ML100570413
| ML100570413 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/24/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100570413 (31) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 February 24, 2010 10 CFR 50.4 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Facility Operating License No. DPR-52 NRC Docket No. 50-260
Subject:
American Society of Mechanical Engineers, Section Xl, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-1S1-18, Revision 2
Reference:
Letter from the Tennessee Valley Authority to the Nuclear Regulatory Commission, "American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 15 Operation," dated September 21, 2009 As identified in the reference letter and in accordance with 10 CFR 50.55a(g)(5)(iii), the Tennessee Valley Authority (TVA) is requesting relief from certain inservice inspection (ISI) requirements in Section Xl of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code. The need for this request for relief was identified during ISI examinations completed during the BFN Unit 2, Cycle 15 refueling outage which is the first refueling outage in the third period of the Third Ten-Year Inservice Inspection (ISI)
Interval. One remaining refueling outage, Cycle 16, is planned for the Third ISI Interval.
TVA has determined that three BFN Unit 2 welds had nondestructive examination (NDE) coverage limitations (less than 90 percent coverage completed) which exceed that specified in ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1."
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 February 24, 2010 These three welds are within the scope of the BFN Unit 2 Risk-Informed ISI Program. The welds are Category R-A (Westinghouse Owners Group (WOG) WCAP-14572, Revision 1-NP-A) Class 1 piping welds. These weld examinations had calculated NDE examination coverage of 50 percent. The welds received greater than 90 percent examination coverage per the requirements of ASME Section XI. However, 10 CFR 50.55a(b)(2)(xv)(A)(2) restricts taking credit for "one-sided" examinations without completing a single-sided ASME Section Xl, Appendix VIII demonstration, using flaws on the opposite side of the weld. At the time of the examinations, no Performance Demonstration Initiative (PDI) Program existed for single-side austenitic stainless steel welds.
Consequently, the percent examination of coverage achieved for each of the three welds was 50 percent. The enclosure to this letter contains BFN Unit 2 request for relief, 2-1S1-1 8, Revision 2, which addresses the examination coverage limitations for the three welds described above.
This request for relief is consistent with 2-1S1-1 8, Revision 0 (Unit 2 Cycle 12 weld examinations) submitted by TVA letters dated June 2, 2003 and December 16, 2003 and 2-1S1-1 8, Revision 1 (Unit 2 Cycles 13 and 14 examinations) submitted by TVA letter dated July 29, 2008. TVA's requests were approved by NRC as documented in safety evaluations dated April 12, 2004, and June 16, 2009 respectively.
TVA seeks review of this request for relief by January 3, 2011, to support resource planning for the Unit 2, Cycle 16 (Spring 2011) refueling outage.
There are no new regulatory commitments in this letter. If you have any questions, please contact Dan Green at (423) 751-8423.
Respectfully, R. M. Krich Vice President Nuclear Licensing
Enclosure:
Browns Ferry Nuclear Plant, Unit 2, Request for Relief 2-1S1-18, Revision 2 cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 2 American Society of Mechanical Engineers,Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval Request for Relief 2-1S1-18, Revision 2 Executive Summary:
The Tennessee Valley Authority (TVA) is requesting relief for two Reactor Recirculation (RECIRC) System full penetration piping welds, and one Reactor Water Cleanup (RWCU)
System full penetration piping weld examined during the Browns Ferry Nuclear Plant (BFN)
Unit 2 Cycle 15 which is the first refueling outage in the third period of the Third Ten-Year Inservice Inspection (ISI) interval.
The subject welds were examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, as required by 10 CFR 50.55a(g)(4).
Under the American Society of Mechanical Engineers (ASME)Section XI Code requirements, ultrasonic testing (UT) coverage attained was essentially 100 percent.
However, credit for the single side access ultrasonic examination of RECIRC welds GR-2-22, GR-2-35, and Reactor Water Cleanup (RWCU) weld RWCU-2-003-025 provided 50 percent coverage, because of the requirement mandated in 10 CFR 50.55a(b)(2)(xv)(A)(2), which states in part, "Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaws on the opposite side of the weld." At the time of these BFN Unit 2 weld examinations, there was no ASME Section Xl Appendix VIII Program for single sided austenitic stainless steel welds.
The performance of the ultrasonic examination of the subject areas to the maximum extent practical provides an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the piping welds. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA is requesting that relief be granted for the BFN Unit 2 third ten-year inspection interval.
This request for relief is consistent with request for relief 2-1S1-1 8, Revision 0 (BFN Unit 2 Cycle 12 weld examinations) submitted by TVA letters dated June 2, 2003, and December 16, 2003, and request for relief 2-1S1-18, Revision 1 (BFN Unit 2 Cycles 13 and 14 weld examinations) submitted by TVA letter dated July 29, 2008. These TVA requests for relief were approved by NRC as documented in safety evaluations dated April 12, 2004, and June 16, 2009 respectively.
E-1
Unit: Browns Ferry Nuclear Plant, Unit 2 ISI Interval: ASME Section Xl, Third Ten-Year ISI Inspection Interval (May 25, 2001 to May 24, 2011)
Systems: Reactor Recirculation (RECIRC) System and Reactor Water Cleanup (RWCU)
System Components: 3 Full Penetration Piping Welds Listed below and in Table 1 of this Enclosure.
ASME Code Class: ASME Code Class 1 ASME Section Xl Code Edition: 1995 Edition, 1996 Addenda Code Table: Code Case N-577, N-577-2500 Table I Examination Category: R-A, Risk-Informed Piping Examinations Examination Item Number: R1.16, Elements Subject to Intergranular Stress Corrosion Cracking (IGSCC)
Code Requirement: The BFN Unit 2 Risk-Informed ISI Program, Code Case N-577, N-577-2500 Table I, Examination Category R1. 16, Requires Volumetric Examination of 100 percent of the Weld and Adjacent Base Material as depicted in Figure IWB-2500-8(c).
List of Items Associated with the Request for Relief:
Weld RWCU-2-003-025 - Pipe (SA 376, TP 316 NG, S.S.) to Valve (SA351, CF8M, S.S.)
Weld GR-2 Pipe Saddle (A403, WP304 S.S.) to Pipe (A358, TP304 S.S.)
Weld GR-2 Pipe Saddle (A403, WP304 S.S.) to Pipe (A358, TP 304 S.S.)
Basis for Request for Relief: It is not possible to achieve the required volumetric examination due to single side access. Because of the requirement in 10 CFR 50.55a(b)(2)(xv)(A)(2), which in part states,-"Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaws on the opposite side of the weld." Only 50 percent coverage for welds GR-2-22, GR-2-35, and RWCU-2-003-025 can be claimed. At the time of the examinations, there was no ASME Section Xl Appendix VIII Program for single-sided austenitic stainless steel welds.
