ML020300477

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Summary of 06/06/00 Meeting Between Consolidated Edison Company of New York, Inc & NRC Staff Concerning U-Bend Inspections
ML020300477
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 01/14/2002
From: Harold J
NRC/NRR/DLPM
To:
References
FOIA/PA-2001-0256, TAC MA8219
Download: ML020300477 (51)
v • d • e


Text

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REG(,

I UNITED STATES 0

NUCLEAR REGULATORY COMMIS WASHINGTON, D.C. 20555-0001 FACILITY:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 LICENSEE:

CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.

SUBJECT:

SUMMARY

OF JUNE 6, 2000, MEETING BETWEEN CONSOLIDATED EDISON COMPANY OF NEW YORK, INC AND NRC STAFF CONCERNING U-BEND INSPECTIONS (TAC NO. MA8219)

On June 6, 2000, a public meeting was held at the Westinghouse Offices, Waltz Mill Site, Pennsylvania, between Consolidated Edison (Con Ed), and the Nuclear Regulatory Commission (NRC) staff. The purpose of the meeting was to discuss matters related to the Indian Point Nuclear Generating Unit No. 2's (IP2) steam generators. Specifically, the probability of detection (POD) of flaws within the U-Bend region of the steam generators.

There were two presentations. The first of which focused on the eddy current inspection performance assessment. Discussions were in the areas of analyst training, the multiple eddy current inspection programs performed during the 2000 outage, analyst performance, alternate nondestructive examination methods, and structural integrity. The presentation discussing the analyst training provided a description of the differences between the 1997 and 2000 outage and what improvement occurred as a result of the change. The eddy current inspection program utilized multiple coil types. The base scope program employed cecco and bobbin in the sludge pile region and + point probe in the u-bend rows 2-4. The expansion program employed the use of + point from tube end through the sludge pile. The second presentation focused on the condition monitoring and operational assessment POD, and depth sizing of pressurized water stress corrosion cracking indications. Enclosure 1 is the list of attendees and Enclosure 2 are the handouts distributed during the meeting. Please direct any inquires concerning this meeting to me. I can be reached at (301) 415-1421 or JFH@NRC.GOV.

Jefferey F. Harold, Project Manager Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247

Enclosures:

As stated cc w/encls: See next page t,.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 LICENSEE:

CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.

SUBJECT:

SUMMARY

OF JUNE 6, 2000, MEETING BETWEEN CONSOLIDATED EDISON COMPANY OF NEW YORK, INC AND NRC STAFF CONCERNING U-BEND INSPECTIONS (TAC NO. MA8219)

On June 6, 2000, a public meeting was held at the Westinghouse Offices, Waltz Mill Site, Pennsylvania, between Consolidated Edison (Con Ed), and the Nuclear Regulatory Commission (NRC) staff. The purpose of the meeting was to discuss matters related to the Indian Point Nuclear Generating Unit No. 2's (IP2) steam generators. Specifically, the probability of detection (POD) of flaws within the U-Bend region of the steam generators.

There were two presentations. The first of which focused on the eddy current inspection performance assessment. Discussions were in the areas of analyst training, the multiple eddy current inspection programs performed during the 2000 outage, analyst performance, alternate nondestructive examination methods, and structural integrity. The presentation discussing the analyst training provided a description of the differences between the 1997 and 2000 outage and what improvement occurred as a result of the change. The eddy current inspection program utilized multiple coil types. The base scope program employed cecco and bobbin in the sludge pile region and + point probe in the u-bend rows 2-4. The expansion program employed the use of + point from tube end through the sludge pile. The second presentation focused on the condition monitoring and operational assessment POD, and depth sizing of pressurized water stress corrosion cracking indications. is the list of attendees and Enclosure 2 are the handouts distributed during the meeting. Please direct any inquires concerning this meeting to me. I can be reached at (301) 415-1421 or JFH@NRC.GOV.

Jefferey F. Harold, Project Manager Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247

Enclosures:

As stated cc w/encls: See next page DISTRIBUTION:

PUBLIC PDI-1 R/F JHarold PMilano OGC ACRS JZwolinski SBlack EAdensam MGamberoni SLittle JMcCann Accession Number:

ML003736166 OFC PM:PDI-1 LA:PDI-1 SC:PDI-1 NAME JHarold SLittle MGamberoni DATE I

I

_1_1_

OFFICIAL RECORD COPY EMurphy SCoffin CDodd WSchmidt FACILITY:

Indian Point Nuclear Generating Station Units 1/2 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Ave. Extension Albany, NY 12203-6399 Mr. John McCann Manager of Nuclear Safety and Licensing Consolidated Edison Company of New York, Inc.

Broadway and Bleakley Avenue Buchanan, NY 10511 Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 Mr. Brent L. Brandenburg Assistant General Counsel Consolidated Edison Company of New York, Inc.

