ML18038B701
| ML18038B701 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/04/1996 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9606100067 | |
| Download: ML18038B701 (50) | |
Text
CATEGORY 1 REGULATOR@
INFORMATION DISTRIBUTION%STEM (RIDE)
~ 'ACCESSION NBR:9606100067 DOC.DATE: 96/06/04 NOTARIZED:
NO DOCKET I FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, 'Tennessee 05000260 AUTH.,NAME AUTHOR AFFILIATION SALAS,P.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides results of reinspection of indications found in initial Unit 2 core shroud weld insp a results of in-vessel visual insps.
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1 NOTE TO ALL "RIDSN RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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i5
Tennessee Valley Authority. Post Office Box 2000. Decatur. Alabama 35609 June 4,
1996 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket No. 50-260 BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 RESULTS OF CORE SHROUD REINSPECTION AND IN-VESSEL VISUAL INSPECTIONS CONDUCTED DURING THE CYCLE 8 REFUELING OUTAGE This letter provides the results of the reinspection of indications found in the initial BFN Unit 2 core shroud weld inspection and the results of the in-vessel visual inspections.
In a letter to NRC dated August 23,
- 1994, TVA committed to perform reinspections of the BFN core shrouds as recommended in General Electric (GE) Service Information Letter 572 (i.e.,
once per refueling outage, if flaws were discovered during the initial inspection, until the flaws are repaired).
The reinspection was performed during the Unit 2 Cycle 8 refueling outage that began on March 23, 1996.
TVA performed ultrasonic non-destructive examinations for 100 percent of',the accessible areas on the horizontal welds using the GE Smart-2000 system.
The results of the reinspection indicate that severe core shroud cracking is not occurring in Unit 2.
Also, crack growth is bound by the assumptions made in the Boiling Water Reactor Vessel and Internals Project (BWRVIP) report number BWRVIP-01, Revision 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines."
'P606i00067,960604 PDR ADQCK'05000260 8
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U.S. Nuclear Regulatory Commission Page 2
June 4, 1996 TVA -has analyzed the inspection results and determined that Unit 2. can be safely returned to service and operated for at least one cycle of operation without repairs.
Cracking of the Unit 2 core shroud welds is limited and poses no significant near-term concern for structural integrity.
In addition to the inspection of the core shroud welds, several other reactor vessel components were inspected during the Unit 2 Cycle 8 outage.
.These inspections were conducted in accordance with the inspection requirements for reactor pressure vessels as stated in American Society of Mechanical Engineers
- Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components."
The enclosure to this letter provides background information regarding BFN's Unit 2 core shroud weld inspections.,
Also included in the enclosure is a summary of the inspection results and TVA's shroud analysis.
This letter is provided based on a verbal request from the NRC Project Manager for BFN.
There are no commitments contained in this letter.
If you have any questions, please telephone me at (205)729-2636.
Since el Pedro Salas Manager of Site Licensing Enclosure cc:
See page 3
0 I+I
U.S. Nuclear.Regulatory Commission Page 3
J'une 4, 1996 Enclosure cc (Encl'osure):
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident InsPector Browns Ferry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611 Mr. J.
F.. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 REACTOR CORE SHROUD INSPECTION PERFORMED DURING CYCLE 8 REFUELING OUTAGE RESULTS AND ANALYSIS I'ACKGROUND Intergranular stress corrosion cracking (IGSCC) of boiling water reactor (BWR) internals has been identified as a
technical issue of concern by NRC and the nuclear industry.
TVA has been aware of IGSCC concerns in the reactor core shroud and has been working closely with General Electric (GE) and the Boiling Water Reactor Owners Group (BWROG) to address the issue.
As a result of IGSCC concerns, NRC issued Generic Letter (GL) 94-03, "Intergranular Stress Corrosion Cracking (IGSCC) of Shrouds in Boiling Water Reactors,"
on July 24, 1994.
In the GL, NRC requested that BWR licensees inspect their core shrouds for cracking at the next scheduled refueling outage and provide the inspection results within 30 days of completing the inspection.
In its response to the GL dated August 23,
- 1994, TVA committed to inspect 100 percent of the accessible areas on welds H1 through H7 (see Figure
- 1) using the best available non-destructive examination (NDE) technology.
TVA also committed that subsequent core shroud inspections would be performed as recommended by GE Service Information Letter (SIL)-572 (i.e.,
once per refueling outage, if flaws were discovered during the initial inspection, until the flaws are repaired).
The initial inspection was performed during the Unit 2 Cycle 7 refueling outage.
The inspection results were transmitted by TVA letter to NRC dated November 18, 1994.
The reinspection discussed in this report was performed during the Unit 2 Cycle 8 refueling outage that began on March 23, 1996.
II'NSPECTION
SUMMARY
TVA inspected 100 percent of the accessible areas on the Unit 2 core shroud welds H1, H2, H3, H5, H6, and H7 using ultrasonic NDE methods.
Weld H4 was not examined during this inspection since there were no reported indications during the initial (Cycle 7) inspection.
Welds H2, H3, and H5 were inspected since indications were previously found.
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Examination of weld H1 was added to the inspection scope to obtain more inspection coverage.
Welds H6 and H7 were inspected with improved techniques, which signi'ficantly increased the inspection area for both welds.
The inspections were completed on April 10, 1996.
The inspections were performed by qualified personnel using the best available technology in accordance with approved BFN procedures.
Personnel performing the scanning examinations were certified to at least Level II status in accordance with GE procedures FQP-03 and/or
- 386HA480, which meet the requirements of American Society of Non-Destructive Testing recommended practice SNT-TC-1A, 1984 Edition.
Additionally, personnel performing the ultrasonic (UT) examinations were qualified through the Electric~Power Research Institute (EPRI)
NDE Center in accordance with the Coordination Plan for NRC/EPRI/BWROG Training and Qualification Activities of NDE Personnel.