The performance of the ultrasonic examination of the subject areas to the maximum extent practical provides an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the piping welds. Table 1 of this enclosure provides a detailed description of the limitations for each weld examination listed above.
E-2
Alternative Examination: None. In lieu of the ASME Code required essentially 100 percent volume ultrasonic examination, TVA proposes an ultrasonic examination of the accessible areas to the maximum extent practical given the component design and configuration of the aforementioned piping welds.
Justification for the Granting of Relief: The welds were examined with the latest ultrasonic techniques, procedures, equipment, and personnel qualified to the requirements of the Performance Demonstration Initiative (PDI) Program, as required by 10 CFR 50.55a(g)(4).
An ultrasonic examination was performed on the piping welds to the maximum extent practical due to the configuration. Credit for the one-sided examination of GR-2-22 and GR-2-35 and RWCU 2-003-025 provided 50 percent coverage because of the requirement in 10 CFR 50.55a(b)(2)(xv)(A)(2), which states in part, "Where examination from both sides is not possible on austenitic stainless steel welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaws on the opposite side of the weld." At time of the examination, there was no ASME Section XI Appendix VIII Program for single sided austenitic welds. Under the original ASME Section Xl Code requirements, UT coverage attained was essentiallylOO percent.
The performance of the ultrasonic examination of the subject areas to the maximum extent practical provides an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the piping welds.
Welds associated with Request for Relief 2-1S1-18, Revision 2, are as follows.
Weld Examination Report Cycle Examined RWCU-2-003-025 R-074 15 GR-2-22 R-026 15 GR-2-35 R-047 15 Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), TVA requests that relief be granted for the Third Ten-Year ISI inspection interval for the above listed welds.
Implementation Schedule: This request for relief is applicable to the BFN Unit 2 Third Ten-Year ISI inspection interval (May 25, 2001 to May 24, 2011). The Reactor Recirculation (RECIRC) System welds and the Reactor Water Cleanup (RWCU) System weld listed in Table 1 of this enclosure were examined during the first refueling outage, Cycle 15, of the third period of the Third Ten-Year ISI inspection interval.
E-3
Precedents:
The NRC has approved two similar requests for BFN Unit 2 during the third ten-year interval. Request for relief 2-ISI-18, Revision 0 (BFN Unit 2 Cycle 12 weld examinations) was submitted by TVA letters dated June 2, 2003 and December 16, 2003. NRC approved the TVA request for relief by letter dated April 12, 2004 (ADAMS Accession No. ML041040375). Request for relief 2-1S1-18, Revision 1 (BFN Unit 2 Cycles 13 and 14 weld examinations) was submitted by TVA letter dated July 29, 2008. NRC approved the TVA request for relief by letter dated June 16, 2009 (ADAMS Accession No. ML091200040).
Reference:
TVA Nuclear Power Group, Nondestructive Examination procedure, N-GP-31, "Calculation of ASME Code Coverage for Section Xl, Appendix VIII Ultrasonic Examinations" Attachments:
Attachment A 3 ISI Sketches:
2-ISI-0272-C, Sheet 1 2-ISI-0270-C, Sheet 1 2-ISI-0270-C, Sheet 2 Attachment B:
Three Nondestructive Examination Reports:
R-026 R-047 R-074 E-4
TABLE 1 WELD NPS ISI PERCENT REMARKS NUMBER DRAWING EXAMINED RWCU-2-003-025 6"
2-1SI-0272-C, 50%
Limitation due to the pipe to valve Sheet 1 joint configuration. Weld contour (Reactor Water prevented scanning on the weld Cleanup System) surface in the axial direction to achieve full interrogation of the required examination volume. This weld was examined using PDI qualified personnel, procedures and equipment.
GR-2-22 12" 2-1SI-0270-C, 50%
Limitation due to saddle to pipe Sheet 1 component configuration (Reactor and the requirement in Recirculation 10 CFR 50.55a(b)(2)(xv)(A)(2),
System) which requires UT of one side of austenitic stainless steel welds to be qualified to ASME Section X1 Appendix VIII Program to claim full Code coverage. At the time of the examination, there was no ASME Section Xl Appendix VIII Program for single sided austenitic welds.
GR-2-35 12" 2-1SI-0270-C, 50%
Limitation due to saddle to pipe Sheet 2 component configuration (Reactor and the requirement in Recirculation 10 CFR 50.55a(b)(2)(xv)(A)(2),
System) which requires UT of one side of austenitic stainless steel welds to be qualified to ASME Section Xl Appendix VIII Program to claim full Code coverage. At the time of the examination, there was no ASME Section Xl Appendix VIII Program for single sided austenitic welds.
E-5
ATTACHMENT A ISI SKETCHES 2-ISI-0272-C, Sheet 1 2-ISI-0270-C, Sheet 1 2-ISl-0270-C, Sheet 2
C 0
0 RWCU-2-003-GO02 C-,Y C-oRffC-2-078 1-DRWC-.2-07A REGION OF THERMAL FA TIGUE EXAMINAT ION PER NUREG-0619 THERMAL TEE (UPSTREAM OF VALVE
. 2-FCV-69-630)
\\RCROS-2-45 RCRDS-2-0.3 RCRD-2-44 REFERENCE DRAWIi:,S CR0-2-005 RCrC-2-004 Mk j
-'17 NOTE:
rHIS DRAWINa SUPERSEDES CH1-2075-C AND HM-2072 -C (ALL SHEETS)
RCR.VS-2--OJ-TEE-A THERAS4L TEE
- 7 MATERIAL SPECIFICA TIONS STAINLESS STEEL FITTINGS 6-SA403 WP3II6NG SC/.
80 SS PIPING 6'
SA376 TP316NC SCH. 80 55 6' A376GR TP304 SCH.
80 S5 6"
A312GR TP304 SCH.
80 A-333. CRI (SEAIMLESS)
CS 6' X 0.562" NOU WALL SCH. 120 CS 8" K 0.583" NOM WALL SOH. 100 CS 2-9--630 SA351 CF8M SS ROD CAP 4" X 0.674' NOI WALL 55
- f, SRWC-2-06 CARBON STEEL..
I STAINLESS STEEL D'SRWC-2-05 (OL)
DOSRWC-2-04 (OL)
T 0~SRWC-2-03 (CL)
TRI DSP0 0G2-S5, 3
Oý T
'G0.. 9,0 00 D SRWC-2-01
,-OKOE RWCU-2-003~-O37 OR AC-2-1Al 15, 20 I
R14 061025 105---._
RISK INFORMED FELD
[V001 ACV!IJ Ji Kneio.
ppm gC 9/7
ý BROWNS FERRY NUCLEAR PLANT UNIT 2 REACTOR lrATER§E P
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2-isr-0272-CINN.