4 Irving Place - 1822 New York, NY 10003 David Lochbaum Nuclear Safety Engineer Union of Concerned Scientists 1616 P Street, NW., Suite 310 Washington, DC 20036 Edward Smeloff Pace University School of Law The Energy Project 78 North Broadway White Plains, NY 10603 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Ms. Charlene D. Faison, Director Nuclear Licensing Power Authority of the State of New York 123 Main Street White Plains, NY 10601 Mr. Thomas Rose Secretary - NFSC Consolidated Edison Company of New York, Inc.

Broadway and Bleakley Avenue Buchanan, NY 10511 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. A. Alan Blind Vice President, Nuclear Power Consolidated Edison Company of New York, Inc.

Broadway and Bleakley Avenue Buchanan, NY 10511 Jim Riccio Public Citizen's Critical Mass Energy Project 215 Pennsylvania Ave., SE Washington, DC 20003 Michael Mariotte Nuclear Information & Resources Service 1424 16' Street, NW, Suite 404 Washington, DC 20036

ATTENDANCE LIST JUNE 6. 2000 MEETING CONCERNING U-BEND INSPECTIONS Organization J. McCann E. Murphy S. Coffin C. Dodd W. Schmidt J. P. Lareau D. C. Adamonis T. A. Petterle D. Malinowski S. M. Ira L. Campagna G. Witeman A. Sagar G. Elder Consolidated Edison NRC NRC NRC NRC Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Name

-->~PJ NRC Public Meeting With Con Edision" Steam Generator U-Bend Inspections Westinghouse Waltz Mill Site Madison, PA June 6, 2000 Introduction Purpose of Meeting U-Bend POD Presentation U-Bend POD Q&A Other Topics

Indian Point-2 U-Bend CMOA POD and Depth Sizing of PWSCC Indications NRC/ConEd/Westinghouse Meeting June 6, 2000 Westinghouse Waltz Mill Site Prepared By:

T. A. Pitterle Westinghouse Electric Company

Probability of Detection Detection Enhanced with 800 kHz High Frequency Probe

"* Reduced effects of deposits

"* Reduced ovality effects apparently due to smaller coil shoe

"* Permitted detection of indications in tubes found to have unacceptable signal to noise data with 400 klILz probe Indications found in R2C4, R2C85 and R2C74 Additional indications detectable on R2C87 Indications found in R2C71 previously restricted for mid-range probe Lower Bound +Point POD Distribution

"* Low POD selected to bound high frequency probe detection (not applicable to mid range coil detection)

"* Maximum and average depth PODs Recommended POD consistent with Indication Sizes Found in the Inspection

SG-CO-05-008 Figure A.3-5. Year 2000, SG 4, U-Bend Tube R2C4 - 400 kHz Mid-Range Figure A.3-6. Year 2000, SG 4, U-Bend Tube R2C4 - 400 kHz High Frequency A-17

SG-00-05-008 Figure A.1-5. Year 2000, SG 4, U-Bend Tube R2C4 - 400 kHz Mid-Range Figure A.1-6. Year 2000, SG 4, U-Bend Tube R2C4 - 800 kHz High Frequency A-5

SG-00-05-008 Figure A.1-13. Year 2000, SG 4, U-Bend Tube R2C74-400 kHz Mid-Range Figure A.1-14. Year 2000, SG 4, U-Bend Tube R2C74 - 800 kHz High Frequency A-9

1.00 0.90 0.80 0.70

° 0.60 o 0.50

$4 0.30 0.20 0.10 0.00 20%

30%

40%

50%

60%

70%

Average Depth - % TW 80%

90%

100%

5-18 SG-00-05-008 Figure 5-1. Comparisons of +Point Average Depth PODs

-9

+Point Avg. Depth - Symmetrical

__Denting

.+Point Avg. Depth - Axial Denting, P2 800 kHz 0

Detected Indication Average Depth 0%

10%

SG-00-05-008 Figure 5-2. Comparisons of + Point Max. Depth PODs 0%

10%

20%

30%

40%

50%

60%

070%

80%

90%

100%

Maximum Depth - %TW 5-19 1.00 0.90 0.80 0.70 0

-4 0.60 o 0.50 4.-4 o0

  • o 0.40 0.30 0.20 0.10 0.00

+Point Sizing of U-Bend Indications

+Point Sizing Methods for PWSCC at Dented TSP Intersections Applied

  • Refinements applied to distinguish noise from flaw signal, particularly for R2C5 Noise characterized away from flaw Flaw signal extends beyond noise in phase response 400 kHz Data Used for Sizing
  • Correlations of destructive exam ("truth") to NDE developed for 300-400 kHz data

- NDE sizing uncertainty standard deviation increased by 25% to reflect application of dented TSP data to U-bend indications

  • Higher frequencies yield larger depths and correlation to destructive data not available 11 indications in 2000 sized at 400 kHz out of 14 detected/sized at 800 kHz
  • Growth rates developed from 1997 and 2000 400 kHz data (9 indications)

