDY CURRENT METHODOLOGIES USED AT ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2) On July 15, 1993, representatives of Entergy Operations, Inc., and ABB-Combustion Engineering (hereafter referred to as the licensee) briefed the NRC staff on eddy current methodologies used at ANO-2. Meeting attendees are listed in Enclosure 1. Handouts that were presented by the licensee during the meeting are in Enclosures 2 and 3. The NRC staff opened the meeting by stating that this meeting is the first of two meetings on the ANO-2 steam generators. The purpose of this meeting is to have a working-level technical meeting on eddy current methodologies used at ANO-2. The purpose of the next meeting (late August) is to have a management-level meeting to discuss how long ANO-2 should continue to operate before the next steam generator inspection. The staff asked if any of the information to be presented is considered proprietary. The licensee replied that there was no proprietary information in the handouts. The licensee presented a history from January 1987 to the present of expansion zone circumferential cracking and nondestructive examination techniques employed in Combustion Engineering steam generators. The plants mentioned included Millstone-2, Maine Yankee, St. Lucie 1, ANO-2, and San Onofre-2. Next, the licensees discussed their method for calculating average wall loss of a steam generator tube. They take the maximum depth of the crack and multiply that times the measured length of the crack (in degrees) and then divide by 360 degrees. The licensee stated this method is conservative in that the entire length of crack is assumed to be uniformly deep, but also non-conservative in that the motorized rotating pancake coil (MRPC) is transparent to cracks less than 40% through-wall. The licensee presented information indicating that the MRPC results can be used to predict average crack depth fairly well; however, the MRPC appears to underpredict crack length. Regarding crack depth, the staff noted that the data used to support the ability to predict crack depth may be biased to show a better than actual correlation if many of the data points represent cracks with arc lengths close to 360 degrees. The staff asked the licensee to state the current MRPC threshold for reliably detecting cracks in steam generator tubes. The licensee replied that the SO*AOS$koS8$8$6a EbEN I fy g P PDR.
depth threshold is about 50% through-wall and that the length threshold is 40 degrees arc length. The licensee also stated that the maximum calculated degradation allowed to maintain the safety margins required by Regulatory Guide 1.121, " Bases for Plugging Degraded PWR [ pressurized-water reactor] Steam Generator Tubes," is 79% average through-wall for ANO-2, and the expected number of tubes with circumferential cracks in both steam generators should ANO-2 run until its next refueling outage is 77 (total in both steam generators). The licensee presented a graph of the worst-case cracks (percent average through-wall) versus effective full-power years (EFPYs) for CE plants. The data showed that for all plants (including AN0-2) the size of the worst-case crack has generally decreased versus increasing EFPYs. The licensee presented graphs of the number of cracks versus the average crack depth for the last three inspections at ANO-2. These graphs resemble gamma distributions, with the number of cracks decreasing asymptotically for higher average crack depths. The graphs from the last two inspections show that the gamma distributions are shifting to the left, indicating that the probability of exceeding the 79% average through-wall limit is decreasing with each inspection. The staff thanked the licensee for the presentation and stated that it helped t in understanding the licensee's eddy current methodologies. The staff stated that it needs additional information to be able to decide if the data supports