--*T i 1
I ALL A/D HISTORY RESEARCHED AT ROOD I ICA ANAIINE07D 01N DRAWIN
REFERENCE DRAWINGS:
2-47W2408-8.9 (S.E. RE.:
.IAENT)
CE 769E963 (S.E. REPLA,
ýiT)
TVA 47KI544-2 CE 2-15JF754 KELLOGG BE 2-160 NOTE: THIS DRAWING SUPERSEDES CHM-2068-C ALL SHEETS MATERIAL SPECIFICATIONS:
A358.
TP 304 4" X 0.337" NOM WALL THK. (SS) 12" X 0.569" NOM. WALL TH.K (55) 22" X 1.030" NOM. WALL THK. (SS) 28" X 1.138" NOM. WALL THK. (SS) SUCTIO, 28" X 1.322" NOM. WALL THK, (SS) DISCHARGE 2J SCH. 60 A-376, TP304 2' FITTINGS A-182, F304 SAFE END REPLACEMENT 12" X 0.688 NOM. WALL THK. (SS)
SA 40J WP 316 N.C.
ASME CC-I (EQUIVALENT) 2RXI
.. ;:"f2X 2R~t-RX RPV-L
,ii R / E T A l I 0 +,
2 R X 5 RISER DETAIL l
WELDS 2RXI ARE THE NOZZLE TO SAFE-END WELDS ALL 2" WELDS ARE SOCKET WELDED EXCEPT WHERE NOTED.
PIPE SEGMENTS CONTAINING TWO LONGITUDINAL SEAMS WILL BE IDENTIFIED AS:
(BASE WELD NO.)-LS-ID (DOWNSTREAM)
(BASE WELD NO.)-LS-2D (DOWNSTREAM)
(BASE WELD NO.)-LS-IU (UPSTREAM)
(BASE WELD NO.)-LS-2U (UPSTREAM)
THE -LS-I SEAM WILL BE NUMERICALLY CLOSEST TO O ON THE PIPE. AND THE -LS-2 SEAM WILL BE NUMERICALLY FARTHERMOST FROM 0" ON THE PIPE.
({eg. -LS-I AT 130",
AND -LS-2 AT 310*)
PIPE SEGMENTS CONTAINING ONLY ONE LONGITUDINAL SEAM WILL BE IDENTIFIED AS (BASE WELD NO.)-LS-D (DOWNSTREAM)
(BASE WELD NO.)-LS-U (UPSTREAM)
- r l RISK IMFORMED WELDS XR-N-N 2R I
"..ELD0 ND.
r K = KEL LOGC SHOP WELOD UNIT ND.
C -
SYS TEM SYS TEM 005 1 AMIN I RD LEMSM I kli.
I f 4 REVISEO PER OLINSI 10 140 DI 21200 00 05 1I'ENNESSEE VALLEY AUTHORlIT BROWNS FERRY NUCLEAR PLANT RXN UNIT 2 WELD NO.
RECIRCULATION SYSTEM RISER 8
SA0AflO
,80 IO SEAl N LETTER ALL A/D HISTORY RESEARCHEO AT RODO jCD
REFERENCE DRAWINGS:
2-47W2408-8,9 (S.E. RE
- MENT)
CE 769E963 (S.E.
REPLAt
.*T)
TVA 47K1544-2 CE 2-153F754 KELLOGG BF 2-IS0 NOTE:
THIS DRAWING SUPERSEDES CHM-206B-C ALL SHEETS KR-2-5 0~S~
KR-2-50-L -
GR-2-60-LSE CR--67 fL 1 R-IcI,3P (DL)
N18-SE1 2RA I R6
- V24 jo
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FCV-88-31 NIB180 lV?
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CR-2-5 5
KR-233 2
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KR 8-34-S K~~
CR-?
-341 S-45(
NOE I- -.
I (A
KR-2
-25 MATERIAL SPECIFICATIONS:
A358. TP.304 4
X 0..337" NOM WALL THK. (SS) 12" X 0.569" NOM. WALL THK. (SS) 22" X 1-03O" NOM. WALL THK. (SS) 28" X I.liaS" Nom.
WALL THK. (SSJ SUCrTic 28" X 1.322. NOM. WALL THK. (SS)
DISCHARGE 2" SCH. 80, AJ76, TP304 2" FITTINGS A182.FJD4 SAFE END REPLACEMENT 12" X 0,688 NOM. WALL THK. (SS)
SA 403 WP 316 N.C.
ASNE CC-1 (EQUIVALENT)
KR
ý GR-2-61-LS-5S:
.L 2" WELDS ARE SOCKET WELDED XCEPT WHERE NOTED.
IPE SEGMENTS CONTAINING TWO LONGITUDINAL TAMS WILL RE IDENTIFIED AS.'
BASE WELD NO.)-LS-ID (DOWNSTREAM)
BASE WELD NO.)-LS-2D (DOWNSTREAM)
BASE WELD NO.)-LS-IU (UPSTREAM)
BASE WELD NO.)-LS-2U (UPSTREAM)
HE -LS-I SEAM WILL BE NUMERICALLY CLOSEST 0 0" ON THE PIPE, AND THE -LS-2 SEAM WILL BE UMERICALL t FARTHERMOST FROM O
- DN THE PIPE.
e.g.
-LS-I AT 130".
AND -LS-2 AT 310')
'(PE SEGMENTS CONTAINING ONLY ONE ONCITUDINAL SEAM FILL BE IDENTIFIED AS BASE WELD NO.)-LS-D (DOWNSTREAM)
BASE WELD NO.)-LS-U (UPSTREAM)
I RISK INFORMED WELDS
~5I,
'[KR-2-26 fCR-Z-33 F:
KR-2-24-LS-.
KR-L 2- '/
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-638 G 2_ 27 CR-?_-29-L S-II FCV-6"-77 C-2 CR-2-22729-LS-2 2-
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CR-2-2i~2 CR 3-LS~
~
FL-87 KR-2-SJ--<R V
FCV-6B-79-LIC RBC-2 CR--8 Gý R-2-64 (DL)
IC2O C--lL 4"DECONTAMINATION LIN
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KR-2-52-LS-1 C--0l--7L Z 'NKR2-52-LS-2
-KW-2-23 REVISED PER S RIC WWT R'..1202 102 REVý CHAERE itF R
I IRF t-ER E
I EC PRK E I
"ATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNI T 2 RECIRCULATION SYSTEM WELD LOCATIONS DRA E D I PPPCDeIor AIF 0
0TS CUIJl.ML0.)( EDC IGLB 6 4RR
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VIrE-S-3-fi 2
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WELD NO.