Evaluations of weld examination data were performed by personnel certified to Level III status, in accordance with the GE procedures listed above.
Ultrasonic examinations (UT) were performed using the GE Smart-2000 system.
UT was performed on 100 percent of the accessible areas for the six welds examined.
Visual observations were performed in selected areas to locate obstructions and assist in positioning the ultrasonic test equipment.
Inspection procedures were prepared to implement the applicable portions of American Society of Mechanical Engineers (ASME) Code,Section V and XI requirements, NRC/EPRI/BWROG Coordination Plan, and GE SIL-572.
Accessibility for the inspections was limited due to various equipment or internal structures that restricted access to the welds.
The proximity, of various components such as guide pins, shroud lifting lugs, core spray downcomers, shroud head locking lugs, jet pump riser braces, and jet pumps precluded further examination.
The following provides a summary of the amount that each weld was examined:
'WELD NUMBER CIRCUMFERENCE EXAMINED INCHES PERCENTAGE EXAMINED H1 H2 H3 H5 H6 H7 434.08 434.08 450.97 428.20 426.58 405.91 62.81 62.81 69.31 65.81 67.64 64.36 E-2
0 igt
Examination coverage for=welds H2, H3,,
and H5 was approximately the same as that achieved during the Cycle 7
inspection.
The coverage for weld Hl (which was added to the inspection scope to.obtain a larger inspection area) increased from 33..35 to 62.81 percent.
The coverage for welds H6 and H7 increased dramatically from that achieved during the initial (Cycle 7) inspection (3.33 to 67.64 percent and 2.22 to 64.36 percent, respectively).
This increase is attributed to the smaller transducer package uti:lized during the Cycle 8 inspection.
III INSPECTION RESULTS The results of the BFN Unit 2 Cycle 8 inspection indicate that severe cracking of the core shroud is not occurring.
During UT inspections, surface-connected planar indications associated with IGSCC were found in the welds inspected.
The flaws were dispersed around the circumference of each weld.
There were no through-wall cracks identified.
The individual Examination Summary Sheets for shroud welds Hl, H2, H3, H5, H6, and H7. are provided as an attachment to this enclosure.
A summary of the Cycle 8 inspection results is provided below.
WELD NUMBER INSPECTION TYPE RESULTS FLAW TYPE H1 H2 H3 H5 H6 H7 UT UT UT UT UT UT (2) indications 4.49" total length (2) indications 2.73" total length (6) indications 15.98" total length (6) indications 8.82" total length (13) indications 34.65" total length (26) indications 65.63" total length Planar Planar Planar Planar Planar Planar E-,3
4l
IV SHROUD ANALYSIS
SUMMARY
TVA's analysis of the Unit 2 core shroud cracks identified during the Cycle 8 inspection show that restart and operation for an additional 18-month operating cycle is acceptable.
The analysis calculated the safety factors for the inspection areas and weld indications for the Cycle 8 inspection.
The analysis was based on the fracture mechanics limit load based screening criteria and evaluation techniques applicable to BFN.
For welds H1, H2 H3I H5I H6g and H7, the limit load safety factors were calculated using the Distributed Ligament Length methodology.
For weld H3, Linear Elastic Fracture Mechanics (LEFM) methodology was also used to calculate the safety factors.
This methodology was used since the fluence level for the H3 weld is expected to be greater than 3x10'eutrons per square centimeter (n/cm').
Table 1 provides the safety factors calculated for each inspected weld.
The following assumptions were used to perform this evaluation:
~
All uninspected areas were assumed to be fully cracked.
~
Only areas with no indications in which all three transducers are engaged were considered as uncracked metal.
~
The inspected flaw depth for each indication was used for this calculation.
~
A conservative crack growth rate of 5 x 10 inches/hour of hot operation was used.
~
Crack growth for two 18-month cycles was added to each flaw depth and to each flaw end.
~
NDE uncertainty of 0.4 inches plus 0.5 degrees was added to the end of each flaw.
~
NDE uncertainty of 0.15 inches was added to the depth of each flaw.
The required safety factors are 2.77 for Normal/Upset conditions and 1.39 for Emergency/Faulted conditions.
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TABLE 1 SAFETY FACTORS USING TWO CYCLES OF CRACK GROWTH LIMIT LOAD LEFM WELD H1 H2 H3 H5 H6 H7 NORMAL/
UPSET SF 49.8 42.3 44.9 18.5 14.1 6.8 EMERGENCY/
FAULTED SF 21.0
- 18. 3 19.7 8.7 7.1 3.5 NORMAL/
UPSET SF 5.'5 EMERGENCY/
FAULTED SF 2.4 V0 CONCLUSION The results shown in Table 1 above indicate that the minimum safety factors for the inspected welds are met for two cycles of crack growth.
These results support operation for at least one additional 18-month cycle.
Therefore, it is acceptable to operate Unit 2 through the Cycle 9 operating cycle.
The results of the inspection confirm that cracking in the Unit 2 core shroud welds is limited and poses no significant near-term concern for structural integrity.
VI~ IN-VESSEL VISUAL INSPECTION In addition to the inspection of the core shroud welds, several other reactor vessel components were subjected to In-Vessel Visual Inspection (IVVI) during the Unit 2 Cycle 8
outage.
These inspections were conducted in accordance with the inspection requirements for reactor pressure vessels as stated in ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components."
Additional requirements and recommendations can be found in the Code Of Federal Regulations 10 CFR 50.55a, 10 CFR 50 Appendix G, NRC Regulatory Guides, and GE SILs.
A brief summary of IVVI activities performed during the Unit 2 Cycle 8 refueling outage follows:
E-5
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Top Guide The lower beams (where fuel and blade guides are removed) were visually inspected in accordance with GE SIL-554.