Figure 1 Indiani Point-2 R2C5 Noise Level of About 0.9 Volts Away from Flow I I Y 245 1

44 "1~l~

41 A~rs{3SU',jri)

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11 1

rL MYE UM rLP PA44 9 -

oi K 0 HR OF MeXM? YEW I EH I x 5S4 TMZK OFF SET TRIG C-fr flKICA,_OIY SFIEEO 0.,11 1.1... ]LOUR 0

1A I-A Q:Tubcilt\\IPP\\2000\\NRCmtgsRAIs\\RCsponsCs to NRC RAIs 2 6 14 16.doc 77

Figure 2 Indian Point-2 R2C5 Combined Noise Plus Flaw Peak Voltage of 2.46 Volt Q:Tubcint\\IPP\\2000\\NRCmtgsRA]s\\RcsponsCs to NRC RAIs 2 6 14 16.doc 8

Figure 3 Indian Point-2 R2C5 Peak Flaw Voltage of 1.38 Volt 6W.05' 215.5 Q:Tubeint\\1PP\\2000\\N'RCmtgsPRAls\\Respoflses to NRC RAls 2 6 14 16.doo 9

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SCAN TRACK ON -TRIG ON W11-j A..RKCIRC..OFF SPEED 0G.11 Wn...

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0 0

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SG-00-05-008 Table 3-5. Indian Point-2 U-Bend Indication +Point Sizing Results for 800 and 400 kHz Data

+Point Sizing Results SG Tube Crack Max.

Max.

Avg. Length Burst Burst No.

Volts Depth Depth (inch)

Avg. Length

(%)

(%)

Depth (inch)

Leaking Indication 400 kHz - 1997 Data 4 R2C5 1

2.241 921 63.0 2.43 73.6 1.26 1

2.311 921 70.6 2.43 80.2 1.87 New Indications 400 kHz - 2000 Data 4 R2C69 1

2.71 74 55.2 0.91 58.3 0.79 2

1.03 74 44.5 0.11 44.5 0.11 3

0.94 54 38.2 0.23 42.0 0.20 4

R2C72 1

3.17 82 59.8 0.54 66.6 0.44 4 12C7101 )

1 2.43 96 64.0 0.57 69.0 0.48 1 R2C87 1

1.68 55 42.8 0.30 48.0 0.25 2

2.25 61 43.6 0.29 48.0 0.25 3

2.28 53 41.6 0.35 44.3 0.31 3

R2C85(2) 1 1.20 50 38.9 0.25 46.0 0.18 4 R2C4(2) 1 0.86 44 23.2 0.17 32.3 0.10 4 R2C74(2) 1 0.97 38 14.4 0.19 19.4 0.11 New Indications 800 kHz - 2000 Data 4 R2C69 1

4.12 89 64.6 0.97 68.5 0.86 2

1.03 68 48.8 0.27 48.8 0.27 3

0.92 84 61.1 0.23 61.1 0.23 4 R2C72 1

3.60 82 62.8 0.56 69.9 0.47 4 R2C4 1

0.89 50 33.0 0.12 33.0 0.12 4 R2C71 1

1.77 95 75.6 0.58 75.6 0.58 2

0.95 34 18.8 0.09 18.81 0.09 4 R2C74 1

1.42 53 39.4 0.16 39.41 0.16 1 R2C87 1

2.79 84 60.7 0.28 60.7 0.28 2

2.91 79 65.1 0.35 65.11 0.35 3

2.82 68 51.8 0.43 59.31 0.32 4

1.81 58 46.5 0.23 48.2 0.21 5

0.70 68 52.6 0.11 52.6 0.11 3 R2C85 1

1.41 68 44.5 0.28 47.9 0.25

1. Midrange probe was restricted and +Point inspection was not performed with midrange probe. Data at 400 kHz obtained by evaluating high frequency probe data at 400 kHz.
2. Bad data was obtained with midrange probe and U-bend region of flaw was not inspectable in region of flaw. Data at 400 kHz obtained by evaluating high frequency probe data at 400 kHz based on flaw detected at 800 kHz.

3-11

SG-00-05-008 Table 5-1. Indian Point-2 U-Bend Axial PWSCC Growth Rates (400 kHz Data)

+Point - 2000 inspection

+Point - 1997 Inspection Growth per EFPY Midrange Coil Midrange Coil 2000-1997 = 1.48 EFPY S

Tube Crack Max. Max.

Avg. Length Burst Burst Max. Max.

Avg. Length Burst Burst Max. Max.

Avg. Length Burst Burst G

No.

