ML20079B452

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Submits Info Re SG Weld Indication Evaluation
ML20079B452
Person / Time
Site: Prairie Island  
Issue date: 12/30/1994
From: Richard Anderson
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9501060112
Download: ML20079B452 (17)


Text

{{#Wiki_filter:p q l Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 December 30, 1994 10 CFR Part 50 Section 50.55a U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PIANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Steam Generator Weld Indication *. vtation During the Unit I refueling outage in Spring 1994, ultrasonic examinations of the steam generators were performed in accordance with ASME Boiler and Pressure Vessel Code Section XI. Examinations were done to satisfy the third period requirements of the second ten-year interval and the first period requirements of the third ten-year interval. The second ten-year interval plan for Prairie Island was written to conform to the 1980 edition of ASME Section XI, with addenda through the winter of 1981. The third ten-year interval plan for Prairie Island was written to conform to the 1989 editt of ASME Section XI. During the examinations, an indication was identified in the upper shell to dome weld region of #11 Steam Generator (see attached cover sheets to c:: amination reports #94-0095 and 94-0096) and indications were identified in the tubesheet to channel head weld region for #12 steam generator (see attached cover sheets to examination reports #94-0218, 94-0219, and 94-0220). These indications exceed the allowable flaw size when evaluated against the standards provided in ASME Section XI, IWB-3500. Accordingly, we performed an analytical evaluation of each of these flaws per ASME Section XI, IWB-3610. ?" h flaws were found accepteble per these analyses. Attached for your review are the results of these evaluations. The procedure used for these evaluations are available for review. The evaluations were performed prior to the unit startup following the refueling but we just recently became aware of the Code requirement fcr approval by the regulatory authority having jurisdiction at the site (in our case, the Nuclear Regulatory Commission). We regret the untimely submittal of these evaluations. Additionally, we are currently reviewing our previous flaw evaluations to determine if there were others which would have required Nuclear Regulatory 9501060112 941230 PDR ADOCK 05000282 00 /gI P PDR

1 i i USNRC NORTHERN STATES POWER COMPANY December 30,.1994 Page 2 l l l Commission approval. Accordingly, we will complete this review by January 31, 1995 and submit any required evaluations for your approval at that time. i i Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any l questions related to this letter. l 1 N &&ke$?!S-fl C esg Roger 0 Anderson Director l Licensing and Management Issues j c: Regional Administrator - Region III, NRC l Senior Resident Inspector, NRC NRR Project Manager, NRC l J E Silberg j i Attachments: j i

1. Ultrasonic Examination Report #94-0095 (cover shset)
2. NSP Flaw Evaluation: 1994 PI Unit 1 ISI Program / ISI 3rd 10-yr Report 94-0095 Flaw Acceptability per WCAP 13032
3. Ultrasonic Examination Report #94-0096 (cover sheet) i
4. Westinghouse ASME Section XI Flaw Evaluation, Prairie Island Unit 1 j

Steam Generator 12[11], Upper Shell to Dome Indication (three pages)

5. Ultrasonic Examination Report #94-0218 (cover sheet)
6. Ultrasonic Examination Report #94-0219 (cover sheet) l
7. Ultrasonic Examination Report #94-0220 (cover sheet) 1
8. Westinghouse ASME Section XI Flaw Evaluation, Prairie Island Unit 1 j

Steam Generator 12, Tubesheet - Channel Head Indications (four pages) l i i I i i I l r i l r u m3'ML.Dm: i J