UNI T WELD NO.
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KELLOGG SHOP WELD UNIT N.J IE C
CE FIELD WELD UNIT NO.ER ST TEM SYSTEM LETTER ALL / HISTORY RESEARCHED
. ROOD i
C
ATTACHMENT B Weld Examination Reports R-074 R-026 R-047
Examination Report No. R-074 Weld No. RWCU-2-003-025
/
C 60 0261 !
TENNESSEE VALLEY EXAMINATION
SUMMARY
AUTHORITY AND REPORT NUMBER:
RESOLUTION D AT A SHEET 9'0 7*
PROJECT: BFN UNIT: 2 CYCLE: 15 COMPONENT ID: RWCU-2-003-025 EXAMINATION METHOD SYSTEM: RWCU I ISI DWG. NO. 2-ISI-0272-C-01 MTI E I PTI vT CODE CLASS: I CATEGORY: R-A PROCEDURE: N-UT-64 REV: I1I TC: N/A CONFIG.:
I Pipe TO Valve EXAMINER: Tommy Brown EXAMINER: N/A EXAMINER: N/A EXAMINER: N/A LEVEL: III LEVEL:
LEVEL:
LEVEL-
/
This report contains the data associated with the manual ultrasonic examination weld RWCU-2-003-025.
The exam was performed to meet the requirements of ASME Section X 1995 Edition 1996 Addenda, Category R-A, Item RI.16A.
This exam was performed using TVA Nuclear Procedure N-UT-64 Rev. 11 which incorporates PDI-UT 2 Rev C Addenda No. 1, 2, and 3, for UT examination Austenitic Welds..
A 450 Shear was used for the circ scans and a 45' and a 700 Shear was used for the axial scans.
No scan on the downstream side due to Pipe to Valve configuration.
50% Code Required Coverage was achieved.
RESOLUTION BY: Tommy Brown REVIEWED BY:
ANA.:
' '~
I~
UA itL:
-9/ IP7 LEVEL: III DATE: 05/111/09 LEVEL: /=DiATE:_4/77
_PG.
/
OF
000270 TE E V Y
DIGITAL ULTRASONIC TENNESSEE VALLEY CALIBRATION REPORT NUMBER:
AUTHORITY DATA SHEET k6 PROJECT: BFN UNIT 2 CYCLE: 15 CALIBRATION DATE:
05/11/09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WB -84 TEMP: 81 'F INSTIL MFG: Krautkramer DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODEL/TYPE: USN 60 M & TE NO.: E36305 THERMOMTER S/N: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: KBA MODEL: Comp-G COUPLANT Ultragell H BATCH: 06125 ELEMENTS: I SHAPE: Round S/N 00W27L SIZE:.375" FREQ 2.25 MHz EXAM TYPE:
SHEARZ LONGLI RLI--]
CONTOUR:
Flat FOCUS: N/A ANGLE VERIFICATION CONFIG:
[] D-SBS
[]D-TANDEM ED SINGLE BLOCK TYPE:Rompas
] S/N:
93-5721 CABLE TYPE: RG 174 LENGTH: 6'0
- CNT: 0 NOMINAL ANGLE: 700 J
ACTUAL ANGLE: 700 Simulator 0.5 "Notch INSTRUMENT SETTINGS 100 A
REFLECTOR REFERENCE MEMORY
\\
M SCAN DIRECT.
NTCH SDH SENSITIVITY NUMBER 80 p
AXIAL L9 I-51.0 dB RWCU-25-70 L
CIRC 0
1
[
N/A dB N/A I
RANGE: 2.0"
- INST. FREQ.: 2.25 Mhz T
PROBE DELAY: 7.1488
- RECTIFY:Fullwave 40 U
VELOCITY: 0. 1230 DUAL T] ON 0 OFF D
DISPLAY DELAY: 0.0
- REJECT: 0 20 E
- ENERGY: High
-DISPLAY START: IP 0
DAMPING: IK Q DET: []PEAKZ FLANK 0
D A C
- PRF MODE: Autohigh TCG: ONE]
OFF[
DISPLAY WIDTH: 2.0 inches REF. REFLECTOR: 0.5 Notch GAIN: 41.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 1.42 INITIAL TIME: 1227 FINAL TIME: 1350 VERIFICATION TIMES
- 1) 1305 12)N/A 13) N/A
- 4) N/A 15) N/A 16) N/A 17) N/A 18) N/A
- 19) N/A
- PDI QUAL/F][D INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK SIGNAL 1 100 90 80 70 60 50 40 30 20 10 VERTIC SIGNAL 2 50 45 40 35 30 25 20 15 10 5
GAIN SET
-6 dB
-12 dB SET
+12 SET
+6 ATENUATOR IAMP 80 32-48 16-24 20 64-96 40 64-96 40 20 80 80 COMMENTS: Maintained 10% to 20% ID roll.
WELDS/ITEMS EXAMINED: RWCU-2-003-025 EXAMINER: Tommy Brown EXAMINER: Roger Senger REVIEWER:
~
A-9-<DATE:
_X/jj7 LEVEL: III LEVEL: Trn LEVEL:
DAT;ElzZ P
OF
000271 DIGITAL ULTRASONIC TENNESSEE VALLEY CALIBRATION REPORT NUMBER:
AUTHORITY DATA SHEET
- 074-PROJECT: BFN UNIT 2 CYCLE: 15 CALIBRATION DATE:
05/11/09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WB - 84 TEMP: 81 'F INSTR. MFG: Krautkramer DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODE/ITYPE: USN 60 M & TE NO.: E36305 THERMOMTER S/N: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: KBA MODEL: Comp-G COUPLANT Ultragell II BATCH: 06125 ELEMENTS:
1 SHAPE: Round S/N 0OW40C SIZE:.375" FREQ 2.25 MHz EXAM TYPE:
SHEARZ LONGE]
RL[]
CONTOUR: Flat FOCUS: N/A ANGLE VERIFICATION CONFIG:
[I D-SBS D-TANDEM 0
SINGLE BLOCK TYPE: Rompas S/N:
93-5721 CABLE TYPE: RG 174 LENGTH: 6'0
- CNT: 0 NOMINAL ANGLE: 45*
ACTUAL ANGLE: 450 Simulator 0.5 "Notch INSTRUMENT SETTINGS 100 A
REFLECTOR REFERENCE MEMORY M
SCAN DIRECT.
