ML18039A466
| ML18039A466 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/31/1998 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-MA1153, NUDOCS 9808120181 | |
| Download: ML18039A466 (28) | |
Text
CATEGORY 1 REGULA Y INFORMATION DISTRIBUTION SYSTEM (RIDS) 4 ACCESSION NBR:9808120181 DOC.DATE: 98/07/31 NOTARIZED: NO DOCKET FACIL:50-'296'rowns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E.
Tennessee Ualley Authority RECIP.NAME REC1PIENT 'AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards corrections to data in util 980612 response to NRC staff recpxest for addi info re Revised Relief Recpxest 3-ISI-1.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TXTLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES:
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AEOD/SPD/RAB NRR/DE/ECGB OGC/HDS3 RES/DET/EMMEB NOAC 1
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NOTE TO ALL "RIDS" RECIPIENTS:
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Tennessee Valley Authority. Post Otfice Box 2000. Decatur. Alabama 35609 July 31, 1998 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Tennessee Valley Authority
)
Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 REVISED RELIEF REQUEST 3 ISI 1 r REACTOR PRESSURE VESSEL (RPV)
SHELL WELDS r AUGMENTED EXAMINATIONAND AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
SECTION XI INSPECTIONS CORRECTION OF DATA IN RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MA1153)
This letter submits corrections to data provided in TVA's June 12,
- 1998, response to the NRC staff's request for additional information (RAI), regarding BFN request for relief 3-ISI-1 (revised).
BFN request for relief 3-ISI-1 (revised) was submitted by letter dated February 17, 1998.
The staff requested additional information by letter dated May 19, 1998.
In TVA's June 12, 1998 response, BFN identified flaw size inspection data values that needed to be corrected for the flaw designated 12-015, located in circumferential weld H-34 (C-3-4). During the review and preparation of the corrected NIS-1 data sheets for flaw 12-015, incorrect inspection data values were also identified for flaws12-069, 12-116,12-144, 12-145,
These incorrect values were the result of typographical and data transposition errors.
- j. 3I.~~a
'tl808i20i8i stl8073i PDR ADOCK 05000296 8
0
U.S. Nuclear Regulatory Commission Page 2
July 31, 1998 As a result of these data corrections TVA has revised Attachment A (flaw evaluation table) of the enclosure to its June 12,
- 1998, RAI response.
It should be noted that only the data corrections for flaws12-069'nd 12-145 affect the information previously provided on Attachment A. The corrected data does not impact TVA's previous determination that the 15 flaws are subsurface.
TVA has also revised the table (Summary of BFN Unit 3 RPV Inspection Results and IWB-3600 Evaluation) in Attachment 2 of TVA's February 17, 1998 letter, transmitting revised request for relief 3-ISI-1.
Enclosure 1 to this letter provides the corrected Attachment A and two minor corrections from TVA's June 12, 1998 letter, discussed above.
Enclosure 2 contains corrections to request for relief 3-ISI-1 (revised) resulting from the corrected'law size data for flaws12-015, 12-069, and 12-145 referenced above.
The revised.data is provided on a page-for-page replacement basis to facilitate incorporation into the aforementioned submittals.
There are no new commitments contained in this letter.
If you have any questions, please telephone me at (256) 729-2636.
ncerely E. Abney Manager of L'ns'ng and Indus ry Af airs Enclosure cc:
See page 3
ll
U.S. Nuclear Regulatory Commission
,Page 3
July 31, 1'998 Enclosures cc (Enclosures):
Mr. Michael T. Anderson INEL Research Center 2151 North Boulevard P.O.
Box 1625 Idaho Falls, Idaho 83415-2209 Mr. Harold O. Christensen, Branch Chief U.S. 'Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611 Mr. Albert W.
De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
ENCLOSURE 1
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 REACTOR PRESSURE VESSEL (RPV)
SHELL WELDS I AUGMENTED EXAMINATIONAND AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
SECTION XI INSPECTIONS CORRECTIONS TO RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FOR REVISED RELIEF REQUEST 3-ISI-1 CORRE C TED PAGE S Attached are corrected pages for TVA's response to the staff's request for additional information dated June 12,.
1998.