4* No'rthern States Power Company Prairie Island Unit 1 Reportl 94-0095 Operations & Maintenance Supt 60* ULTRASONIC EXAMINATION source Doc-c 1. 20 Materials & Special Processes REPORT (3rd 10yr) S/N 1075 System ISO Item Item Description STEAM GENERATOR #11 ISI-43A W-H TOP HEAD - SHELL Material Size / Length Thick /Dia Temp Surface Condition SA-533GAC2 / SA-533GAC2 175"a 3.620 90* F BLENDED Procedure W R Number ISI Contractor Exam Date ISI-UT-3 Rev 5 Field Change N/A 9402190 LMT 05/14/94 Calibration Beam Angle Temp Gauge S/N Exam Start 0 1320 hours Report Nmbr WLT-007 60* (Nominal) NSP-035 Exam End 0 1445 hours Evaluation Level Reporting Level Cal Block 26 Ref Sensitivity 58 dB 20% DAC 20 % DAC Ref Std IMr-107 Scan Sensitivity 76 dB RESULTS NAD = No Apparent Discontinuities; L = Linear; S = Spot; M = Multiple GEO = Geometry Visual = Non-Section XI Visual Examination Scan Res-Indication Sweep Metal Surf Circ Axial Indication Amp Nmbr ults Type Loc'n Path Dist Location Location Length %DAC 1 IND L 4.0 3.39 2.93 13'7" 2.3 7" 40% 2 NAD 3 NAD 4 NAD I 1 LIMITATIONS: 2"x2" WELDED PADS @ 6",176",29',40'4" ALL DOWNSTREAM. REMARKS: E.J ' VLIC,LEVELI N/ A / e AM *** # f# V##"J88 ^" W b J &aegpl M /c,I! & L enY LEs g*g {e r-Wl (CW 'to Ptnhops subscAnons wrkt r=owJD e 410XosK 1 m %$ UdW & g.24g SKETCH PERSONNEL Examiner: A LTI@y Level [ Examiner: M uncQ4 n ( )

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Surface sa*; skce 3 0.M I All Embedded Flaws (on This Side of i kl ] 0.03 {p,' Demarkation Line) t 0.02 i are Acceptable per Criteria of IWB 3600 0.01 as Long as 2a/t 2 0.25 O 0 0.05 0.10 0.15 0.20 0.25 Distance from Surface (5/t) i 2 7.;;( k[':p,Y' j \\ ..f. j FIGURE 6-3 EMBEDDED FLAH EVALUATION CHART FOR CIRCUHFERENTIAL INDICATIONS f. IN THE UPPER SHELL TO DOME HELD REGION, PRAIRIE ISLAND UNITS 1 AND 2 (Note that this chart is a direct implementation of the rules of Section XI, IHB 3600.) 5384s/121291:10 6-8 fq g

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e* \\ Northern States Power Company Prairie Island Unit 1 Report # 94-0096 Operations & Maintenance Supt 45* ULTRASONIC EXAMINATION source Doc-c 1. 20 iD Materials & Special Processes REPORT ( d 10yr) S/N 1075 System ISO Item Item Description STEAM GENERATOR #11 ISI-43A W-H TOP HEAD - SHELL Material Size / Length Thick /Dia Temp Surface Condition SA-533GAC2 / SA-533GAC2 175"e 3.620 90* F BLENDED Procedure W R Number ISI Contractor Exam Date ISI-UT-3 Rev 5 Field Change N/A 9402190 LMT 05/14/94 Calibration Beam Angle Temp Gauge S/N Exam Start @ 0985 hours Report Nmbr WLT-006 45' (Nominal) NSP-035 Exam End @ 1147 hours Evaluation Level Reporting Level Cal Block 26 Ref Sensitivity 42 dB 20% DAC 20 % DAC Ref Std LMT-107 Scan Sensitivity 60 dB RESULTS NAD = No Apparent Discontinuities; L = Linear; S = Spot; M = Multiple GEO = Geometry Visual = Non-Section XI Visual Examination Scan Res-Indication Sweep Metal Surf Cire Axial Indication l Amp Nmbr ults Type Loc'n Path Dist Location Location Length %DAC 1 NAD 2 IND LINEAR 6.0 3.733 2.63 14'10" 2.85 2" 50% , 3 NAD 4 NAD N LIMITA110NS: 2"x2" WELDED PADS @ 6",17 6",29',47 4" ALL DOWNSTREAM --Tc'/."42* '.J +-M P 'i-40 5 _M d-ZFWf;A baM A Addi ~ REMARKS: E3 .1C LEVELI Sc* * **Ib * '** .f. L - L. AL - j, jg t fttysous oAlbicA toNC kt r reoWO te (To/ b Ac&Cn~? 4't G'Y' W SKETCH PERSONNEI., g /- ]A m g-g Examiner: s n 'L Level ^ Examiner: Oh n g _, i o LLI RS Level D 0* Contractor Review: // k// [/2f/[f g.g 1 Date I NSP f Review: / 'a,, [/(([ eview: / kc e Page 1 of [7fl A