NTCH SDH SENSnrrIITY NUMBER 8 0 K"*.i p
AXIAL 27.0 dB RWCU-25 L
CIRC 27.0 dB N/A 6o I
RANGE: 1.25"
- IINST. FREQ.: 2.25 Mhz T
PROBE DELAY: 4.8897
- RECTIFY:Fullwave 40 U
VELOCITY: 0. 1230 DUAL [] ON N OFF D
DISPLAY DELAY: 0.0
- REJECT: 0 20 E
- ENERGY: High
- DISPLAY START: IP
- DAMPING: 1K 0 DET: []PEAKN FLANK 0
D A C
- PRF MODE: Autohigh TCG: ONE]
OFFS DISPLAY WIDTH: 1.25 inches REF. REFLECTOR: 0.5 Notch GAIN: 27.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 0.7 INITIAL TIME: 1230 FINAL TIME: 1355 VERIFICATION TIMES
- 1) 1320 12)N/A 13) N/A
- 4) N/A
- 15) N/A 16) N/A 17) N/A 18) N/A
- 9) N/A
- PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK SIGNAL]
100 90 80 70 3 60 50 40 30 20 10 VERTICML
-SIGNAL 2
50 45 40 35 30 25 20 15 10 5
GAIN SET
-6 dB
-12 dB SET
+12 SET
+6 ATTENUATOR AMP 80 32-48 16-24 20 64-96 40 64-96 40 20 80 80 COMMENTS: Maintained 10% to 20% ID roll.
WELDS/ITEMS EXAMINED: RWCU-2-003-025 EXAMINER: Tommy Brown EXAMINER: Roger Senger REVIEWER:.
ANII: 4/
LT
/D ATE:
s.UVEL: LuI LI$VELTr LEVEL:
DATE-PG.
OF
_7 (a
- 27
.. I MANUAL ULTRASONIC TENNESSEE VALLEY PIPING EXAMIATION REPORT NUMBER:
AUTHORITY DATA SHEET
[
" ]
PROJECT: BFN UNIT: 2 CYCLE: 15 EXAMINATION DATE:
05/11/09 PROCEDURE: N-UT-64 REV: 0011 TC: N/A START TIME: 1306 END TIMIE: 1334 SYSTEM: RWCU ISI DWG. NO: 2-1SI-0272-C-01 EXAM SURFACE
[]E ID OD COMPONENT ID: RWCU-2-003-025 MATL. TYPE: [] CS ss
"]cCSCL
[]CCSS CONFIGURATION SURFACE TEMP.: 83* F PYRO. NO.: 562777 Pipe TO Valve CAL DUE DATE: 03/21/10 FLOW EXAM INATION ANGLE 45S 70S N/A Wo
REFERENCE:
CENTERLINE OF WELD CIRC. SCAN SENSmIvrry 42.0 N/A N/A Lo
REFERENCE:
Outside radius of elbow AXIAL SCAN SENSITIVUTY 42.0 55.0 N/A IND.
L (in) FROM REF.
AT MAX AMP MAX EXAM NOM.
N IND. INFO:
NO.
LI L
L2 W
MP D
AMP NO.
ANG.
R TYPE, DAMPING, MAX MAX MAX MAX
%DAC 3-14 1
ETC.
1 11.0 11.75 12.0
.5
.6 100%
3 45
[
SHEAR **
NRI 3
70
[SHEAR NRI 5
45
[SHEAR NRI 6
45
[SHEAR El 0]
El 0]
El REMARKS /LIMIATIONS: Maintained 5% to 20% ID Roll.
- Indication number 1 is root concavity verified on RT Film from Previous data report number R-315 From cycle 10.
0
n A 0721 WALL THICKNESS e
T APROFILE SHEET
.I*
PROJECT: *l WELD NO: R,,vi LU -
D.
o3 -oa.
UNIT:
SYSTEM:
w r\\~
(ot Record Thickness Meesurements As Weld
- Weld Edge Indicated, Including Weld Width, Canterline Edge-'ro-Edge At o" 0"
.6-2.S"-
Position 0"
90g 180 270I CROWN HEIGHTr: FIUS H DIAMETER:
.VIP_
P*ot* Coi4C,.i'L-
"F JSie Side M3
-/,A
./.......,I.../
EX fEVIEWED By,4-LE5VEL--*
C-I l 97A T AWALL THICKNESS REPORT No-.
PROFILE SHEET PROJECT: R F.
WELDO.
RNO /C:J UNIT:.
SYSTEM:
R W C ii Record Thickness Measurements As Weld
.2.5"-
Position
- 0.
1180.
270.
2 3
4U
-0 4/
-lP1 F
V Z
ED._., "
Side Side F1
,.48" N*
I -1 A 7_
CROWN HEIGHT: FLUS Ll DIAMETER:
6 CROWN WIDTH:
WELD LENGTH:_
piP&P MPIV6 TOf 1ro/ue..
IoL) >Me x
.,5:-15x'-
1 1, e
70-7",q/ C eracj,,
. l."/.,.t5":
o..
x 100 So V
- f.
vaalp
-6t V-LEXA" 2
Y*
REVIEWED By AN I
LVL
/
AGE DA I PAGE OF
Examination Report No. R-026 Weld No. GR-2-22
000098 TENNESSEE VALLEY EXAMINATION
SUMMARY
AUTHORITY AND REPORT NUMBER:
RESOLUTION DATA SHEET
/'-*':
PROJECT: BFN UNIT: 2 CYCLE: 15 COMPONENT ID: GR-2-22 EXAMINATION METHOD SYSTEM: Recire ISI DWG. NO. 2-ISI-0270-C-03 MT Pl LIT VT CODE CLASS: I CATEGORY: R-A PROCEDURE: N-UT-64 REV: 11 TC: N/A CONFIG.:
SDL TO PIPE EXAMINER: Tommy Brown EXAMINER: N/A EXAMINER: N/A EXAMINER: N/A LEVEL: III LEVEL:
LEVEL:
LEVEL:
This report contains the data associated with the manual ultrasonic examination weld GR-2-22.
The exam was performed to meet the requirements of NU0313, EXREQ B02-02 category C and ASME Section XI 2W Edition 2003 Addenda, Category R-A, Item RI.16C.
This exam was performed using TVA Nuclear Procedure N-UT-64 Rev. II which incorporates PDI-UT 2 Rev C Addenda No. 1, 2, and 3, for UT examination Austenitic Welds..
A 450 Shear and a 600 RL was used for the axial scans and a 45' Shear for cire scans.