The revised pages are listed bel'ow:
~
Page E-5, second paragraph fifth sentence, "As compared (Attachment B,
Figure 1)..." is revised to read "As compared (Attachment B, Figure 2)..."
~
Page E-S, data listed near the bottom of page, "S":
0.94 inches is revised to read "S":
0.75 inches.
Note:
0.94 inches includes the RPV cladding.
~
Attachment A (table) to the enclosure, "Reactor Pressure Vessel Flaw Evaluation for Subsurface Designation Considering NDE Method Uncertainties"
the Unit 3 RPV beltline materials in accordance with the requirements of NRC Regulatory Guide 1.99 Revision 2.
The P-T operating curves are periodically adjusted based upon calculations of accumulated fluence which are validated by testing of RPV material specimens.
The use of the 32 EFPY curves test temperatures will ensure that any needed compensation for the change in RPV RT~D~ will be adequately accounted for by the limitations imposed with the use of the new curves.
"...(b) provide the fluence for Weld H23 to clearly rule out any meaningful embrittlement of Weld H23 due to fluence, As stated in TVA's letter dated February 17,
- 1998, the calculated beltline region accumulated fluence for 12 EFPY of operation was 0.0401 x 10" n/cm'n the RPV wall.
Based upon the power uprate 32 EFPY operating P-T curve information the expected fluence in the beltline region was calculated to be 0.064 x 10 n/cm at the
~~ T (vessel wall thickness).
The P-T curves proposed to be used with the power uprate are based on a limiting beltline Adjusted Reference Temperature (ART) of 113 'F.
Xn the beltline region the elevation of the bottom of the active fuel (BAF) is 216.3 inches above the bottom of the vessel.
As compared (Attachment B, Figure 2), the calculated RPV fluence at an area 135 inches above the BAF (at 351.3 inches) will decrease to a level of approximately 50 percent of the value at the peak in the beltline region.
RPV circumferential weld H23 (designated as C-2-3 in figures and tables previously provided) is located at an elevation of 391.5 inches above the bottom of the RPV.
The H23 weld is the circumferential weld located between the vessel shell courses Mk-58 and Mk-59.
This is the first circumferential shell weld located above the beltline region shell course.
This area is 175.2 inches above the BAF region and is located 19.5 inches above the top of the designated beltline region.
Consequently, the fluence at the H23 weld will be considerably less than that encountered in the beltline region and has been conservatively estimated for the 32 EFPY of plant operation to be between 10 and 20 percent of the beltline peak fluence value.
This corresponds to fluence values for the H23 (C-2-3) weld of approximately 0.0064 to 0.0128 x 10 '/cm'.
This fluence is 2.5 to 4.2 times less than the beltline region expected fluence.
Materials test report data for the Unit 3 RPV H23 shell weld fabrication filler wire indicates that the percent Copper and Nickel content of the filler wire is 0.09 and 0.72 percent, respectively.
Calculations in accordance with the guidelines in Regulatory Guide 1.99, Revision 2, E-5
0
Equation (2-5) is derived from Equation 167 in Reference 11:
Kz P /
(2nc)
~
where "P" is load per unit depth and "c" is the distance from the application of P to the crack tip.
The equation used in GENE-523-120-0992 (Equation 2-5) is:
Ky 2@clad tclad /
(2nc) 1/2 The term a~i~~ t ~~~ is equivalent to P, and the factor of 2 is applied to account for loading on both crack faces.
The "c" term in Equation 2-5 is taken from the center of the clad
- depth, which is where the equivalent load P would be applied to the crack tip.
Therefore, TVA considers that Equation 2-5 on page 11 of GENE-523-120-0992 is an appropriate interpretation of Equation 167 from the paper by Paris and Sih (reference 11).
In addition to the above information, TVA has identified that flaw size inspection data values provided for the flaw designated 12-015, located in circumferential weld H34 (C-3-4),
need to be corrected.
These values are being amended to eliminate differences shown between the previously provided copies of the General Electric GERIS 2000 Examination Summary Sheets for RPV circumferential shell weld H34 (C-3-4) and vertical shell weld V4 (V-4-B).
These data sheets are shown as pages 6 of 9 and 9 of 9 in Attachment 2 of TVA's February 17, 1998, letter transmitting the revised request for relief 3-ISI-1.