es-aO-1994 15 29 4123746337 WEC P.63 i + ASMB Section XI Plaw Evaluation Pmide Island Unit 1 Steam Generator 12 Upper Shell to Dome Indication i During the June 1994 In Se:Vice inspection (ISI), ultrasonic examination revealed an indication in the upper shell to dome weld region of the steam generator at Pralrie Island Unit 1. The dimension and sizing Information were taken from Prsirie Isisnd Unit 145'P Ultiewidc Examination Report # 94- . 0096. This indication has been determined to be acceptable by analysis and is shown in Pigure 1, 1his evaluation was based on the ASMB Code Section XI criteria for acceptance of an indication by l fracture mecharJes analysis given in paragraph IWB-3600. The material information used to generate i these charts is specific to the Prairic Island steam generators. The RTmn. is 10'P for this region. 1he Aacture toughness of the matedals in this region was determined to be on the upper shelf due to the high minknum temperature for the normal and upset transients in this region, the lowest of which Is 254*P, the inservice hydrostatic test temperature applicable for 20 BPPY. The upper abelf for i fracture toughness has been assumed to be 200 kal/in,1his is based on the reference toughness curves found in Pisure A 4200-1 of appendix A of ASMB Code Section XI. i This region has been evaluated for similar flaws in the past. Ultrasonic examination revealed 3 indications in this region in 1991 la the sane steam generator. The analyses for the flaws found in the l 1991 inspection are documented in Reference 1. Figure 2 is the chart fmm reference 1 which shows the plotted indications found in 1991. The last page shows the cover page of the Reference 1 WCAP report.

References:

1.) WCAP 13032 "Ilandbook on Plaw Evalaution - Pral:te Island Units 1 and 2 Steam e Generators Upper Shell to Dome Weld." S. Tendon, et al, July 1991. i f

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i SURFACE / EMBEDDED FLAW DEMARCATION UNE i 0*13 WiE:.1:.i:4:4austoose PLAwEE& ~-- --- -a

~: ' ILANI WITH I l

. Lam.. u=. commounAn0N * = ~ ~ t = ABOVE THIS LINE ARE 0.12 -- ",:? ~

    • i NOT ALLOW.ABLE

- Z ** _ c.-- Cd_. ..me i +4 '- ' ' ' _ _ O 11 g _7 s i

== =: =

= ~ q = ~ - - = c.10 m_ =

= 3---2

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iEE
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-- Z 2.-

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t 0 0.06 0.10 0.15 0.20 0.25 l I DISTANCE FROM SURFACE h i t l Figure 2. Results of Flaw Evaluation for the Upper Shell to Dome Region, Prairie Island Unit 1, Spring 1991 1 I I i l l l t