The retaining pins were visually inspected in accordance with GE SIL-588.
No indications were recorded.
Jet Pump Sensing Lines - The sensing lines were visually inspected in accordance with GE SIL-420.
No indications were recorded.
Jet Pump Throats - Jet Pumps 11 and 12 were visually inspected in accordance with GE SIL-465, Revision 1, to determine if blockage exists.
Some minor corrosion oxide build-up was found on the inlet mixer, but not in the throat area.
No other indications were recorded.
Jet Pump Riser Braces - The braces and welds on Jet Pumps 11 through 20 were visually inspected in accordance with GE SIL-551.
No indications were recorded.
Jet Pump Adjusting Screws - The tack welds on the screws were visually inspected in accordance with GE SIL-574.
Very small linear indications were observed on three jet pump restrainer set screw tack welds on Jet Pump 1, Jet Pump 11, and Jet Pump 12.
The indications were evaluated and determined to be irrelevant due to their very small size.
Vessel Interior Attachments - The dryer support brackets, guide rod brackets, feedwater sparger brackets, core spray piping brackets, jet pump riser support bracket, and shroud support were visually inspected in accordance with BFN Surveillance Instruction 2-SI-4.6.G.
No indications were recorded.
Reactor Pressure Vessel (RPV) Cladding - The RPV cladding was visually inspected in accordance with 2-SI-4.6.G to determine if additional degradation has occurred.
No changes were observed between this examination and prior examinations.
~
Core Shroud Support Access Hale Covers - Welds on the access hole covers were UT examined in accordance with GE SIL-462.
No reportable indications were recorded on either cover.
~
Core Spray Spargers and Associated Piping - The Core Spray Spargers and associated piping were visually inspected in accordance with IE Bulletin 80-13 and BFN Mechanical Section Instruction MSI-0-001-INS-001.
The Core Spray T-box was also visually inspected in accordance with E-6
t
While inspecting the "B" core spray
- sparger,
.a small indication was observed that was located in the lower tack weld of the nozzle to sparger in nozzle 3B.
An evaluation of the tack weld was performed and it was determined to be acceptable.
The weld is one of two tack welds that act as a locking device for the core spray sparger threaded nozzle lock nut.
Further, it. was determined that the tack welds do not provide any structural integrity.
In order for the nozzle to become
- loose, both tack welds would have to fail and the lock nut would have to rotate loose.
.One tack weld has no indications, and the tack weld in question has an indication on only one of four sides.
No other indications were recorded.
Core Spray Piping - A visual inspection of the Core Spray piping and welds inside the RPV was performed.
An enhanced visual of the accessible piping welds was performed from the slip joint area to the shroud attachment point in accordance with the guidance provided in GE SIL-289, Revision 1, Supplement 2.
The remaining accessible surfaces and welds were inspected to the requirements of IE Bulletin 80-13.
No indications were recorded.
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ATTACED(1E!vT EXAMINATION
SUMMARY
SHEET
'E Nuclear Energy I
Egl PROJECT:
EIROWNS FERRY NUCLEAR I
, PROCEDURE~BEKSOXV~
REV~ FRR: ~l SYSTEM:
PV-WELD NO.:
CONFIGURATION:
hr Fl n Pl REV EL FRR;~
REV:~ FRR:~
EXAMINER: wa EXAMINER:
EXAMINER:
LEVEL: Ul LEVEL:~
LEVEL:~if~i WELD TYPE:
MT CIRCUMFERENTIAL LONGITUDINAL 0 OTHER DATASHEET NO.(S): ~1622=23~I=26 CAL SHEET NO.(S):
Ouring the ultrasonic examination of the above referenced weld. Nvo (2) indications associated with IGSCC were recorded by the "Smart 2000" system utilizing a 45'hear wave. 60'efracted longitudinal (RL) wave. and OO creeping wave search units.
The 45'hear wave search unit did record non-relevant indications. inside and outside weld crown geometry and acoustic interface, along with the indications referenced above.
The 60 RL search unit recorded non-relevant indications. inside weld crown geametry, along with the indications referenced above.
The OO creeping wave search umt did record non-relevant indications along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in angular units. The conversion factor for linear units is 1.75 inches per degree.
Examination Area: Examined 31 lug sets for a total area scanned of 226.10 (62.81'k), which was interrogated by all transduceis.
17 lug sets were not examined due to inaccessibility.
This examination was limited to the areas scanned due to abstructians from the guide pins. shroud lifting lugs, wbration instrumentation pads and lines, and core spray downcomers.
The examination was performed from the upper side of the weld only. due to shroud head holddown lugs. The H-1 and H-2 examinations were performed simultaneously from the plate side only.
For the indication and limitation parameters see page 2. For additional details see drawings BFN41-ROLL, indication map and the scan plan.
G REVIEWED BY LEVEL DATE LEVEL OATK GEIN PE NTR UTIUTY REVIEW nfl II4 i
PAGEL!
OF
ii ik
GE Nuclear Energy 7VA EIowns Ferry Huclear U2cd shroud UTprolecr 1Fz(t(9 March t995 Shroud Weld H-1 Indication Data 7 otal Scan Length Examined (Oeg)
Total Scan Length Examined (In.)
Percentage of Weld Length Examined Percentage Flawed of Examined Weld Length Percentage Rewed of Total Weld Length Total Flawed Length (Deg.)
Total Rawecl Length (In.)
226.10'34.08" 62.81%
1.03%
0.55%
2.34'A9" Thickness (In.)
Circumference (In.)
Inchea per Degree Degrees per Inch 2.00" 691.15"'.92" 0.52'nd.
Start End Length Lengtlr Length
'Depth Depth Depth Percent Indication Ho.
Deg.