Volts Depth Depth Avg. Length Volts Depth Depth Avg. Length Volts Depth Depth Avg. Length G

hD(_Depth Its Depth V

Depth Depth ___

R2C5 1

100 90 2.24 92 63.0 2.43 73.6 1.22 8.00 11.1 11.1 Note 1 2.31 92 70.6 2.43 80.2 1.87 4 R2C69 1 2.71 74 55.2 0.91 58.3 0.791 1.33 84 57,0 0.9 62.8 0.7 0.93

-6.76

-1.22 0.01

-3,04 0.061 1.03 74 44.5 0.11 44.5 0.11 0.54 50 31.5 0.25 39.0 0.16 0.33 16.22 8.78

-0.09 3.72

-0.03 0.94 54 38.2 0.23 42.0 0.20 0.61 50 33.8 0.16 37.7 0.13 0.22 2.70 2,97 0.05 2.91 0.05 4 R2C72 11 3.17 82 59.8 0.54 66.6 0.44 1.3 79 61.8 0.39 66.4 0.35 1.26 2.03

-1.35 0.10 0.14 0.06 4 R2C71 1 2.43 96 64.0 0.57 69.0 0.48 1.87 87 57.5 0.68 63.1 0.57 0.38 6.08 4.39

-0.07 3.99

-0.06 1I R2C87 1 1.68 55 42.8 0.30 48.0 0.25 1.05 63 40.8 0.15 40.8 0.15 0.43

-5.41 1.35 0.10 4.86 0,07 1

2.25 61 43.6 0.29 48.0 0.25 0.76 53 36.4 0.19 40.8 0.16 1.01 5.41 4.86 0.07 4.86 0.06 1

2.28 53 41.6 0.35 44.3 0.31 0.95 63 36.5 0.27 45.2 0.19 0.90

-6.76 3.45 0.05

-0.61 0.08

_Av_-.

1 0.68 2.39 3.80 0.03 3.09 0.04 Max.

1.26 16.22 11.1 0.10 11.1 0.08 Note 1. R2C5 not sizeable in 2000 by NDE after crack opening resulting in leakage. Maximum depth in 2000 is assumed to be throughwall. For ligament tearing, which is the expected cause for opening the R2C5 crack, the average depth to tear the ligament of a 2.2 to 2.4 inch flaw would be about 90%. The 90% depth value is applied with the smaller burst effective depth estimate for R2C5 in 1997 to assign a conservative growth value to R2C5.

5-17

SG-00-05-008 6-11

SG-00-05-008 Figure 3-5. Indian Point-2: Comparison of SG 4 R2C71 400 and 800 kHz Depth Profiles SG4, U-Bend Tube R2C71, Crack 1 NDE Depth vs. Axial Length 100.00 90.00 80.00 70.00 60.00 00.00 40.00 30.00 20.00 10.00 0.00.

7.00 7.10 7.20 7.30 7.40 7.50 7.60 7.70 7.80 Axial Distance (in.)

3-17 0

C

,)

Analyst/year s0400/2000

-U--

Analyst/year s0400/2000 - Burst

-A - Analyst/year s0800/2000 Analyst/year s0800/2000 - Burst

SG-00-05-008 Figure 8-3 SG 4, U-Bend Tube R2C71, Crack Depth Profiles Comparison of Pre and Post In Situ NDE Depth vs. Axial Length 100.00 90.00 80.00 70.00 60.00 50.00 40.00 30.00 20.00 10.00 0.00 7.00 7.20 7.40 7.60 Axial Distance (in.)

...A- --800khz-Pre -

800kHz-Post -----400kHz-Pre 8-7 0

a i-7.80

SG-00-05-008 Figure 3-4. Indian Point-2; Comparison of SG 4 R2C69 400 and 800 kHz Depth Profiles SG4, U-Bend Tube R2C69, Crack 1 NDE Depth vs. Axial Length II SI I,

II l

'I II I

I II I

S I,

S I

Ii S

5 8.40 Axial Distance (in.)

8.60 8.80 30400 s0800 2000 2000 Lengo 0.91 0.97 Max. Volts 2.71 4.12 Max. Depth (%) 74.0 89.0 Avg, Depth (%) 55.2 64.6 Burst Effective s0400 s08OO 2000 2000 Length 0.79 0.86 Max. Volts 2.71 4.12 Max. Depth (%) 74.0 89.0 Avg. Depth (% 5 8.3 68.5 Pb (ksi) 8.186 6.590 Sf - 100.00 (ksi)

Analyst/year s0400/2000 Analyst/year s0800/2000 E----Analyst/year s0400/2000 - Burst

-&-Analyst/year s0800/2000- Burst 3-16 100.00 90.00 80.00 70.00 60.00 50.00 40.00 30.00 20.00 10.00 Os 0.00 7,80 8.00 8.20 Lill.

l!