This specific flaw data was reported on both data sheets because the vertical shell weld intersects the circumferential shell weld and the flaw indication is encountered in both the circumferential and the vertical shell welds'xamination volumes.
This flaw is circumferentially oriented and is actually located in the H34 (C-3-4) circumferential shell weld.
The discrepancies in the values are those shown for the flaw's Z position (z Pos),
the "S" value, and the "T wall" value.
The correct values are:
Z Pos:
1.16 inches "S":
0.75 inches T wall:
0.444 inches All other parameters for this flaw indication are correct and remain the same as originally reported.
These incorrect values were also reported in the original inspection data report submitted in the ASME Section XI NIS-1 outage summary report submitted following the Unit 3 cycle 5 outage by TVA E-8
Attachment A Browns Ferry Nuclear Plant Unit 3 Reactor Pressure Vessel Flaw Evaluation for Subsurface Designation Considering NDE Method Uncertainties Indication f/
Weld ID Indication No. T wall=2a 2a+.13 a
Aa s
Including Original Original Original RMS Error s/Aa Original "a" = (2a+.13)/2.4'I(2a+.13)/2l s-.13 (s-.13)/(.4'[(2a+.13)/2])
Original Results Including Including Including Including RMS Error RMS Error RMS Error RMS Error Result 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15
~FLG
~FLG CWFLG
~FLG C4-FLG C~
C~
C4-4 C~
C~
C4-4 C-24 C-24 2IWI07 20412 20409 20411 20408 16476 16475 12-148 12-116 12415 12-145 12~9 12-144 08426 08467 0.4 0.53 OA8 0.61 0.38 0.51 0.39 0.52 0.39 0.52 OA4 0.57 0.3 0.43 0.511 0.641 0.62 0.75 0.444 0.574 0.39 0.52 0.339 0A69 0.325 0.455 0.41 0.54 0.37 0.5 0.2 0.08 0.82 0.24 0.096 0.95 0.19 0.076 0.84 0.195 0.078 1.04 0.195 0.078 0.83 0.22 0.088 2.53 0.15 0.06 2.83 0.256 0.102 OA3 0.31 0.124 2.6 0.222 0.089 0.75 0.195 0.078 0.42 0.170 0.068 1.94 0.163 0.065 0.75 0.205 0.082 1.56 0.185 0.074 1.47 10.250 Subsurface 9.896 Subsurface 11.053 Subsurface 13.333 Subsurface 10.641 Subsurface 28.750 Subsurface 47.167 Subsurface 4.207 Subsurface 20.968 Subsurface 8A46 Subsurface 5.385 Subsurface 28.614 Subsurface 11.538 Subsurface 19.024 Subsurface 19.865 Subsurface 0.265 0.305 0.255 0.26 0.26 0.285 0.215 0.321 0.375 0.287 0.26 0.235 0.228 0.27 0.25 0.106 0.122 0.102 0.104 0.104 0.114 0.086 0.128 0.15 0.115 0.104 0.094 0.091 0.108 0.1 0.69 0.82 0.71 0.91 0.7 2.4 2.7 0.3 2.47 0.62 0.29 1.81 0.62 1A3 1.34 6.509 6.721 6.961 8.750 6.731 21.053 31.395 2.340 16A67 SA01 2.788 19.296 6.813 13.241 13A00 Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Subsurface Reference ASME Section XI, Figures IWA-3320-1 and IWA-3380-1 Ifs is greater than or equal to 0.4a, originally (i.e. the ratio is > 1.0); then the flawwas judged to be subsurface.
Ifthe conservatively adjusted "s," (s-.13), is greater than or equal to the conservatively adjusted "0.4a," (.4*[(2a+.13)12]) (i.e. the ratio is > 1.0); then the flawwas still judged to be subsurface.
0
ENCLOSURE 2
TENNESSEE'ALLEY AUTHORITY BROWNS. FERRY NUCLEAR PLANT (BFN)
UNIT 3 REACTOR PRESSURE VESSEL (RPV)
SHELL WELDS, AUGMENTED EXAMINATIONAND AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)'ECTION XI INSPECTIONS CORRECTIONS TO RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FOR REVISED RELIEF REQUEST 3-ISI-1 CORRECTED
'PAGES FOR REQUEST FOR RELIEF 3-ISI-1 '(REVISED)
Attached are corrected pages for request for relief 3-ISI-1 (revised) submitted by TVA letter dated February 17.,
1998.