Oeg.
Deg.
In.
Trans MaxJn.
Trans
'PoaOeg.
771ruwall Location' 12.21 13AB 1.24 2.38 6OL 0.36 45e 12.92 18.0 LowerllO' 267.88 268.98 1.10 2.11 45a OA7 6OL 268A8 23.d LowerllO Scan Mufdple Type Scan 1
N 1'
,Indlcat/on Comments:
'n reference to the weld D Indicadon depth is measured from initiation surface. either I.D. or O.O.. as applicable.
Indication length as noted In inches refers to O.D. measurements.
regardless of whether the indication is I.O. or O.D..
D Indlcadon 8 1, and 2 areas. were not examined during the U2C7 ISI.
Areas Hot Examined by All3 Transducera (Azimuth References)t Examination Umltadonal 0.00 lo 12.30 Ior 12.30'uide Pin and Core Spia,Oowncomer.
158.50 to, 250.70'or 101.90 Lilti Lu, Core Spra Oowncomers. Guide Pin and Vibration Lu s.
340.30 to 350.00 for 19.70 Ufd L
. Core Spra Oowncomer and Guide Pin.
Total Degrees Hof Examined 133.90 Exp(anadon of Examination Urn(tat)oner v
No accessibility for the exameadon equipment due to the proxtm+ of the limitations referenced above.
Additional Comments:
None Preparedby'ate: ~re" w Reviewed te MJK BFN2DATA.XLS 4/10/96 12:48 Revision 1
page Z.
ii
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4/
t EXAMINATION
SUMMARY
SHEET
'EPGRT "o'E Nuclear Energy I
I ~~2 I
PROJECT:
BROWNS FERRY NUCLEAR I
IIPROCEDURE:
REV'~ FRR SYSTEM: Els~HJJQ REV'~ FRR CONFIGURATION:
Pl T
id
'n REV:~ FRR;~
EXAMINER:
EXAMINER' LEVEL:
LEVEL:~
LEVEL ~~/
WELD TYPE:
MT'T OUT CIRCUMFERENTIAL LONGITUDINAL 0 OTHFR DATASHEET NO.(S):
CAL SHEET NO.(S):
During the ultrasonic examination of the above referenced weld. two (2) indications associated with IGSCC were recorded by the "Smart 2000" system utilizing a 45'hear wave. 60 refracted longitudinal (RL) wave, and OD creeping wave search units.
The 45'hear wave search unit did record non-relevant indications. inside and outside weld crown geometry and acoustic interface, along with the indications referenced above.
The 60'L search unit recorded non.relevant indications, inside weld crown geometry, along with the indications referenced above.
The OD creeping wave search unit did record non-relevant indications along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in angular units. The conversion factor for linear units is 1.75 inches per degree.
Examination Area: Examined 31 Iug sets for a total area scanned of 226.10'62.81%), which was interrogated by all transducers.
17 lug sets were not examined due tc inaccessibility. This examination was limited to the areas scanned due to obstrucbons from the guide pins. shroud lifting lugs..vibration instrumentation pads and lines. and core spray downcomers.
The examination was performed from the upper side of the weld only, due to limitations from the. weld orientation.
The H-I and H-2 examinations were performed simuitaneotisty from the plate side only.
For the indication and limitation parameters see page 2. For additional details see drawings BFNC1-ROLL, indication map and the scan plan.
GE I OEPENOENT REVIEW UTILITY REVIEW PAGE'
ii il
GE Nuclear Energy iYA Srotttns Feny Nuclear U2CS Shroud VTProiect >FZN9 Afatch f995 Shroud Weld H-2 Indication Data Total Scan Length Examined (Deg)
Total Scan Length Exanrined (In)
Percentage of Weld Langur Examined Percentage Hewed of Examined Weld Length Percentage Flawed of Total Weld Length Total Flawed Lengtlr (Oeg.)
Total Flawed Length (In.)
228.10'34.0S" 62.81'%
0.53'%.3' 42'.73" Thickness (In.)
Circumference (In.)
Inches per Degree Degrees per tinch 2.00 691.1 6, 1.92 0.52'nd.
Start End Length Length Length Depth Depth Deptlr Percent Indlcadon Scen Multiple Ho.
Deg.
Deg.
Deg.
In.
Trans Max.ln.
Trans Pos.Oeg.
Thruwaff Locadon Type Scan 1
72.82 73.34 0.52 1.00 45e
<0.20 45a 73.13
<10.0 Upperil0 1
N 2
273,79 274.59 0.90 1.73 45a 0.82 60L 274.09 41.0 UpperliO N
Indication Commentsl
'n reference to the weld
>> indlcadon depth ts measured from Inttiathn surface. either l.O. or O.O., as applicable.
tndicabon length as noted in inches refers to O.O. measurements.
regardless ol whether theindicaSonis l.O. or O.O..
>> Upon review of U2c7 data. indicadon a 2 was recorded. but not repoaed. at approximately the same parameters ss referenced above.
Areas Hot Examined by All3 Transducera (Azimuth References)I 0.00'o IL30 for tL30 Guide Pin and Core Sp Oowncomer 159.80 Io 250.70 for 101.90 Liiti
. core spra oowncorners. Gutde pin and vibration Lu s.
34040 Io 350.00 for.
19.70'i
. Core S ra Oowncomer and Guide Pin.
Total Degrees Not Examined 133.90'xplanation of Exaninatfon Uinitadonst No accessibility for the examinadon equipment due to the proxtmriy of the limitations referenced above.