M

SG-00-05-008 Figure 8-2 SG 4, U-Bend Tube, R2C69 Crack Depth Profiles Comparison of Pre and Post In Situ NDE Depth vs. Axial Length *'O0*

6.80 7.00 7.20 7.40 7.60 7.80 8.00 8,20 8.40 8.60 8.80 Axial D1stance (In,)

9,00 I" -.- 8OOkHz-Pre -

G--.80kHz.Post 400kHz-Pre I 8-6 100.00 90.00 80,00 70.00 60.00 50,00 40.00 30.00 20.00 10.00 0

0.00 -ýi 6.60

SG-00-05-008 1

0.9 0.8

  • 0.7 0.6 0.5 S0.4 0.3 o0.2 0.1 0

10 12 14 16 18 20 22 Average Depth -%

24 26 28 30 Figure5-11 Indi an Point-2 IJBexd PIXSI Ratio of Maxim= to Burst Erfective Average Depth 0

10 30 40 50 Burst Effective Average Depth- %

5-24 Figure 5-10.

Indian Point-2 New Indication Average Depth Distribution 60 70 s0

Benchmark Analyses Benchmark Analyses for Integral Check of Sizing and Analysis Methods

" Projections of 1997 data to compare with R2C5 leakage and in situ results in 2000

- Test of Monte Carlo techniques applying profiles, growth distributions, burst correlation and ligament tearing correlation

- Projections at 95/95 should provide lower bound to in situ results

- Operational assessment benchmark analyses must be performed at high probability to reflect growth rate distribution (nominal growth would be expected to underestimate large indications)

"* Comparisons of burst and ligament tearing pressures using 2000 profiles with in situ test results

- Analysis results at 95/50 should provide lower bound

- Best estimate analyses are test of profiles and burst/tear profiles Benchmark Results

  • Best estimate R2C5 profile yields better agreement with leakage than alternate profile e 400 kHz profiles are preferred data as 800 kHz profiles introduce unnecessary conservatism
  • Analyses correctly predict indications with more limiting in situ test results

- Burst pressures and ligament tearing predicted at pressures below test results at required confidence levels for R2C69, R2C71 and R2C69

- Only low level leakage of R2C74 initiating at 4486 psi not bounded by analyses

SG-00-05-008 6-7 Table 6-1. Summary of Predictions for R2C5 Leakage Event Based on 1997 Data Burst SLB Ligament Estimated

+Point Profile Pressure Leakage Tearing &

Event (psi)

(gpm)

Leakage at Leakage APNo(l) at APNo (gpm)

(gpm) 95/95 50/50 95/95 50/50 95/95 50/50 Reference Growth Rates Best estimate 1349 3100 166 3.89 12 0.0 140-160 Alternate estimate 1724 4070 118 0.0 12 0.0 Growth Rates x 1.25 1

1 Best Estimate 1295 195 6.31 Alternate estimate 1535 145

0.0 Notes

1. Ligament tearing computed at APNo = 1569 psi for EOC-14. Leak rates adjusted from SLB leak rate correlation assuming a SLB to normal operating leak rate ratio of 5.0.

SG-00-05-008 Table 6-2. Indian Point-2 U-Bend Indications; Comparison of Burst Pressures and Leakage for Projected and Actual EOC-14 Indications Analyses & In Situ Results at Operating Temperatures -Requirements: 3APNO = 4617 psi, SLB Leak Rate = 1 zum Burst Pressure SLB Leak Rate In Situ Test Indication Calculation Predictions - psi bpm Results Parameters Burst SLB 1997 NDE 2000 NDE 1997 NDE 2000 NDE Pressure Leak Projection Data Projection Data psi Rate SG Tube Crack NDE Year gpm No. Profile Profile 95/95 50/50 95/50 50/50 95/95 50/50 95/50 50150 4 R2C69 1 400 kHz 1997 3313 5600 4851 6970 2.818 0.0 0.0 0.0

>4834 0.00 2

6949 9750 8447 10000 0.0 0.0 0.0 0.0 3

1 7350 10000 7657 10000 0.0 0.0 0.0 0.o 1800 kHz 2000 3749 5770 1.51 0.0 2

6589 9090 '

0.0 0.0 3

6099 8800 0.0 0.0 4 R2C71 1 400 kHz 1997 3703 5860 4486 6430 1.047 0.0 0.04 0.0

>4206 0.024 1800 kHz 2000 3823 5570 0,60 0.0 4 R2C72 1 400 kHz 1997 4283 6400 4888 6800 0.316 0.0 0.0 0.0

>5140 0.00 1800 kHz 2000 4432 6420 0.10 0.0 1 R2C87 1 400 kHz 1997 6955 9580 6888 9380 0.0 0.0 0.0 0.0

>5140 0.00 2

6888 9570 6968 9330 0.0 0.0 0.0 0.0 3

6391 8910 7048 9420 0.0 0.0 0.0 0.0 1800 kHz 2000 5680 8240 0.0 0.0 0,0 0,0 2

5130 7490 0.0 0.0 0.0 0.0 5778 7900 0.0 0.0 0.0 0.0 6-8

SG-00-05-008 Table 6-3. Indian Point-2 U-Bend Indications: Comparison of Condition Monitoring Burst and Li ament Tearini Pr*.irrp. iutlj Tin