The revised pages are listed below:
~
Attachment 2,
page 1 of 9, Table, Summary Of BFN Unit 3 RPV Inspection Results And IWB-3600 Evaluation.
~
Attachment 2,
pages 6,
7 of 9, Geris 2000 Examination Summary.Sheet for RPV. weld C-3-4, indications12-015, 12-069,12-116, 12-144, 12-14'5, and 12-148.
~
Attachment 2,
page 9 of 9, Geris 2000 Examination Summary Sheet for RPV weld V-4-B, indication 12-015.
~
Attachment 3,
page 13 of 15, Figure 8,
"Flaw Evaluation of Subsurface UT Indications vs. Year 40 Allowable Curves for H23,
- H34, H45"
0
SUMMARY
OF BFN UNIT3 RPV INSPECTION RESULTS 8 IWB-3600 EVALUATION Weld Indication RPV Wall a /t ID No.
Thickness'ctual'in)
(%)
a/t 2a allowed'ctual'%)
(in) 2a allowed (in)
Difference actual -
allowed'%)
(in) 2a allowed'in)
Margin allowed actual 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 C-5-FLG C-5-FLG C-5-FLG C-5-FLG C-5-FLG C-4-5 C-4-5 C-3-4 C-3-4 C-3-4 C-3-4 C-3-4 C-3-4 C-2-3 C-2-3 20-007 20-012 20-009 20-011 20-008 16-076 16-075 12-148 12-116 12-015 12-145 12-069 12-144 08-026 08-067 6.54 6.87 6.59 6.62 6.55 6.60 6.60 6.44 6.49 6.53 6.44 6.51 6.44 6.60 6.55 3.05 3.47 2.91 2.92 2.98 3.33 2.27 3.97 4.81 3.40 3.03 2.66 2.45 3.11 2.82 2.27 0.40 0.30 2.97 0.48 0.41 2.41 0.38 0.32 2.58 0.39 0.34 2.74 0.39 0.36 2.87 0.44 0.38 2.23 0.30 0.29 2.46 0.51 0.32 3.96 0.62 0.51 2.71 0.44 0.35 2.39 0.39 0.31 2.48 0.35 0.32 2.39 0.32 0.31 2.79 0.41 0.37 2.68 0.37 0.35 0.78 0.50 0.50 0.34 0.24 0.46 0.04 1.51 0.85 0.69 0.64 0.18 0.06 0.32 0.14 0.102 0.069 0.066 0.045 0.031 0.061 0.005 0.194 0.110 0.090 0.082 0.023 0.008 0.042 0.018 1.36 1.53 1.40 1.43 1.46 1.92 1.92 1.92 1.92 1.92 1.92 1.92 1.92 1.92 1.92 3.4 3.2 3.7 3.7 3.7 4.4 6.4 3.8 3.1 4.3 4.9 5.5 6.1 4.7 5.2 CONTROLLING VALUES:
1.51 0.194 Notes:
1.
Examination data and assessment per IWB-3500 as submitted by March 6, 1995 letter to NRC.
2.
Per IWB-3600 or lower bounded by 1/3 vessel thickness as reflected by GE fracture mechanics analysis.
This is the maximum Year 6 (Cycle 5 outage for BFN Unit 3) depth (2 a) which would be acceptable following an additional 34 years of service (40 year total service life) considering fatigue crack growth due to design basis cyclic loads on the vessel shell.
3.
Indication 12-116 is actually a combination with indication 12-117 and reflects reevaluation by GE on June 11, 1998.
4.
Same indication recorded forweld V-4-B.