P.06 06-24-1994 15:32 41234,g WCAP 13032 i HANDBOOK ON FLAW EVALUATION PRAIRIE ISLAND UNITS 1 AND 2 STEAM GENERATORS UPPER SHELL TO DOME WELD REGION July 1991 S. Tandon D. E. Prager i J. C. Schmertz D. S. Drinon S. i e, Reviewed by: W. H. Bamford i Approved by: .b r 2-N6] D. C. Adamonis, Acting nager Structural Mechanics T nology This document contains information proprietary to Westinghouse Electric Corporation; it is submitted in confidence and is to be used solely for the purpose for which it is furnished ar.d returned upon request. This document and such information is not to be reproduced, transmitted, disclosed or used otherwise in whole or in part without authorization of Westinghouse Electric Corporation, Nuclear and Advanced Technology Division. WESTINGHOUSE ELECTRIC CORPORATION Energy Systems Division i P.O. Box 2728 Pittsburgh, Pennsylvania 15230-2728 e 1991 Hastinghouse Electric Corp. i 5384s/071891:10

t i." I Northern States Power Company -Prairie IslandtUnit 1 Reportl 94-0218 l i .Operatio9s & Maintenance Supt 45' ULTRASONIC EXAMINATION Materials & Special Processes source Doc =B 2. 40 REPORT (2nd 10yr) S/N 1062 System ISO Item Item Description STEAM GENERATOR #12 ISI-438 (ISI-43) W-A i Material TUBE SHLET / HEAD I Size / Length Thick /Dia Temp Surface Condition SA533GR-B / SA533GR-B 135" 5.160 7 5* F BLENDED Procedure j W R Number ISI Contractor Exam Date ISI-UT-3 Rev 5 Field Change N/A 9402190 LMT 06/07/94 Calibration Beam Angle Temp Gauge S/N Exam Start @ _0905 hours Report Nmbr OL-011 45' (Nominal) NSP-037 Exam End 0 _I137 hours Evaluation Level Reporting Level Cal Block 25A 20% DAC 20 % DAC Ref Std LMT-106 Ref Sensitivity _48 dB j Scan Sensitivity 60 dB RESULTS NAD = No Apparent Discontinuities; L = Linear; S = Spot; M = Multiple f GEO = Geometry Visual = Non-Section XI Visual Examination Scan Res-Indication Sweep Metal Surf Circ Axial Indication Amp [ Nmbr ults Type Loc'n Path Dist Location Location Length %DAC 1 L LINEAR 4.5 4.215 3.25 33' 6.5" 3.049" 12.5" 75% 2 NAD 3 NAD 4 NAD I t l P { m LIMITATIONS: 2*x2" PADS ON U.S. AND D.S. OF WELD TOE @ 5'2".14' 23", AND @ 32' 3" UPSTREAM SCANS ONLY @ ll' TO II' 6" DUE TO 6"x4" PAD. A r REMARKS: EXAMINER: E.J. PAVLIC, LEVEL I XN g 1 SKETCl! ( stAA/.5 PERSONNEL Examiner: f.Lo M Q-* ~ Leve1 R I Examiner: /p j% / r, X t Y~ f Level Hand Hoj, /( Contractor I ChannelHead A To Tubesheet Weld Review: _49 h / ~U 6/e/jf i Date Manway eview: 'MM_ /[O/ i' D _ ate ANII Review: I [/2/h Date i Page 1 of f

l i t l Northern States Power Company Prairie Island Unit 1 Reportl 94-0219 Operations & Maintenance Supt 0* ULTRASONIC EXAMINATION source Doc =D 2. 40 Materials & Special Processes REPORT (2nd 10yr) S/N 1062 System ISO Item Item Description STEAM GENERATOR #12 ISI-43B W-A TUBE SHEET / HEAD Material Size / Length Thick /Dia Temp Surface Condition SA533GR-B / SA533GR-B 135" 5.160 75* F BLENDED Procedure W R Number ISI Contractor Exam Date ISI-UT-3 Rev 5 Field Change N/A 9402190 LMT 06/06/94 Calibration Beam Angle Temp Gauge S/N Exam Start 0 1245 hours Report Nmbr QL-010 0* (Nominal) NSP-037 Exam End 0 1430 hours Evaluation Level Reporting Level Cal Block 25A Ref Sensitivity 37 dB 20% DAC 50 % DAC Ref Std LMT-106 Scan Sensitivity 49 dB RESULTS NAD = No Apparent Discontinuities; L = Linear; S = Spot; M = Multiple GEO = Geometry Visual = Non-Section XI Visual Examination Scan Res-Indication Sweep Metal Surf Cire Axial Indication Amp Nmbr ults Type Loc'a Path Dist Location Location Length %DAC L1 NAD f LIMITATIONS: 2"x2" PADS ON U.S. AND D.S. OF WELD TOE @ 5' 2",14',23' AND AT 32' 3". UPSTREAM SCANS ONLY @ ll' TO Il' 6" DUE TO 6"x4" PAD. Di REMARKS: EXAMINER: E.J. PAVLIC, LEVEL 1 W SKETCH r/ g PERSONNEL Examiner: n M Examiner: / Level ~ c-OY Channa! Head Contractor Hand * - h To Tubesheet Weld Review: 4 /v M f[ 8/[/g j he ,/ Date Me NSP Fw [p/ / Review: /7/f h w-u- aty ANII s Review: / b (Date /@ Page 1 of 1