  • i+-v-i T*+

v11+,

Burst Pressure Ligament Tearing In Situ Test Results Indication NDE Profile Predictions Pressure Burst Initial Frequency 2si p i Pressure Leakage SG Tube Crack 95/50 Best 95/50 Best psi Pressure No, Estimate Estimate psi R2C69 1

400 kHz 4851 6503 2877 5796

>4834 4834 1

800 kHz 3749 5235 0.0 4580

>2 gpm 4

R2C71 1

400 kHz 4486 5799 0.0 5480

>4206 Steady 1

800 kHz 3823 4828 0.0 4096 Increase 4

R2C72 1

400 kHz 4888 6219 2570 6022

>5140

>5140 1

800 kHz 4432 5728 0.0 5466 1

R2C87 1

400 kHz 6888 8838 6498 8835

>5140

>5140 2

6968 8837 6553 8840 1

800 kHz 5680 7828 0.0 7665 2

5130 6834 2658 6688" '

4 R2C4 1

400 kIHz 9017 11314 9078 10664

>5140

>5140 800 ki-z 8879 11059 9041 10660 4

R2C74 1

400 kHz 9850 12150 9470 11035

>5140 4486 800 kHz 8035 10202 8487 10202 3 R2C85 1

400 kHz 7456 9578 7580 9422

>5140

>5140 800 kHz 6827 8846 6945 8862 6-9

Indian Point 2 2R14 Steam Generator Inspection June 6, 2000 Con Edison Westinghouse Qr~h

Inspection Performance Assessment Analyst training

"* Multiple eddy current inspection programs

"* Analyst statistics and performance

  • Alternate NDE method Structural integrity Conclusions

Analyst Training

"* Primary, secondary and resolution analysts QDAs

"* Site specific written examination ANSER software orientation Indian Point 2 specific degradation mechanisms

"* Site specific practical examination Included 1997 Indian Point 2 data

  • Crevice, sludge pile, low row U-bend and support plates All Cecco tests graded to meet 80% POD @ 90% CL

"* U-bend training supplements First upon initial investigation

- Second for "tertiary review" of midrange +Point data and used for analysis of high frequency +Point

"* +Point training for expanded sludge pile program

1997 Versus 2000 Outage iiu

§ UUIaI.

ouD utlage Whly This 1 Ae Im provement Vonerai Ueneral Rev. 5 defines additional Rev.4 of the EPRI Guidelines in force for Intent of Rev.5 of the EPRI Guidelines met rigors for analyst training and the outage. NEI 97-06 not in force, for the outage. NEI 97-06 Intent met as testing. NEI 97-06 provides well.

industry commitment to how steam generators are to be exam ined.

Analyst Training Analyst Training 1997 data included first Based on sample and 1995 data analysis Based on sample and 1997 date analysis reported axial indications in results.

results.

crevice, sludge pile and low row U-bends. These were not part of the experience base for the 1997 outage.

Analyst Testing Analyst Testing Majority Of the Cocco calls Not done on a statistical basis for Ceoco Cecco test was based on statistical used had also been probe data - point basis only. Not done requirements perRev. 5 of the EPRI confirmed by RPC on Indian Point 2 data confirmed by RPC.

Guidelines. Reduced data set for bobbin (expansion, crevice, sludge and RPC per EPRI Guidelines, Data pile and support plate). All based on 1997 inspection and Included all data used in the testing and Identified damage mechanisms, grading was Indian Point 2 data; data from other sites or sam ples were not part of the grading set. All Cecco tests (PWSCC and ODSCC) were graded to meet the 80% POD 0 90% CL per EPRI Guidelines because Cecco is not part of the QDA practical examination.

AnalysiS Process Analysis Process As a lesson learned in All CeccolBobbin probe data was All Cecco/Bobbin probe data was debriefing the analysts analyzed for both bobbin and Cecco analyzed for bobbin and Cecco results following the 1997 outage, it results concurrently by the Same analyst.

separately by different analyst team3.

was determined that the I.e. the primary analyst had to analyze for analysis was slowed due to both Cecco and bobbin.

analyzing both types of data concurrently. It was felt that this might lead to some level of distraction and fatigue for the analyst which might increase the potential for missed calls. The separate analyses allow the analyst to concentrate on one type of analysis, thereby improving that analysis. Also. it affords four looks at the data rather than two in the primary and secondary analyses.