50% Coverage Achieved.
RESOLUTION BY: Tommy Brown REVIEWED BY:
NI
~
DATE:
11f~
LEVEL: I[I DATE: 04/30/09 LEVFL:-Z/7DATE: ~/5>
PG.
/
OF 10
I OoOO9'~
]
~DIGIrTAL ULTRASONIC TENNESSEE VALLEY CALIBRATION REPO.ART INUMBER:
'iAUTHORITY DATA SHEET K/ I VZ1 PROJECT: BFN UNIT 2 CYCLE: 15 CALIBRATION DATE:
05/01 /09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WB - 84 TEMP: 83 'F INSTIL MFG: Kmutkramer DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODEL/TYPE: USN 60 M & TE NO.: E36305 THERMOMTER S/N: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: KBA MODEL: Comp-G COUPLANT Ultragell II BATCH: 06125 ELEMENTS:
I SHAPE: Round S/N 01FH9R SIZE: 0.5" FREQ 1.5 MHz EXAM TYPE:
SHEAR*
LONGLI RL["
CONTOUR: Flat FOCUS: N/A ANGLE VERIFICATION CONFIG:
[I D-SBS E] D-TANDEM '
SINGLE BLOCK TYPE: Rompas S/N:
93-5721 CABLE TYPE: RG 174 LENGTH: 6'0
- CNT:0 NOMINAL ANGLE: 450 ACTUAL ANGLE: 450 Simulator
- 1.
"Notch INSTRUMENT SETTINGS 100 A
REFLECTOR REFERENCE MEMORY 8
\\
M SCANDIRECl INTCH SDH SENSMVIrIY NUM[ER 80 P
_AXIAL E
21.0 dB GR-2245 60I L
CIRC 21.0 dB N/A 60 1
RANGE: 2.5"
- INST. FREQ.: 2.25 Mhz T
PROBE DELAY: 5.9912
- RECTIFY:Fullwave 40 U
VELOCITY: 0.1230 DUAL LI ON S OFF D
DISPLAY DELAY: 0.0
- REJECT: 0 20 E
- ENERGY: High
- DISPLAY START: IP D&.
- DAMPING: 1K Q DET: E]PEAK0 FLANK 0
D
- PRF MODE: Autohigh TCG:ON[]
OFFE]
DISPLAY WIDTH:
2.5 inches REF. REFLECTOR: 1.0 Notch GAIN: 21.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 1.28 INITIAL TIME: 1320 FINAL TIME: 1650 VERIFICATION TIMES 1(1510 12 )N/A
- 13) N/A
- 4) N/A
- 15) N/A 16) N/A 17) N/A 18) N/A 19) N/A
- PDI QUALIFIED INSTRUMENT SETTINGS, VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK S SIGNALI 110 1
9 1 80 1
7 1 60 1
5 1
40 1 30 1 20 1
10 vETCý SIGNAL 2 5014 0
1 3
0 5
2 5
11 ATTENUATOR*
4032-484 16-242 20 64-96840 64-960 COMIMENTS: Maintained 10% to 20% ID roll.
t WLDS TMS EXAMINED: GR-2-22 EXAMINER: Tommy Brown E
R: Roger Senger REVIEWER:
ANU 7
LEVEL:,
AE PDATE:
IE:IILEVEL:
Trn LEVEL:
DATE-PG.
OF
________2:______
j i:
ý <I a
000100 TENNESSEE VALLEY CALIBRATION REPORT NUMBER:
"' "!AUTHORITY DATA SHEET
/"O.
PROJECT: BFN UNIT 2 CYCLE: 15 CALIBRATION DATE:
05/01/09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WB - 84 TEMP: 83 'F INSTRL MFG: Krautkrarner DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODEL/TYPE: USN 60 M & TE NO.: E36305 THERMOMTER S/N: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: RTD MODEL: TRL2-Aust COUPLANT Ultragell If BATCH: 06125 ELEMENTS: 2 SHAPE: Rect S/N 99-1219 SIZE:2(8xl4)
FREQ 2.0 MHz EXAM TYPE:
SHEAR[]
LONGO-I RLo CONTOUR: Flat FOCUS: 20 FS ANGLE VERIFICATION CONFIG:
0 D-SBS 0I D-TANDEM [I SINGLE BLOCK TYPE: Rompas S/N: 93-5721 CABLE TYPE: RG (2) 174 LENGTH: 6'0
- CNT: 0 NONN 60 ACTUAL ANGLE: 60 0 Simulator 1.0 "Notch INSTRUMENT SETTINGS 100 I
I P
A REFLECTOR REFERENCE MEMORY 0
M SCAN DIRECT.
NTCH SD1-SENSITIVITY NUMBER P p AXIAL 0
68.0 dB 99-1219 L
CIRC N/A dB N/A 60
-I RANGE: 3.0"
- INST. FREQ.: 2.0 Mhz T
PROBE DELAY: 8.7925
- RECTIFY:Fullwave 40 U
VELOCITY: 0.2302 DUAL 0 ON El OFF D
DISPLAY DELAY: 0.0
- REJECT: 0 20 E
- ENERGY: High
- DISPLAY START: IP 0
- DAMPING: 1K 0 DET: 9PEAKE] FLANK 0
D A
C
- PRF MODE: Autohigh TCG: ONE]
OFFZ DISPLAY WIDTH: 3.0 inches REF. REFLECTOR-1.0 Notch GAIN: 68.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 2.0 INITIAL TIME: 1310 FINAL TIME: 1645 VERIFICATION TIMES 1)1535 12)N/A
- 13) N/A
- 4) N/A 5)NA 16) N/A
- 17) N/A 8)/A W
9)N/
PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK I SIGNAL I1 1001 90 1
80 1
0 1
60 1
50 1
40 1
30 1 20 1 10 GAIN SET
-6 dB
-12 dB SET
+12 SET
+6 ATTENUATOR AMP-80 16-24 20 64-96 1
40 64-96 40 2080 so COMMENTS: Maintained 10% to 20% ID roll.
WELDS/ITEMS EXAMINED: GR-2-22 E*XAMINER: Tummy Brown E
R: Roger Senger REVIEWER:
ANI:
DATE: rTA VE:IILEVEL:
Trn LEVEL-DATE:
PG.