. \\ . 4, l I ~ Northern States Power Company Prairic Island Unit 1 Reportl 94-0220 Opdrations & Maintenance Supt 60' ULTRASONIC EXAMINATION source Doc-s 2. 40 Materials & Special Processes REPORT (2nd 10yr) S/N 1062 System ISO Item Item Description STEAM GENERATOR #12 ISI-43B (ISI-43) W-A TUBE SHEET / HEAD Material Size / Length Thick /Dia Temp Surface Condition SA533GR-B / SA533GR-B 135" 5.160 75' F BLENDED Procedure W R Number ISI Contractor Exam Date ISI-UT-3 Rev 5 Field Change N/A 9402190 LMT 06/07/94 Calibration Beam Angle Temp Gauge S/N Exam Start 0 1300 hours Report Nmbr OL-012 60' (Nominal) NSP-037 Exam End 0 1507 hours Evaluation Level Reporting Level Cal Block 25A Ref Sensitivity 54 dB 20% DAC 20 % DAC Ref Std LMT-106 Scan Sensitivity 66 dB RESULTS NAD = No Apparent Discontinuities; L = Linear; S = Spot; M = Multiple GEO = Geometry Visual = Non-Section XI Visual Examination Scan Res-Indication Sweep Metal Surf Circ Axial Indication Amp Nmbr ults Type Loc'n Path Dist Location Location Length %DAC 1 L LINEAR 4.7 6.302 5.00 33' 5" 6.3" 12.5" 80% 2 NAD 3 NAD 4 NAD LIMITATIONS: 2"x2" PADS ON U.S. AND D.S. OF WELD TOE @ 5' 2".14',23', AND AT 32' 3", UPSTREAM SCANS ONLY @ 11' TO 11' 6" DUE TO 6" x 4" PAD. REMARKS: EXA. MINER: E.J.PAVLir)4 LEVELI SKETCH gAA;E PERSONNEL g .-g Examiner: M X 6> REDO Level Examiner: [ 'Uff[dh / E ROY ~ Level -qyfa"a"::L., "%"$7" um 1/ wry he / 3 ,7 Date he NSP / F Review: _ //4h. _//_d' 'r-Date 8 O/k view: / 3 ~ Date j Page 1 of 1