-Standards used in 2000 meet new industry guidelines

Multiple Eddy Current Inspection Programs Multiple coil types Cecco, bobbin, MR pancake, HF pancake, MR +Point, HF +Point Base scope program 100% Cecco/bobbin, 100% U-bend +Point rows 2-4, re-roll RPC and bobbin Identified areas for improvement in crevice and sludge pile Expansion program

+Point from tube end through sludge pile

  • Examination of record for crevice and sludge pile Analysts reviewed data prior to expansion program

& Sludge pile, crevice, tube end and roll transitions

Base Scope Cecco and Bobbin Sludge Pile Examination Program SSPD in accordance with Rev. 5 of the EPRI NDE Guidelines Indian Point 2 data used for training and testing Cecco tests graded to meet 80% POD @ 90% CL 0 19 sample size

"* All hot and cold leg tubes examined from 20" above TTS to TE Eight hot leg axial ODSCC indications confirmed by +Point

"* SG 22; R33C51, R34C51, R35C51

"* SG 23; R31C47, R30C46, R31C46 and R29C46

"* SG 24; R42C43

"* Question about "blind zone" in sludge pile region

Base Scope Sludge Pile Insitu Tests

"* All sludge pile axial indications insitu tested R34C51 exhibited leakage Post insitu eddy current inspection

  • Previously unreported crevice cracking R34C51, R35C51 and R29C46 called by one analyst
  • Same primary and secondary analysts on R34C51 and R35C51

- Same analysts made calls on R33C51

"* Options assessed Re-analysis of crevice Cecco data

+Point inspection of crevice UT sample

"* +Point expansion selected Including sludge pile and UT sample

"* +Point training administered to analysts

Hot Leg Sludge Pile Expansion Program

  • 20% of the tubes in steam generators 21, 22, 23 and 24 inspected from TEH to below TSP1 (-48" above TTS) concentrated in kidney region
  • Results analyzed to determine maximum elevation above the tubesheet at which axial indications were found height of the sludge pile upper boundary for +Point inspections of the remaining tubes in each steam generator 0 The remaining 80% of the hot leg tubes in all steam generators were examined from TEH to a height of 24" above the top of tubesheet (20" plus a 20% buffer)

Cold Leg Sludge Pile Expansion Program

  • 20% of the tubes in steam generator 23 inspected from TEC to just below TSP1
  • Results analyzed to establish maximum elevation above the tubesheet at which indications were found height of the sludge pile 20% of tubes in steam generators 21, 22 and 24 were inspected from TEC to 24" above TTS expansion to another 20% sample necessary in steam generators 23 and 24 due to pits exceeding the 28% repair criterion no cracks detected pitting was detected

Base Program Versus +Point Expansion Program Sludge Pile Results Average +Point Signal Voltages and Lengths Base vs Expansion Program 0.8 0.7 0.6 AfV i

0.5 o.4 0.3 0.2 0.11 0

Ivolts 1 imLength

Sludge Pile Indications Expanded Scope S/G I Row Col Probe Cal Indication Primary Secondary Comments 21 34 41 PPT 531 SAI Yes No real flaw, modest amplitude increase post in-situ 22 33 49 PPT 331 SAM Yes Yes real flaw, modest amplitude increase I I post in-situ 33 54 PPT 473 MAI Yes Yes real flaw, no noticeable amplitude increase post in-situ; small shallow indication 34 54 PPT 315 MAI Yes Yes real flaw, modest amplitude increase II II post in situ

+Point Expansion Program Indications by Analysts Indications Primary Only Secondary Only Both Analysts Total Number 243 341 803 1387 Percent 17.5%

24.6%

57.9%

100%

,;No industry database on detection by single/both analysts

  • Recent sludge pile data from PLANT X:
  • 11 of 19 indications reported by both - 57.9%

+Point Expansion Program Hits and Misses for Axial Crevice and Sludge Pile Indications 0 Crack-like indications detected in the hot leg +Point expansion program were identified in the zone from 3" above tube end hot to maximum height examined (24" or 48" above TTS)

  • Coverage included crevice and sludge pile 24" above TTS for 80%

48" above TTS for 20%

  • These indications were assessed in terms of analyst statistics for HITS and MISSES by primary and secondary analysts.

A total of 210 indications

Analyst Performance for Axial Crevice and Sludge Pile Indications SG HIT MISS TOTAL PRI SEC PRI SEC PRI SEC 21 8

8 2

2 10 10 22 87 77 8

16 95 93*

23 45 42 10 12 55 54*

24 40 48 10 2

50 50 TOTAL 180 175 30 32 210 207*

AVG 85.7%

84.5%

14.3%

15.5%

  • Three tubes were reported as BDA by secondary analysts

Analyst Performance +Point Expansion Program Axial Indications in Crevice and Sludge Pile No tubes identified with significant sludge pile indications missed by a single (primary or secondary) analyst

"* Analyst conservatism demonstrated by overcalls Overcalls on the order of 7.7%

"* Statistics for individual analysts in the expansion program were evaluated where a statistically significant population of indications was evaluated Two analysts identified with "HITS" less than 80%

Study expanded to include entire +Point program Both analysts achieved "HITS" 80% or greater

"* Indications detected in the +Point expansion program were smaller in terms of voltage, length and depth as compared to those in the base scope program

Alternate NDE Method Ultrasonic Sampling in Sludge Pile Region Westinghouse UTEC system used to sample tubes steam generator 22 Two inspection phases inspection of localized areas of sixteen tubes where Cecco and/or bobbin eddy current examinations had identified indications and