Additional Corn(nants:
Prepared by:
Oats: ~ ~i'~t-Reviewed b
~Date:
t'/ yL Revision 1
Psge ~ Of'<
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F I
I EXAMINATION
SUMMARY
SHEET GE Nuclear Energy i
~9%93 I
PROJECT:
BROWNS FERRY NUCLEAR
'PROCEDURE -VLB2LStLLV4 REV~ FRR:~
SYSTEM:
V-WELD NO.:
CONFIGURATION: T EXAMINER:
A EXAMINER:
F EXAMINER:
Rin I
LEVEL:~t LEVEL:~
WELD TYPE:
REV~ FRR:~
REVL~ FRR:~
CIRCUMFERENTIAL LONGITUDINAL 0 OTHER DATASHEET NO.(S):.D~M1=02=93~~)5 GAL SHEET NO.(S):
During the ultrasonic examination of the above referenced weld. six (6) indications associated with IGSCCI IASCC were recorded by the "Smart 2000 system utilizing a 45'hear wave. 60'efracted longitudinal (RL) wave. and OD creeping wave search units.
The 45'hear wave search unit did record inside and outside weld crown geometry, inside surface geomeby and nonmlevant indications along with the indications referenced above.
The 60 RL search unit did record inside surface geometry. acoustic interface and nonmlevant indications along with the indications referenced above.
The OD creeping wave search unit did record non-relevant indications along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in angular units. The conversion factor for linear units is 1.81 inches per degree.
Examination Area: Examined 33 lug sets for a total area scanned of 249.5'69.3%), which was interrogated by all transducers.
15 Iug sets were not examined due to inaccessibility.
This examination was limited to the areas scanned due to obstructions from the guide pins. shroud lifting lugs, wbration instrumentation pads and core spray downcomers.
The'examination was performed from the lower side of the weld only. due to limitations from the weld orientation.
For the indication and limitation parameters see page 2. For additional details see drawings BFN<1-ROLL, indication map and the scan plan.
GE INO PENOENT REVIEW
<QS EL GE REVIEWED BY LEVEL OATE UTIUTY REVIEW PAGE'F
GE Nuclear Energy TI/A Byowns Feny Nucfear U2C8 Shroud UTPnject IFZN9 Maycn f995 Shroud Weld H-3 Indication Data Total Scan Length Examined (Degd Total Scan Length Examined (In.)
Percentage of Weld Length Examined Percentage Flawed ofExamfned Weld Length Percentage Rawect of Total Weld Length Total Rewed Length (Oeg.)
Total Flawed Length (In.)
249.50'50.97 69.31'le 3.$
4'%.48'%.84'5.98" Thickness (In.)
Circumference (In,)
Inches p<<Degree Degrees per Inch 2.00" 650.70" 1.$ 1" 0.$5 Ind.
Start End Length Length Length Oepur DepOt Depth Percent IndfcaVon Scen MulVpie No.
Oeg.
Deg.
Oeg.
In.
Trans Marin.
Trans Pos.Deg.
77yruwalf Locadon'ype Scan 1
60.87 62A1 1.$4 2.78 45s OAB 2
2$5.81 2$7.84 1.03 1.8$
60L 0.43 3
270.27 272.33 2.0$
3.72 46s.
0.72 4
331.71 334.S7 2.5$
4.$ 1 60L 1.0$
5 3S7.25337.97 0.72 1.30 45e 0.23 8
345.68 348A1 0.$3'.$ 0 45e 0.27 60L 61.81 240 1
60L 257AS 21.5 1
60L 271.$ 3 36.0 1
60L
'333.04
$4.0 1
45e 337.7811.5 1
60L 34ILBO 13.5 1
Y.
N N
N N
N Indtcadon Commenter
'n reference to the weid
- Through wall dimension on indication ¹ 4 was determined trom the tip signai response which exhibited the most through wall dimension.
However, due to the outside surface weld crown geometry the fu$ echo dynamic pattern from the tip signal response couid not be achieved and should be consxiered a best effort sizing estimation.
>> indication ¹'s 1, 3 and 4. were recorded during the U2C7 examina5on.
>> indication ¹'s 2 and 6 areas. were not examined during the U2C7 ISI.
>> Upon review of U2C7 data, indication ¹ 5 was recorded. but not repoted. at approximateiy the same parameters as referenced above.
>> Indicadon depth is measured from initiation surface. either I.O. or 0.0.. as applicable.
Indication length as noted in inches refers to 0.0. measurements.
regardless ot whether the indication is I.O. or O.O..
4 Areas ffotExamined by All3 Transducers (Azbnuth References Jl ExanfnaVon UrnltsVonsl 0.00'o 'L10'or '.
10'6ILSO to 257.00'or 90.70 34ILSO'o 350.00'or 13.70 Total Degrees Not Examined,f10.$ 0 Guide Pin Lu. Core Spra Downcomer. Guide Pin and Vibe Lu s.
L
. Core Spra Downcomer and Guide Pin.
ExpfanaVon of Exanbtscfon UnrItadonsr No accessibility forthe examination ecpipment due to the proximity ot the limitations referenced above.
Addlttonal Comm<<rtsr
>> Due to the individual transducer offsets within the Tri-modal Search Unit, indications ¹ 2 and 6 extended into the area referenced above as 'Not examined by ail three transducers'.
Prepared by:
Date: ~Y.
-54 Reviewed by:
MJK BFN2DATA.XLS 4IBI96 07:56 Revision 3 Page 0
5 bi
<Qi II
TF F
EXAMINATION
SUMMARY
SHEET: "
GE Nuclear Energy; I
PROJECT:
BROWNS FERRY NUCLEAR PRDDEDURE:~LEEELEDm REV; D
FRR,~
SYSTEM:
PV-WELD NO.'ONFIGURATION:
EXAMINER:.wa EXAMINER:
EXAMINER:
LEVEL:~
LEVEL:~
WELD TYPE:
REEL:. EEA FRR;~
REV:~ FRR:~
MT PT OUT CIRCUMFERENTIAL LONGITUDINAL 0 OTHER DATASHEET NO.(S): DSELMm~EES~
GAL SHEET NO.(S):
Ouring the ultrasonic examination of the above referenced weld. six (6) indications associated with IGSCC I IASCC were recorded by the "Smart 2000" system utilizing a 45'hear wave. 60'efracted long)tudinal (RL) wave. and OD creeping wave search units.