OF 0
000101 MAU04A-LULTRASONIC TENNSSEE VALLEY PIPING EXAMINATION REPOAET NUSMLBER:
AUTHORITY DATA SHEET K- ~N* o PROJECT: BFN UNIT: 2 CYCLE: 15 EXAMINATION DATE:
05101N09 PROCEDURE: N-UT-64 REV: 0011 TC: N/A START TIME: 1503 END TIME: 1555 SYSTEM: Recirc I SI DWG. NO: 2-1S1-0270-C-91,0"3 EXAM SURFACE
[]ID
[]
OD COMPONENT I D: GR-2-22 My D
[P]CCSS CONFIGURATION SURFACE TEMP.: 85° F PYRO. NO.: 562777 SDL TO Pipe A
CAL-DUE DATE: 03/21/10 FLOW EXAM INATION ANGLE 45S 60RL 70S Wo
REFERENCE:
CENTERLINE OF WELD cimc. SCAN sENsmrrycr 40.0 N/A N/A Lo REFERE*NCE: Outside radius of elbow Ax[AL SCAN SENSmTVITy 40.0 70.0 N/A MN.
L (in) FROM REF.
AT MAX APMAX EXAM NOM.
N IND. INFO:
NO.
fL1l L
L2 W
UP D
AMP NO.
iANG.
R TYPE, DAMPING, M AX MAX MAX MAX
%/DAC 3-14 1
ETC.
NRI 4
45
[]SHEAR NRI 5
45
[]SHEAR N_
6 45
_SHEAR RNR 4
60 KIL ITNL MR
[
REMLARKS /LIMITATIONS:
MAINTAINED 5 TO 20% ID ROLL DURING SCANNING.
EXAMI[NER: Tommy LEVEL: in ANII:*
EXAMINER: Roger Senger /
/
"LEVEL:
Trn DATE:
L~~ ~
~
TE:Z/FDAE REVIEWER:
LIEt
?27DTE PAGER OF 5
000102 TVA IWALL THICKNESS REPORT NO:
PROFILE SHEET
,'° PROJECT: REF wELD NO: C' R -*
UNIT:
SYSTEM:.@*C Record Thickness Measurements As Weld
- Weld Edge Indicated, Including Weld Width, Centerline Edge-To-Edge At 0.
Position 1 0- o 1801r270*12r5 2l Sd/A Side
[]
.*66
[]_
, -7,
[E]
.0o
,=
Flow-CROWN HEIGHT:
07 DIAMETER: __
CROWN WIDTH:
WELD LENGTH: 38 S.L N
- PPE-V IS-T ri i4ýD vo lum&Z
-00 COVI-R1'q~
- 5o~j~ :SO0 I
0~
DATL DA&
IPAGE.
OF,
Examination Report No. R-047 Weld No. GR-2-35
000152 TENNESSEE VALLEY EXAMINATION
SUMMARY
AUTHORITY AND REPORT NUMBER:
RESOLUTION DATA SHEET R0#7t PROJECT:BFN UNIT: 2 CYCLE: 15 COMPONENT ID: GR-2-35 EXAMINATION METHOD SYST'EM: Recite ISI DWG. NO. 2-ISI-0270-C-02 MT El PT El LUT ED VT []
CODE CLASS: I CA-TEGORY-R-A PROCEDURE: N-UT-64 REV: I1 TO N/A CONFIG.:
SDL TO PIPE EXAMINER: Tommy Brown EXAMINER: N/A EXAMINER. N/A EXAMINER: N/A LEVEL: III LEVEL:
LEVEL:
LEVEL:
This report contains the data associated with the manual ultrasonic examination weld GR-2-35.
The exam was performed to meet the requirements of NU0313, EXREQ B02-02 category C and ASME Section XI 24W+ Edition 2003-Addenda, Category R-A, Item RI. 16C.
This exam was performed using TVA Nuclear Procedure N-UT-64 Rev. 11 which incorporates PDI-UT 2 Rev C Addenda No. 1, 2, and 3, for UT examination Austenitic Welds..
A 450 Shear and a 600 RL was used for the axial scans and a 450 Shear for circ scans.
50% Coverage Achieved.
RESOLUTION BY: Tommy Brown REVIEWED BY:
ANH:
E 7A009L A
</
DATE:
.ch 'qra0 LEE:m
- -LEVEL'*--0DATE-
!5-11 PG.
/OF 5
It
000153 J
~
DIGITAL ULTRASONIC T.
DC.GTENNESSEE VALLEY CALIBRATION REPORT NUMBER:
E TSAUTHORITY DATA SHEETR PROJECT: BFN UNIT 2 CYCLE: 15 CALZF 5RATION DATE:
05/04 /09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WF - 84 TENP: 83 'F INSTR. MFG: KrautD- [mer DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODELTYPE: USN 60 M & TE NO.: E36305 THERMOMTER SN: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: KBA MODEL: Comp-G COUPLANT Ultragell BATCH: 06125 ELEMENTS: I SHAPE: Round S/N 01FH9R SIM: 0.5" FREQ 1.5 MHz EXAM TYPE:
SHEAR2 LONGST']
RLQ25 CONTOUR4 Flat FOCUS: N/A ANGLE VERDUCATION CONFIG:
[3 D-SBS El D-TANDEM
[] SINGLE BLOCK TYPE: Rompas S/N:
93-5721 CABLE TYPE: RG 174 LENGTH: 6'0
- CNT: 0 NOMINAL ANGLE: 45' ACTUAL ANGLE: 45 Simulator
- 0.
ENotch INSTRUMENT SETTINGS 100 A
A REFLECTOR REFERENCE MEMORY
- /M SCAN DIRECT.
InCH SDH SENSITIVITY NUMBER 80 W
p AXIAL 21.0 d
GR-22 45 L
CIRC AI AT 21.0 dB N/A 60 1
RANGE: 2.5 0
- INST. FREQ.: 2.25 Mhz T
PROBE DELAY: 5)9912N
- RECTIFY:Fu7lwave 40 U
VELOCITY: 0.1230 DUAL El ON Z] OFF D
DISPLAY DELAY: 0.0
- REJECT: 0 20 E
- ENERGY: High
- DISPLAY START:_1P
- DAMPING: IK L1I DET.-E]_PEAK[M FLANK 0D A C
- PRF MODE: Autohih TGONj OF DISPLAY WIDTH:
2.5 inches REF. REFLECTOR: 1.0 Notch GAIN: 21.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 1.28 IM~LTM 80 FNLTfi 10 VERIFCATION TIMES 1105 2NA1)_ N/A
- 4) N/A
- 15) N/A 16) N/A 17) N/A 18) N/AI
)*/
- PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHIECK SIGNAL 100 90 801 70 60 50 40 30 20 10 VERTICA SIGNAL 2 50 145 j40 35 30 25 20 115 110 5
-6 dB
-12 dB SET
+12 SET
+6 ATTENUATOR AMP 80 32-48 16-24 20 64-96 40 64-96 40 50 80 80 COMMENTS: Maintained 10% to 20% ID roll.