+Point examinations were used for confirmation inspections of twenty-three tubes from just above the first support plate to the top of tubesheet

  • seven contained known eddy current indications
  • sixteen "NDD"
  • three tubes subject to full-length insitu pressure testing were included

Phase I Ultrasonic Sampling Results Cocco UE Tube~~

Voir Location C O e R18C83 13.92 TSHT~

+1.4F ND R1C83 2.52 TSH + 0.8

~PI

__DDN R721 73 TSR + 074

-PTF

-- R NDD7 R2C26 1.98 TSH +T2.~

PF TJDD NDD 93OC43 8.F TSH + 3.2 PF PIT PIT R33C1V 7.98 TSH + 0.61 PI AT MAI R33F6

-3T TSR-B 06--TFI

-- 7AF MAI RU -

55.2 TS + 1.~

F

-PIT NDD/DEPOSIT R3CF-30.12 TSH +0.3 P[F P-TrF NDD/DE POSIT R3428 14.22~ -TSH17-7V-

-PW

-NUD NODD R3451 24.35

-TSH -+ 0.17-

-Pr MAI MA R3C1 1~3-A9 TSH + 0.62 PF MAI MAI R357 118.4 TSH + 1.-41 PVI

--- TT-NDD/DEPOSIT 73C0 11755 TSHW+4 Pi VOL7 NDD/DEPO.SITr R35C5U 17.~32

-- TSII + 0-.27-PW VOL~

PIT R35C50 0.-67T s-i -0.19 TF-TDD NDD R335C5 10.6 TSH 06U PF MAI MAI R35CF 136 TS PF A

MAI R3C4 122.

TSH + 6.6 Pfl VOL NOD/DEPOSIT R3C4 8.09 TSH~

+TF P

NDD NDD R3U43 60 TSH + 9.069 PF N-DD-NDD R3C59 T13.8 TSH + 8.68 ----

F--? -- V01-NOD/DEPOSIT R4C3 16.2 TSH + 1.26" TF VOET PITAIWEAR R353 14.8 TSH + 1.29 PI NUD PITAIVEAR

Phase 2 Ultrasonic Sampling Results TWOb Post insitu

+-P-olnt Location UTEC R324-E NDD NA NDD 7O66 NO

~

NDD NA MIDD RKTC18N NDD NA NDD R1 81 NO ND Nw NOD RT5C32 NO NOD NA-NOD R15C7T NO NDD NA D

RT5C0 NO NDD NA NDD R17C72 NO NDD-NA' NDD R18C76 NO NDD NA NDD K22G75 NO

~

NDD-NA NDD RZZG78 No

~

NDUD NA NOD RZ5Q3T NO NODU NA NODU R25C49 NO PIT TSH +6.48 PIT R26C76 NO NDD NA-NOD1 R29C7 NO NDD NA NOD RIM1q04N NOD NA NOD1 R32C48 NO ZAl ISH UR+ 0.73 WA R33C51

~YES MA TSH + 1.7MAI 3454 NO

~

MAI TSH +0.57 MAI K~3~5(5 NO VOL TSH +0.38 PIT R35C-0T YES9 VA I TSH +0.-65 MAI R35C52 NO

~

MAF I

TSH +0.75 MAI R35C56 NO ND NA NOD J

L A

Ultrasonic Sampling in Sludge Pile Region All OD axial indications (SAI and MAI) confirmed by +Point were confirmed by UTEC.

  • No additional axial indications were found by ultrasonic inspection in areas where +Point did not confirm the Cecco and/or bobbin calls as OD axial degradation.
  • Cecco and/or bobbin indications not confirmed by +Point were also reported as NDD by UTEC.

There was general agreement between +Point and UTEC on volumetrics (VOL) and pits (PIT).

No evidence of "new" indications in tubes subject to insitu testing Validates eddy current results in sludge pile

Structural Integrity

  • Insitu pressure testing
  • 44 tubes tested excluding row 2 U-bends 40 with crevice or sludge pile indications 4 with no detectable degradation
  • No leakage from any indications in expanded program
  • No additional indications identified post-insitu above TTS 0 43 of 44 exhibited no leakage R34C51 in the base scope program was the exception

Conclusions Multiple eddy current examinations provide reasonable assurance of detection

"* No tubes with significant indications identified by only one analyst in the +Point expansion program

"* Expansion program analyst performance exceeds 80% POD @

90% confidence level

"° Ultrasonic testing identified no new indications Insitu pressure test results No new sludge pile indications No leakage for expansion program indications

"* Insitu and ultrasonic data provide independent assessment of sludge pile results Independent tests of 70 tubes with no detectable or additional degradation support statistics for 95% POD @ 95% confidence level

"* Multiple sources of data provide confidence in the inspection program

"* No additional data analysis is necessary

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