1 e ~. e 9 j ASME Section XI Flaw Evaluation Prairie Island Unit 1 Steam Generator 12 Tubesheet - Channel Head Indications A fracture mechanics evaluation has been performed on the indication found during ultrasonic examinations of steam generator 12 at Prairie Island Unit 1 in June 1994. This evaluation was based on the ASME Code Section XI criteria for acceptance of an indication by fracture mechanics analysis given in paragraph IWB-3600. J Infonnation detailing the weld dimensions was provided in three Prairie Island Ultrasonic Examination Repons; Report #'s 94 - 218,94 - 219 and 94 - 220. These repons were provided in Reference 1. The indication was found in the tubesheet to channel head weld W-A (see Reference 1). The result of this evaluation is a flaw evaluation chan, shown in Figure 1, which was developed to pennit on-site evaluation of flaws found in the region in question during in-service inspections. The chart showstthe largest acceptable flaw sizes for a range of aspect ratios as prescribed by the criteria of section XI. The chan has been constructed for a circumferential embedded flaw since this is the type of flaw which was discovered in the June inspection. The chan is based on conservative material propenics with the RTum= 40 F ( RT yr for Prairie Island Unit I is 30*F). Nt The fracture toughness of the materials in this region was determined to be on the upper shelf. This is due to the high minimum temperature for the normal and upset transients in this region, the lowest of which is 254'F, the inservice hydrostatic test temperature applicable for 20 EFPY. The upper shelf for fracture toughness has been assumed to be 200 ksi/in. This is based on the reference toughness curves found in Figure A-4200-1 of appendix A of ASME Code Section XI. Crack growth analyses used in the generation of the attached flaw chan also applied the approach outlined in ASME Code Section XI and used the reference crack growth curves shown in Appendix A, Figure A 4300-1. The crack growth analysis was performed using all design basis transient cycles applicable in the tubesheet - channel head region. Results presented in the chan represent the 10,20 and 30 year final crack sizes for these aspect mtios. The results are the same for 10,20 and 30 years, l 1

,~ since the fatigue crack grow'h is small in this region. In this region, the flaw chart is blank, meaning that a flaw which meets the code criteria to be classified as embedded is acceptable by the analytical criteria of Section XI IWB-3600 To use the chart, three parameters are needed: a/t : flaw depth / wall thickness a/# : flaw depth / flaw length 6/t : flaw surface proximity / wall thickness where S = S+a S = distance fmm the flaw to the nearest surface The parameters used to detennine the point plotted on the chan am listed below; a = 0.186" t = 5.589" f = 12.5" r S =t2.98" S = 3.166" S/t = 0.566 (chart limit =0.25) a/t = 0.0333 It is easily seen from the chart that the indication in the tubesheet to channel head region found in Unit 1 is acceptable for operation by analysis.

References:

l. Letter from R. Pearson of Northern States Power to W. H. Bamford of Westinghouse Electric Corporation,

Subject:

Ultrasonic Exam Indications in 12 Steam Generator Tubesheet/ Channel Weld. I

4 s 9 e t Surface / Embedded Raw Demarketion i Une iM!!5fikIE U1!f! i_ d . Embedded FM i FLAWB WITH alt J:Hph win.- Configuration nii $.' It- --k p t 2: -i J: ABOVE TH.is UNE ARE ~ F-L 4_a ":tf xt Ei./i NOT ALLOWABLE NEi @ *"

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a~

f, - 0.08 r

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p n "I

Efl. L !! . 4 .C E Considered 6 - 0.06 TJ 55urface i L[ r f Ris l i ( ) 'g E Flawe E x V - b .-.+. E9ti

f:

' t 4 +- = 0.0s p + _4 it 7.,r;

f:

(U I

naml

~ + = fij j \\ 0.04

i

^ ~ ALL EMBEDDED FLAWS E. i " (ON THIS SIDE OF 0.03 10 _51 17 DFMARKATION UNE) %d[d 5[ J + ~h~ + q iL_11 e-ARE ACCEPTABLE PER . pg: :y 2 CRITERIA OF IWB 3000 0.02 4j+ m((. f$j A5 LONG AS 2a/ts0.25 g; . {. t 6 d ] ;

-s'L g4 g

xi

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' q a !- 4 ~- pr 1 2 3 4a : w pmu in qd py z O O 0.02s 0.05 0.07s 0.1 0.125 0.1s 0.17s 0.2 0.22s 0.25 Distance from Surface (6/t) Figure 1. - Embedded Flaw Chart for the Tubesheet to Channel Head Weld Region Containing Indication Found in June 1994}}