plant operation for the remainder of the current cycle (the next refueling outage is scheduled for March 1994). The staff requested that the following information be provided in a formal submittal as soon as possible: 1. For the purposes of calculating MRPC average wall loss, assume that the crack depth is 50% (instead of 0%) where the MRPC shows no indication of a crack. Propagate these newly calculated average wall losses throughout the analysis. How does this affect the " probability of a crack exceeding a given average depth" curve for the period from the spring '93 inspection until the next scheduled refueling outage (2P93 - 2R10)7 2. The staff would like to see the analysis supporting 79% average through-wall as the maximum calculated degradation allowed to maintain the safety margins required by Regulatory Guide 1.121. 3. The staff would like to see the analysis supporting the total expected number of tubes (77) with circumferential cracks in both steam generators, should ANO-2 run until its next refueling outage. The staff would also like to see the high and low estimates associated with this number. i l
(D f( 4 ? August 6, 1993 In addition to this information, the staff would like a discussion of the scope of the steam generator inspection planned for 2R10. ORIGINAL SIGNED BY: Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. Handout (History)
- 3. Handout (Agenda) cc w/o Enclosures 2 and 3:
See next page DISTRIBUTION w/ enclosures: Docket File NRC & Local PDR: PD4-1 Reading TAlexion ABBeach w/o Enclosures 2 and 3: TMurley/FMiraglia ACRS (10) JPartlow JRoe EAdensam TChan PNoonan OGC EJordan NRC Participants LPlisco Treed ,0 BC/EMCBk) D(A):PD4-1 0FC LA:PD4-1 PM:PD4 A, EMCrZ EMCB tm NAME PNoorIhNfbTAfhxNNk kC Mhkhy G. Johns $ JStrosnNer HRood%b 3/9f93 f f g f93 ef5/93 g/r/93 V DATE 7 /2 7/93 T b/93 2 f i COPY YESh[0) [YE5/NO YES/NO YES/NO [ES)N0 YES/NO v 0FFICIAL RECORD COPY Document Name: ARJuly15.mts l I
In addition to this information, the staff would like a discussion of the scope of the steam generator inspection planned for 2R10. V)emw?hl 1, vJ uJ- /cv Thomas W. Alexion, Pro ect Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation ] 4
Enclosures:
- 1. List of meeting attendees
- 2. Handout (History)
- 3. Handout (Agenda) cc w/o Enclosures 2 and 3:
See next page
h I = e Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 -l cc: Mr. Donald C. Hintz, President Mr. John R. McGaha and Chief Executive Officer Vice President, Operations Support i Entergy Operations, Inc. Entergy Operations, Inc. l P. O. Box 31995 P. O. Box 31995 i Jackson, Mississippi 39286 Jackson, Mississippi 39286 j Mr. Robert B. McGehee Mr. James. J. Fisicaro Wise, Carter, Child & Caraway Director, Licensing P. O. Box 651 Entergy Operations, Inc. Jackson, Mississippi 39205 I Route 3 Box 137G l Russellville, Arkansas 72801 Mr. Charles B. Brinkman, Manager I Washington Nuclear Operations Mr. Nicholas S. Reynolds ABB Combustion Engineering Nuclear Power Winston & Strawn 12300 Twinbrook Parkway, Suite 330 - 1400 L Street, N.W. Rockville, Maryland 20852 Washington, D.C. 20005-3502 Admiral Kinnaird R. McKee, USN-(Ret)- j Mr. Robert B. Borsum 214 South Morris Street 1 Licensing Representative Oxford, Maryland' 21654 = > B&W Nuclear Technologies 1700 Rockville Pike', Suite 525 Mr. Michael B. Sellman I Rockville, Maryland 20852 General Manager, Plant Operations 1 Entergy Operations, Inc. i Senior Resident Inspector Route 3, Box 137G U.S. Nuclear Regulatory Commission Russellville, Arkansas 72801 1 Nuclear Plant Road p 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 ' i Arlington, Texas 76011 Honorable C. Doug Luningham County _ Judge of Pope County i Pope _ County Courthouse Russellville, Arkansas 72801 9 i Ms. Greta Dicus, Director Division of Radiation Control i and Emergency Management-Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72205-3867 l i i