The 45'hear wave search unit did record inside and outside weld crown geometry and non-relevant indications along with the indications referenced above.
The 60'L search unit did record inside surface geometry, weld discontinuities and nonmlevant indications along with the indications referenced above.
The 00 creeping wave search unit did record non-relevant indications and weld discontinu)ties along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in angular units. The conversion factor for linear units is 1.61 inches per degree.
Examination Area: Examined 33 lug sets for a total area scanned of 236.9'65.61%), which was interragated by all transducers.
15 lug sets were not examined due to inaccessibility.
This examination was limited to the areas scanned due to abstructions fram the guide pins, shroud lifting lugs, wbration instrumentation pads and lines. riser brace and core spray dovmcomers.
The examination was performed from the upper side of the weld only. due to lim(tations from the weld orientation.
For the indication and limitation parameters see page 2. Far additional details see drawings BFN41-ROLL. indication map and the scan plan.
P.u.n LEVEL DATE E
GE REVIEWED 8Y
'EVEL DATE GEI DE NDENTR tjTIUTY REVIEW D TK DATE PAGE j Os '
II
I GE Nuclear Energy Browns Ferry Nuc/ear v2cd shroud UT pro/ect IFZN9 Marcn /995 Shroud Weld H-5 Indication Data Total Scan Length Examined (Deg.)
Tata/ Scan Lengtri Examined (In.)
Percentage of Weld Length Examined Percentage Flawed ofExam/ned Weld Length Percentage Flawed of Total Wold Length Total Flawed Lengtrr (Deg.)
Total Flawed Length (In.)
238.90'28.20" 65.State 2.06'4 1.36'%.88'.82" Thickness (In.)
Circumference (In.)
Inches per Degree Degrees per Inch 2.00" 660.70" 1.81" 0.56'nd.
Start End Length Length Length Depth Depth Depth Percent Ind/cat/on Scan Multiple Ho.
Deg.
Deg.
Deg.
In.
Tram Max./n.
Trans PoaDeg.
77iruwa/I Location'ype Scan 1
2 3
4 5
6 73AB 74.68 103.97 105.09 105.80 106.20 155.1d 155.97 338.70 339.51 340.73 341.24 1.22 2.21 45a 0.90 1.12 2.02 45a 1.01 OAO 0.72 4SO c0.20 0.82 1AS 4SO 0.78 0.81 1 AS 46s ca.20 0.51 0.92 45e c0.20 60L 73.88 6OL 104.67 SOL 10d.99 60L 15dAS 46e 339.1$
45e 341.03 46.0 50.8 c10.0 39.0 c10.0 c10.0 Upper/IO Upper/ID Upper/ID Upper/ID Upper/ID Upper/ID N
N N
N N
N Indication Commenter ln fofefoilco ta Iho weld
- Through wall dimension on indication 6 2 was determined from the tip signal response which exhibited the mast through wall dimension.
However. due to the outside surface weld crown geometry the full echo dynamic pattern from the tip signal response cauld not be achieved and should be considered a best effort sizing estimation.
>> Indication 8's 1 through B. were roconled during the U2C7 examination.
b Indication depth is measured from initiation surface. either I.O. or 0.0.. as applicable.
Indicadon length as noted in inches refers to 0.0. measurements.
regardless ofwhether the indication is I.O. or 0.0..
Areas Hot Examined by All3 Transducera (Azimuth References)r Examination LImitat/oner 144 00'dd.30 to Io Io Io d.10'or 147.50'or 26IL10 for 360.00'or 6.10 13.70e Guide Pin Scanner Arm I Riser Brace Lifti Lu
. Core Spra Oowncomor. Guide Pin. Vibe Lu s and Vibe Uncs.
Lifti Lu
. Core Spra Oowncomor and Guide Pin.
Total Degrees Not Examined f23.50 Explanauon ofExanlnatfon Limitational No accessibility Ibr the examination equipment due to the proximity of the limitations referenced above.
Additions/ Commentar None Prepared dy:
~ H Oats: ~F'Y 4 Reviewed by:
MJK BFN20ATA.XLS 4/9/9B 10:25 Revision 3 Page
il J
GE Nuclear Energy EXAMINATION
SUMMARY
SHEET REPORT NO.:
PROJECT:
BROWNS FERRY NUCLEAR PROCEDURE'YSTEM:
REV~ FRR:~
WELD NO,:
CONFIGURATION:
EXAMINER'XAMINER'XAMINER:
LEVEL:~
LEVEL:~
LEVEL:~
WELD TYPE:
REV~ FRR:~
CIRCUMFERENTIAL LONGITUDINAL 0 OTHER DATASHEET NO,(S):.-
GAL SHEET. NO.(S):
During the ultrasonic examination of the above referenced weld. thirteen (13) indications associated with IGSCC were recorded by the Smart 2000 system uulizing a 45 shear wave. 60'efracted longitudinal (RL) wave, and OD creeping wave search units.
The 45'shear wave search unit did record inside and outside weld crown geometry, inside surface geometry and norwelevant indications along with the indications referenced above.
The 60'L search unit did record inside surface geometry, inside weld crown geometry, acoustic interface and norwelevant indications along with the indications referenced above.
The OD creeping wave search unit did record no~levant indications along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in angular units. The conversion factor for linear units is 1.75 inches per degree.
Examination Area: Examined 33 lug sets for a total area scanned of 243.5'67.6444), which was interrogated by all transducers.