3.1
0
GE Nuclear Energy GERIS 2000 Examination Summary Sheet PrajeCt:
TVA, Browns Ferry Nuclear Plant. Unit 3 SyStem:
Reactor Pressure Vessel Weld ID: C-3<
ASME Code Category:
B-A Calibration Sheets:
c-001, c404, c-115, c-116, and c-117 Supporting Data:
Examination Data Sheets E-1240 thru E-12-15, Indication Data Sheets12-001 Ihru-12-163, Indication Evaluation Sheets, Screen Prints, Exam Patch Location Map, Exam Coverage Plots, GERIS 2000 Setup Records and Manual Data Sheets 0434, D-035, 0-036, 0437, 0-040, 0441. 0444 and 0445.
Examination Summa The ultrasonic examination of weld C-3A resulted in six (6) recorded indications that exceed the allowable standards of IWB-3500, ASME Section XI, 1986 Edition, No Addenda.
The ASME Section XI required examination volume was examined with the GERIS 2000 Syatem from the RpV inside surface utilizing Procedure No. GE-UT-/00, Rev. 2. This examination was limited due to the Guide Rods at 0'nd 180'. The total examination coverage was calculated to be 97%.
The GERIS 2000 utilizes an array of, search units arranged to effectively examine the weld and adjacent base material parallel and perpendicular to the weld axis in two directions.
The transducer packaae consisted of 0'ongitudinal, 45'nd 60'hear wave, and 70'efracted longitudinal (RL) wave search units; The six (6) unacceptable indications were recorded and sized in accordance with GE-UT-700, Rev. 2 and GE-UT-701, Rev. 2 with the results tabulated belovr.
12415 circ.
subsurface 94.35" Ind. No.
Oriented Type X Pos Y Pos ZPos "S"
.75" 525.43" 1.16 T wall Length T Meas 1.75" 6.53" 0.13 3.4 a/I
% a/t Calculated
% alt Allowed 2.71 12469 circ.
subsurface 424.65" 524.58" 2.30" 1.94"
.339" 1.75" 6.51" 0.10 2.66 2.48 12-116 12-144 12-145 12-148 circ.
subsurface 617.15" circ.
subsurface 760.10" circ.
subsurface 763.85" circ.
subsurface 771.35" 526.14" 3.85" 2.6 525.68"
.80" 525.07"
.87" 42M 43II 525.11" '.10"
.75"
.62"
.325"
.39"
.511"
.75" 2.00" 2.40" 2.75" 6.49" 6.63" 6.44" 6.44" 0.21 4.81 0.08 2.45 0.08 3.03 0.09 3.97 3.96 2.39 2.39 2.46 Indication 12415 was sized with 70'L channel 5 utilizing the PATI'echnique.
This indication was also recorded as12-016 and 12-020.
Indication 12-015 was also recorded within the exam volume of weld V+B.
Indication 12469 was sized with 45'hear wave channel 9 utilizing the SPOT technique.
Indication 12-1 16 and 12-117 is a combined indication in accordance with IWA-3390 and is included in the table above as,12-116.
The individual parameters for indications12-116 and 12-117 are as follows Indication 12-116 T-wall =.311"; a/I = 0.21; a/t% allowed = 3.37%; a/t% calculated = 2.40%
,Indication 12-117 T-wall =.311"; a/I = 0.31; a/t% allowed = 4.55%; a/t% calculated = 2.40%
IWA-3390 calculations (al+az)</zz (ac+a'o)/2 or (.156"+.156") <Izz ((6.49.0337)+(6.49.0455)/2 which =.312 <I=.257
'ndication 12-116 calculations in accordance with IWA-3390 T-wall =.62" (.312 2); a/I = 0.21" (aspect ratio for longest individual flaw):
% a/t calculated = 4.81 (.312/6.49); % a/t allowed = 3.96 (.257/6.49)
TITLE:
oAzz: 'tt'j'>"
GERIS Analyst:
,. Tie/rs UTILITYRevie GE Reviewer. g LEVEL:
ANIIReview:
TITL oAzo; z/zz oATR i~/58 6of9
4l
GERIS 2000 Examination. Summary (Cont/nuation) indication 12-1,16 any 12-117 were sized with 45'hear wave channel 7 utilizing the SPOT technique.
Indication 12-144 was sized with 70'L channel 5 utilizing the PATT technique.
This indication was also recorded as 12 130, 12 150, and 12-157.
Indication 12-145 was sizedwith 70 RLchannel4utilizing thePATTtechnique.