i ~ July 15.1993 Workino Technical Meetino to Discuss Eddy Current Methodoloaies Used at ANO-2 List of Attendees Name Oraanization Phone 2 Tom Alexion NRC/NRR 301-504-1326 lan Barnes NRC/RIV 817-860-8176 Dale Powers NRC/RIV 817-860-8195 H. F. Conrad NRC/NRR 301-504-2703 Ken Karwoski NRC/NRR 301-504-2754 Dale James Entergy-ANO 501-967-2649 Darol Harrison Entergy-ANO 501-964-8909 Richard S. Maurer ABB-Combustion Engineering 203-285-3055 Emmett Murphy NRC/NRR 301-504-2710 Jack Strosnider NRC/NRR/EMCB 301-504-2795 Lynn Connor Southern Technical Services 301-652-2500 George Johnson NRC/NRR/DE/EMCB 301-504-3303 Terence Chan NRC/NRR 301-504-1302 Donald Naujock NRC/NRR 301-504-2767 John Dosa Entergy-ANO 501-964-8621 l
( 'i .i HISTORY OF REPANSION BONE CIRCONFERENTIAL CRACKING IN CONBUSTION ENGINEERING STERN GENERATORS AND NDE TECHNIQUE 8 ENPLOYED January 1987 - Millstone Point - Unit Two -- 3 Forced Outage Circumferential Cracking diagnosed by MRPC in SG2 7 Line 25 Row 19 Examination Limited to 7 tubes ] Plant Returns to Power February 1987 i January 1988 - Millstone Point - Unit Two f Refuel Outage l Line 25 Row 19 Deplugged l Tested with MRPC I Tested with UT i Removed for Metallographic Analysis i All Bobbin Coil Data Screened for Expansion Zone Anomalies 23 Circumferential Cracks Detected Post Outage i 1 NU contracts Combustion Engineering to Fabricate Steam I Generator Tube Flawed Samples Pits Circumferential Cracks Wastage IGA Combination Geometry Changes Conductive Deposits 1
s l + Purpose is to Define Optimum NDE Techniques Determine Bobbin Coil Detection Capability MRPC Techniques Refined for Length Measurements MRPC 3 Coil Qualified for Differentiation of Flaw Types l Zetec - AW1 I Atomic Energy of Canada Limited - Cecco-1 Coil Dynacon Pull Thru Ultrasonic Probe Westinghouse Rotating Ultrasonic Probe j B&W Rotating Ultrasonic Probe NUCON Rotating Ultrasonic Probe Results MRPC selected for Detection NUCON selected for Diagnostics i October 1989 - Millstone Point - Unit Two Three Tubes Removed for Metallographic Analysis e Excellent Correlation for Ultrasonic Results i May 1990 - Maine Yankee e Small Leakage During Coastdown Hydrostatic Testing Identifies 3 Leaking Tubes Two Diagnosed by MRPC as Circumferential Cracks Ultrasonic Testing does not agree well with MRPC Tube Row 75 Line 34 Removed for Metallographic Analysis Cracking is PWSCC Poor UT Correlation - 16% Avg Measured vs 45% Avg Met
4 October 1991 - St. Lucie 1 98 Circumferential Cracks Detected MRPC only e April 1992 - Arkansas - Unit Two Forced Outage i Circumferential Cracking Diagnosed by MRPC e Ultrasonic Testing of Selected Tubes e Five Tubes Removed for Metallographic Analysis e Poor Correlation with UT Results i e Reasonable Correlation with MRPC April 1993 - St. Lucie 1 l 20 Tubes with Expansion Zone Indications Detected e Cecco-3 Coil Testing o May 1993 - Arkansas - Unit 2 e 50 Tubes with Expansion Zone Indications Detected High Speed - Low Noise RPC Testing June 1993 - Palo Verde - Unit 2 Two Tubes with Reported Circumferential Cracks Remove 2 l for Metallographic Analysis No Evidence of Laboratory Examinations Complete Circumferential Cracking i i July 1993 - SONGS - Unit 2 ) Two Tubes with Reported Circumferential Cracks 1 l
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i MRPC CALCULATED AVERAGE WALL LOSS I Maximum Depth by 400 KHz Phase Analysis using 3 Point Fit e Curve Maximum Length by 400 KHz Clip Plot or 400 KHZ Crack Map Plot I Length Converted to Degrees Based on ID Circumference of 2.054 inches. Decrees Y DeDth = Avg { 360 Non Conservative
- in that MRPC is transp$ rent to cracks less than 40% Thru-Wall Conservative:
in that entire length of crack assumed to be uniformly' deep. I i l i ) i 'e 1
i i PROPRIETARY e J I / ANO Steam Generator "A" Throughwall Crack Tube R64-L48 e Average Penetration 65.1% e-0* r 30' 330* L rn,a:4 K@lp")@4 p=-