15 lug sets were not examined due to inaccessibility.
This examination was limited to the areas scanned due to obstructions from the guide pins, shroud lifting lugs, vibration instrumentation pads and lines, and core spray downcomers.
The examination was performed from the lower side of the weld only, due to limitations from the weld orientation.
For the indication and limitation parameters see page 2. For additional details see drawings BFN41-ROLL, indication map and the scan plan.
.&24 LEVEL DATE
~~8-e.l E REVIEWED BY LEVEL DATE GEIN EPEND REVI I
(tC PAGE~ OF'
~'w 4 ~ ~ ~ F
ig t
GE Nuclear Energy TVA Biowns Fsny Nuc!ear t)2cd shroud UTpnj ect 1FZN9 Match 1995 Shroud Weld 8-6 Indication Data Total Scan Length Examined (Deg.)
Total Scan Length Exalnlned (In.)
Percentage of Weld Length Examined Percentage Rewed ofExamined Weld Length Percentage Hewed of Total Wehf Length Total Rewed Length(Degi Total Rewed Length (In.)
243 60 42LSS 67.64'%.12%
6.4'9.78 34.66" Thlckne4ts (ln.)
CIrcumference (In.)
Inches per Degree Degrees per Inch 1.76" 0.$7 lnd.
SQrt
&d Length Length Length Depth Depth Depth Percent Indlcatfon Scan M~P<e I(o Deg Deg Deg ln Trans ltfaxIn.
Trans Pos Deg.
7)trutNaII Locatfon'ppe S~
1 89.07 90.07 1.00 2
93.00 9$.3$
2.3$
3 96.89100.68 4.7$
4 10437 tOIL87 1.60 d
11L77 120M 1.$0 6
265.5$
2S5.79 1.20 7
275.72 277M 1.88 8
279.32 1SLSS 1.34 291 03 29@28 1.23 10 29472 294.92 OM 301.11 301.73 0.62 12 30%28 30IL8$
0.51 13 341.17 34282 1.$5 1.7d 46e 0.73 4.1$
45e 0.94 8.3960 L 1.07 2.$3 46e 0.85 2.80 45e 0.77 2.10 60L 0.$$
289 60L OA1 K3I SOL 0.$$
2.15 60L 0.$2 OM 45e
<OM 1.0$
60L OM t.07 45e
~0.20 2.8$
60L 0.52 60L 60L 60L 60L 60L 60L 60L SOL SOL 45e 60L 45@
60L 8$.57 3d.d 94.1947.0 99.08 53.d 104.87 42.d 11$.37 3LS 26400 2$.d 27LSl 2LS 28L14 34K 291.54 314 2$iJC ctLO 301.73 1Ld
- 308AS,
<1LO 34t.89 31.0 LowetflD Lowed\\ D LowetflD LowerhD LowethD LowethD LowerhD LowerhD LowetflD LowerhD LowentD LowerhD LowethD N
N N
N N
N H
N N
N N
H N
Intffcaffon Commenter
'n reference to tt:e weld
- Through wall dimension on indicathn ¹ 3 was determined from the tip signai response which exhibited the most through wall dimension.
However, due to the outskfe surface wekl crown geometry the tuil echo dynam'attern from the Up signal tesponsi coukl not be achieved and aheAd be considered a beat effort stzktg estkttNon.
>> Indication depth is measured from inNatkxt surface, either I O. or 0 O., as appdcable.
Indicadon length as noted kt inches refers to O.O. measurements.
ragatdktsa ofwhether the indhatkw is I.O. or O.O..
Areas ffotExaminecf by AN3 Tlansducae (Azfmuth References)I LIO Io 5.10'or d.f0'uxie Pin fSMO'o 283.00'or 95.70'i L, Core Sp Oowncomer, Guide Pin. Vibe L s snd Vibe ere Io 350.00 for 13.TO Li '
. Core Spra Oowncomer and Guide Pin.
Total Degrees Not Exanuned 1 1d.dO Explanadon ofExamlnadon Llmltadonsl
>> No accessibility for the examination equipment due to the proximity of the dmitations referenced above.
Addfffonal Comments:
>> Oue to a rough surface condidon at eight locations from 50.36'o 158.1S
. which totaled 12.4', only unktkectlonal coverage was, obtained in these areas.
The individual areas are noted on the shroud data sheets.
No indicadons were undetected due to tms ttott Prepared by:
Date:g 7~
Revtewedby:
Paae X:I.'F
ii 0
GE Nuclear Energy EXAMINATlON
SUMMARY
SHEET REPORT NO.:
~86 PROJECT:
BROWNS FERRY NUCLEAR PROCEDURE'RV~
FRR:~
SYSTEM:
RRV~ FRR:~
WELD NO.:
CONFIGURATION:
I EXAMINER'XAMINER'XAMINER:
LEVEL:~
LEVEL:~EH LEVEL:~
WELD TYPE:
RRV~ FRR~
CIRCUMFERENTIAL LONGITUDINAL ilOTHER DATASHEET NO.(S):
CALSHEET NO.(S):
Ouring the ultrasonic examination of the above referenced weld, twanty-six (26) indications associated with IGSCC ware recorded by the "Smart 2000 system uulizing a 45'hear wave. 60'efracted longitudinal (RL) wave. and OD creeping wave search units.
The 45'hear wave search unit did record inside weld crown geometry, outside surface geometry and non~levant indications along with the indications referenced above.
The 60'L search unit did record insxfe surface geometry, inside weld crown geometry, acoustic interface and norwelevant indications along with the indications referenced above.
The OD creeping wave search unit did record nonmlevant indications along with shear component to the indications referenced above.
Circumferential (L) dimensions were recorded in anguLar units. The conversion factor for linear units is 1.75 inches par degree.