WELDS/ITEMS EXAMINED: GR-2-35 EXAMINER: Tommy Brown EXAMINER: Roger Senger REVIEWER:
ANII" LEVEL: Tm LEVEL:
DATE:/
PG.
OF L:L
- //
27 0
000154
[
I DIGITAL ULTRASONIC TENNESSEE VALLEY CALIBRATION REPORT NUMBER:
~~AUTHORITY DATA SHEET
).7 PROJECT: BFN UNIT 2 CYCLE: 15 CALIBRATION DATE:
05/04/09 PROC.:
N-UT-64 REV: 11 TC:N/A CALIBRATION BLOCK NO.: WB - 84 TEMP: 83 'F INSTR. MFG: Krautkramer DUE DATE: 08/18/09 SIMULATOR BLOCK NO: 93-5721 MODELTYPE: USN 60 M & TE NO.: E36305 THERMOMTER S/N: 562777 DUE DATE: 3/21/10 TRANSDUCER MFG: RTD MODEL: TRL2-Aust COUPLANT Ultragell U1 BATCH: 06125 ELEMENTS: 2 SHAPE: Rect S/N 99-1219 SIZE:2(8x14)
FREQ 2.0 MHz EXAM TYPE:
SHEAREJ LONGO E
RL[
CONTOUR: Flat FOCUS: 20 FS ANGLE VERIFICATION CONFIG:
0 D-SBS El D-TANDEM (I SINGLE BLOCK TYPE: Rompas S/N: 93-5721 CABLE TYPE: RG (2) 174 LENGTH: 6'0
- CNT: 0 NOMINAL ANGLE: 60 ACTUAL ANGLE: 60° Simulator 1.0 "Notch INSTRUMENT SETTINGS 100 P
I A
REFLECTOR REFERENCE MEMORY
+
M SCAN DIRECT.
NTCH SDH SENSmVJTY NUMBER so-P AXIAL
]
[1 68.0 dB 99-1219 L
CIRC Li Ij N/A dB N/A 60 I
RANGE: 3.0"
- INST. FREQ.: 2.0 Mhz T
PROBE DELAY. 8.7925
- RECTIFY:Fullwave 40 U
VELOCITY: 0-2302 DUAL 10 ON OFF D
DISPLAY DELAY: 0.0
- REJECT:0 20 E
- ENERGY: High
- DISPLAY START: IP
- DAMPING: 1K Q DET: [PEAKL-FLANK 0
f D
A C
- PJRF MODE: Autohigh TCG: ONE]
OFFZ DISPLAY WIDTH: 3.0 inches REF. REFLECTOR: 1.0 Notch GAIN: 68.0 dB CALIBRATION TIMES AMPLITUDE: 80% FSH METAL PATH: 2.0 INITIAL TIME: 0830 FINAL TIME: 1128 VERIFICATION TIMES 1)0936 2 )N/A
- 13) N/A
- 4) N/A
- 5) N/A 16) N/A
- 17) N/A
- 18) N/A
- 9) N/
- PDI QUALIFIED INSTRUMENT SETTINGS:
VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!
LINEARITY CHECK SIGNAL 1 90 1
80 70 60 50 40 30 20 10 VERTICAfl SIGNAL 2 1 50 1 45 L 40 35 30 25 20 15 10 5
GAIN SET
-6 dB
-12 dB SET
+12 SET
+6 ATTENUATOR AM?
80 1
32-48 16-24 20 64-96 64-40 80 80 COMMENTS: Maintained 10% to 20% ID roll.
WELDSATEMS EXAMINED: GR-2-35 EXAMINER: Tommy Brown EXAMNER: Roger Senger
-VEL: Ill LEVEL: Trn REVIEWER:
LEVEL:
DATE:j-ANll 2J4w DATE:
4/1'f01 PG.
OF
-3 5 0
000155 MANUAL ULTRASONIC TENNESSEE VALLEY PIPING EXA CINATION REPORT NUMBER:
AUTHORITY DATAPSHEET CLDEAT 03/21/
PROJECT:BFN UNIT 2 CYCLE: 15 EXAMINATION DATE:
05/04009 PROCEDURE: N-UT-64 REV: 0011 TC: N/A START TMEi: 0937 END TIME: 1010 SYSTEM: Recirc ISI DWG. NO: 2-IS1-0270-C-94 EXAM SURFACE El nD
[
OD COMPONENT ID: GR-2-35
- -f/
MATL. TYPE:
[--CSCL E']CCSS CONFIGURATION SURFACE TEMP.: 85* F PYRO. NO.: 562777 SDL TO Pipe
[
CAL DUE DATE: 03/21/10 FLOW
-EXAM INATION ANGLE 45S 60RL 70S Wo
REFERENCE:
CIENTER15NE OF WELD CIRC. SCAN SENS rVIY 40.0 N/A N/A Lo
REFERENCE:
Outside radius of elbow AXIAL SCAN SENSrTIVITY 40.0 70.0 N/A IND.
L (in) FROM REF.
AT MAX AMP MAX EXAM NOM.
N IND. INFO:
NO.
LI L
L2 W
MP D
AMP NO.
ANG.
R TYPE, DAMPING, MAX
_MAX MAX MAX
%DAC 3-14 1
ETC.
NRI 4
45 OSHEAR NR!
5 45 OSHEAR NRI 6
45 0
SHEAR NRI 4
60
[]RL 13 11 El El REMARKS /LIMITATIONS:
MAINTAINED 5 TO 20% ID ROLL DURING SCANNING.
Previously recorded geometry noticed at less than recordable amplitude.
EXAMINER: Tommy EXAMINER: Roger Senger REVIEWER:
0
000156 TVA WALL THICKNESS REPORT No:
PROFILE SHEET l/Oqj PROJECT: RRcO~wt FEýI* /
WELD NO:_C-r-UNIT:_
SYSTEM:.
I R(,
Record Thickness Measurements As
-Weld
90' 180' 270' 4].40
/_
[].640 CROWN HEIGHT:
DIAMETER:
CROWN WIDTH:
I WELD LENGTH:
FLoW \\
_. SD.L.
,0 PIPE
_ T-c-lc.)I volume!ý.....
5
- 35*3t O"to-ined Voalu-me. -. 75X.-l 1.I'7.i x3*
-l Torc.o Coý'ero,,%e Z=
o
- /
C.x 1.
s Yo 50 C/
~
.4 Ex
~REVIEWED BY:-______________________ý AEE LEVEL: _______
DATE',O ý DATE:
PAGE __'E= OF