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PROPRIETARY ANO Steam Generator "A" ThrouE wall Crack h m Tube R79-R83 Average Penetration 44.6% = 0 30 ) 330 gq ?2N D I f5 o yy,RL +D Wh%.k, u J ,. ff 9-> e 4)4' - L~ a 300 yy 60' .L Q %f a 4, .w a m 4' nw S Q I&,{: '$i: i di e.$ 6
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[ 270 90 ' ggF f ff a ... u. gp d 3 ^ L 9-Ath y h m,, 120 ^ h?~ $*h Y 240 h " g grip Y%s EL4 @ Y s e M e-eq - g 's ' c.. s 6 .'4' 8 - 150 210 180* IGSCC i $W: Ductile Figure 10-10. Degradation as a function of Circumferential Location for Tube R79L83. 10-19
MRPC DEPTH CORRELATION WITH METALLOGRAPHIC RESULTS ON REMOVED STEAM GENERATOR TUBES WITH CIRCUMFERENTIAL CRACKS ACTUAL MRPC DATE MRPC MRPC MAX MRPC ACTUAL CALCULATED ACTUAL PLANT REMOVED EW LINE VOLTS DJEE LENGTH LENGTH D!FF AVG % AVG % QLFE MILLSTONE 2 01/88 19 25 68.8 88 100 -12 254 62 73 11 % 10/89 22 52 13.2 83 91.3 - 8.3 195 280 - 85 45 47 2 96 23 145 2.7 63 64.4 - 1.4 104 210 -106 18.2 19.3 - 1.1 % 14 118 3.6 72 71.1 + 0.9 249 350 101 49.8 49 + 0.8% MAINE YANKEE 05/90 75 34 11.1 96 100 -4 126 360 234 33.6 45 -11.4 % ARKANSAS 04/92 13 147 80.3 89 100 -11 360 360 0 89 94 5% 55 63 39.8 88 100 -12 360 360 0 88 88 0% 36 130 7.1 80 100 -20 360 360 0 80 88 8% 09/92 79 83 1.0 87 71 +16 181 360 -179 43.7 44.6 0.9 % 64 48 6.3 87 100 -13 239 360 121 57.8 65.1 7.3 % 1 I L
Ana ysis o" S/G Tubes Removed O CD 8 80 e s< o o 60 50 8 a ,o / m O / $3o f'/ 2 20 g / j-# t i I I I I O 10 20 30 Met Lab 366 Degree Average - 80 90 100 40 9 60 70 r-u-,_ --w-u e-- r- --v -%-,--e--'= -,,-m-- --i-w v-r-r +- w w-r w '*-ww,e
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MAINE YANKEE PWSCC SAMPLES 1 SAMPLE VOLTS A LENGTH AVG % ACTUAL AVG DJJJ. .M-4 28.99 80 145 32.2 36 -3.8% M-11 '27.34 96 176 46.9 53 -6.1% M-13 20.81' 90 219 54.8 50 +4.8% M-14 32.45 88 234 57.2 58 -0.8% T-8 7.12 74 139 28.6 58 -29.4% T-12 24.79 75 345 71.9 77 -5.1% T-7 19.61 64 160 28.4 31 -2.6% T-10 10.07 81 331 74.5 75 -0.5% T-9 28.03 74 222 45.6 56 -10.4% T-13 30.23~ 74 196 40.3 39 +1.3%' T-14 2.12 89 66 16.3 16 +0.3% 1 T-11 7.99 91 308 77.9 ,72 +5.9% ,1 E i k ... _ a......;_..
s ~ Maine Yan <ee PWSCC Sam ales , so m a h 70 E g 60 8 w O So o a 0 s C 40 u A 30 N G B } \\ /,, 20 /, i- / in / 10 20 30 40 50 60 70 80 90 Met Lab 360 Degree Average ~ .w~. .m,.... ,.--,.m...,... 4,,,o.....m...o ...,.. ~., _., _.
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t g *. a lumaces&614bEWMA.64mhama24 z.t.e-tesret: an.iv i. to-syrs.so tre. e. e. w sw.t einre bads w A w a w W uw m i w s w A4.eash N ode = DkA2R058 Cale = tape 026A.ca101 SAT 12:58 MAR-23-91 SG B ROW 66 LIN 136 1 Loewsmark s 1t 400 PAHCX 9: 10 LOCAT 1: 400 PAHCK Neut-Last vert vert 1.44 w/d open 9 rot 257 Tube .L Refresh <ns h> 200* 30 10 i, ci _ s "II q h W h" M K_ 1 m 1 d Lt Chan r'! Newt.Legt ChanneI t ( RPC/ l5 CrackMau Vpp HwR Vmu Can IBO TSH- ^ g_(}$3 p TSH 0.05 Dats-Otr/ rite-Func 2 "2 -t Procese e 3 L Channele i System functione i ~ Print-FF I@N N ] r
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6 AGENDA WORKING LEVEL TECHNICAL MEETING ON EDDY CURRENT METHODOLOGIES UTILIZED AT ANO-2 JULY 15,1993 I. INTRODUCTION II. RG 1.121 METHODOLOGY - CALCULATION OF AVERAGE % THROUGHWALL j III. DECREASING WORST CASE AVERAGE % THROUGHWALL WITH SUCCESSIVE INSPECTION IV. MRPC DETECTION TIIRESHOLD/ ACCURACY V. CRACK GROWTII RATES VI. CONCLUSION 1 i ntergy -: ~ E Operations
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93RPC.XLS Chart 25 l d i i I i i t i i 6 1 i 2R9 - 2P93 i PROBABILITY OF A CRACK EXCEEDING A GIVEN l AVERAGE DEPTH l i 100 - i r 90 7 80 t 70 +i i 60 f l 50 i 40 1 30 20 10 0' 35 40 45 50 55 60 65 70 75 80 85 90. 95 100 i l AVERAGE DEPTH (% TW) 1 t I I t 'I -I t .4 ? Page 1 - .l i
l e 93RPC.XLS Chart 35 P t i 5 e i I I e 5 2P93 - 2R10 l PROBABILITY OF A CRACK EXCEEDING 1 t A GIVEN AVERAGE DEPTH 1 100 7 80 4 l 60 4' i t 40 a E j 20 4 t t 0 e o m o m E m e o E E E e e n v v m m e 8 N e e r=. AVERAGE DEPTH. %TW 5 I { k .I f Page 1 -}}