Examination Area: Examined 33 lug sets for a total area scanned of 231.70'64.36%), which was interrogated by all transducers.
15 lug sets
- were not examined due to inaccessibility.
This examination was limited to the areas scanned due to obstructions from the guide pins, shroud lifting lugs, vibration instrumentation pads and lines, jat pump instrumentation line brackets, and core spray downcomers.
For the indication and limitation parameters see page 2. For additional details see drawings BFN41-ROLI indication map and the scan plan.
LEVEL DATE GE RENEWED BY LEVEL OATK GE WDEPEfr REVIEW 0 TE OATK UTIUTY REVIEW PAGE'F'~
ii
GE Nuclear EnergY TVA Browns Feny Nudear t/2C8 Shroud VTeject /FZIV9 March 1996 Shroud Weld H-7 Indication Data Total Scan Length &amined (Deg.)
Total Scan Length Eram/ned (In.)
Percentage of Weld Lengdr Exam/nod Percentage Flawed ofExam/ned Weld Length Percentage Flawed of Total Web/Length Tots/F/awed Lengdr (Deg.)
Total Flawed Lengdr (ln.)
231.70'0L91" 6436 lo 16.17%
1OA1%
37AS'5.S3" TTrlcturass (ln.)
Circumference (In.)
Inches per Degree Degrees per Inch 2.00" 630.67" 1.75" 0.5T Ind.
Ho.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 15 17 18 19 20 21 22 23 24 25 25 Start Dey.
SAO 12.31 19.50 22.78 27.94 30.10 32.75 41.59 48AS 5L31 71.19 TS.OO 81.74 85.10 92.82 28472 26L27 269.88 27L17 279.81 29L32 310.82 314.88 32L31 327.72 333.52 Encl Dey.
6.75 13A4 20.22 23.60 2L97 3082 33AS 43.35 51.S5 5LOS 73.24 TLSS 82AS 8*$1 94.95 26L34 26L88 271.10 2T5.ST 28M2 30MO 311.54 31L10 32145 32LS2 33454 Lengdr Length Dey.
In.
1.35 2.37 1.13 1.98 0.72 1.24 0.82 1A4 1.05 1.80 0.72 1.2$
1.15 1.9$
1.9$
3AS 3.59 5.94 1.75 3.07 2.05 3.59 0.9S 1.65 0.72 1.2$
0.51 0.8$
2.13 3.73 1.82 L84 0.81 1.07 1A2 2AS OAO 0.70 0.$1 1A2 6A$
11.55 1.02 1.79 1.22 2.14 1.22 2.14 LSO 1.05 1.72 3.01 Depth Marin.
OAS 0.54
<<0.20
<<0.20 0.22
<<0.20
<0.20 0.75 O.TS 0.59 0.55 OAO
<<0.20
<0.20 0.35 OAS 0.10 0.3$
<<OW
<<OW 0.9$
0.57 0.54 OA1 0.22 OAS 60L 60L 45a 60L BOL 45o 45a SOL 60L BOL BOL BOL 45e BOL SOL SOL BOL SOL 45o
- 60L, SOL SOL SOL SOL SOL 60L 6.01 13.11 19.91 23.50 28.15 30A1 33.0$
42,00 51 05 54.11 TL51 74.85 S2.17 83.19 94.$4 25L32 26LSS 270.80 27L27 280M 29980 311.33 31L3$
321.02 32L01 334 22 23.0 27.0
<10.0
<<10.0 11.0
<10.0
<<10.0 3LS 38.0 294 3LS 2tLO'10,0
<10.0 17.5 23.0 LO 19.0
<10.0
<10.0 4LO 280.5 11.0 22.5 Upper/IO Upper/ID Upper/ID Upper/ID Upper/IO UpporfIO Upper/ID Upper/ID Upper/IO Upper/ID Upper/ID Upper/IO Upper/IO Upper/ID Upper/ID Upper/ID Upper/ID Upper/IO Upper/ID Upper/ID UpporfIO Upper/IO Upper/ID Upper/IO Upper/ID Upper/IO Depth Percent Indlcatfon Pos.Deg.
Thrvwell Locadon 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
-1 1
1 1
1 N
N N
N N
N N
N N
N N
Y N
N N
N N
N N
N Y
N N
N N
N Scan hfultfple Type Scen Indlcadon Commonr In reference to the weld i Indication depth is measured fram inidadon surface. either I.O. or O.O., as applicable. Indlcatke length as noted n in s re I
inches re/ers to O.O. measurements, regardless ofwhether Ihe indication is I.O. or O.O..
Paae Z
i).
i5
Areas /for Examined by All3 Transducers (AzfmrftfrReferences/r Exammedon Vmrtadons.
0.00'9~
16tL30'o to to 6.10 107.00'64.00 for for 6.10 T.
TO'T.TO Guide Pin Jet pump instrumentation line Liftin Lu
. Core Sora Oowncomer.GuidePin. VibeL'u sand Vibe Line 31/L30 to 331DO'o 320.00'or
/or 3.70'.TO'et oumo instrumentation line Jet oumo instrumentation tine 346.30'o 360.00 13.70'iftin Lu
. Core Sora Oowncomer and Guide Pin.
Total Oegrees Not Examfned 130.60'xpleneoon of Examine tfon Vmftadonsr
~ No accessibility for the examination equipment due to the proximity of the limitations referenced above.
Add/tfonel Comments:
~ The above examinations were performed from the upper plate side only.
~ The lower plate was examined from 6.1 - 46.3'esulting in no reportable indications.
~ Oue to the individual transducer offsets within the Tri-modal Search Unit. indication 9 1 extended into the area referenced above as 'Not examined by all three transducers'.
Prepared by:
I Data: di/-i Reviewed b MJK BFN2DATA.XLS 4/11/96 07:16 Revision 1
page
(Qi