This indicationwas alsorecorded as12-131. 12-158,12-161. 12-162 and 12-163.
Indication 12-148 was sized with 70 RL channel 5 utilizing the PATT technique.
This indication was also recorded as12-132 and 12-160.
The GERIS 2000 also recorded indications with the 0'eld metal scans, 70'L, 45'nd 60 shear wave scans that were evaluated and found to be acceptable per the referencing Code section.
Geometric indications from the OD surface, Nozzles N11-A, N11-8 and N4-F were recorded with the 45'nd 60'hear wave scans.
Selected areas were rescanned using 45'L search units.
The manual technique utilized 0 longitudinal. 45'nd 60'hear wave search units both parallel and perpendicular to the weld axis in two directions to effectively examine the weld and adjacent base materiaL No indications were recorded with the manual technique.
Fabrication records and previous examination results were reviewed prior to the completion of this examination summary.
Summary revised 6/11/98.
Ind. 12469 throughwall dimension corrected.
Ind.12-116 % a/t Allowed corrected.
Ind.12-144 Z Pos and a/I corrected.
'nd.12-145 "S" and a/I corrected.
Ind.12-148 a/I corrected.
Added explanation for 12-116 calculations 7of9
0 0
I I 1
GE Nuclear Energy GERIS 2000 Examination Summary Sheet Project:
TVA, Browns Ferry Nuclear Plant, Unit 3 System:
Reactor Pressure Vessel Weld lD: VA-B Calibration Sheets:
C-001 ASME Code Cafegoryr B-A SI/pporting Qata:
Examination Data Sheets E-1440 and E-14-01
~ Indication Data Sheets14-001 thru 14405 and G-100 thru G-108, Indication Evaluation Sheets, Screen Prints, Exam Patch LocaUon Map, Exam Coverage Plots and GERIS 2000 Setup Records.
Examination Summa The ultrasonic examination of weld VA-Bresulted in one (1) recorded indication that exceeds the allowable standards of IWB-3500, ASME SecUon XI, 1986 Edition, No Addenda; The ASME Section XI required examination volume was examined with the GERIS 2000 System from the RPV inside surface utilizing Procedure No. GE-UT-700, Rev. 2. This examination was limited due to the N11-A Nozzle at 40'. The total examination coverage was calculated to be 83%.
The GERIS 2000 utilizes an array of search units arranged to effectively examine the weld and adjacent base material parallel and perpendicular to the weld axis in two directions.
The transducer package. consisted of 0'ongitudinal, 45'nd 60'hear wave, and 70'efracted longitudinal (RL)wave search units.
The one Indication evaluated as being reportable to IWB4500, ASME Section XI, 1986 Edition, No Addenda was recorded and sized in accordance with GE-UT-700, Rev. 2 and GE-UT-701, Rev. 2.
This indication was recorded during the examination of both welds V4-B as 14402 and C-34 as12-015.
The flaw dimensions were determined from weld C-34 Indication Data Sheet 12415 with the results tabulated below:
Ind. No.
Oriented Type X Pos Y Pos Z Pos
~Sr T wall Length T Meas a/I
% a/t Calculated a/t Allowed 12-015 circ.
subsurface 94.35" 525.43 1.16" 0.75
.444 1.75 6.53" 0.13 3.4 2.71 This indication was sized viith the 70'RL utilizing the PATT technique.
It was also recorded with the 45'nd 60'hear waves.
The GERIS 2000 also recorded an indicaUon with the 0'eld metal scan that was evaluated and found to be acceptable per the referencing Codesection.
Geometricindicationsfromthestabilizerbracketat45 wererecordedwiththe0 weldmetal,45'and60'hear wave scans.
No manual supplemental examination was performed from the RPV outside surface due to access restricUons.
Fabrication records and previous examination results were reviewed prior to the compleUon of this examination summary.
Summary revised 6/11/98. Ind.12-015 Z Pos, S". and throughwall dimensions corrected.
GERIS Analyst:
5 rv wP ANIIReview:
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0.1 0.2 0.3 0.4 0.5 Flaw Aspect Ratio (alLj Figure 8, Evaluation ofSubsurface UT Micatious vs. Year 40 Allowable Curves for H23, 834, H45
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