ML031671466
| ML031671466 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/02/2003 |
| From: | Bhatnagar A Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2-ISI-18, 2-ISI-19 | |
| Download: ML031671466 (93) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Ashok S. Bhatnagar Vice President, Browns Ferry Nuclear Plant June 2, 2003 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-260 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM, THIRD TEN-YEAR INSPECTION INTERVAL - REQUESTS FOR RELIEF 2-ISI-18, AND 2-ISI-19 In accordance with 10 CFR 50.55a(g)(5), TVA is requesting relief from certain inservice inspection (ISI) requirements in Section XI of the ASME Boiler and Pressure Vessel Code. The need for these requests for relief was identified during ISI examinations recently completed during the BFN Unit 2, Cycle 12 refueling outage. The enclosures to this letter contain BFN Unit 2 requests for relief 2-ISI-18, and 2-ISI-19 for NRC review and approval.
TVA has determined that certain 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 XI, Division 1."
Ao47 Pnted on recyded paper
U.S. Nuclear Regulatory Commission Page 2 June 2, 2003 For 2-ISI-18, two austenitic stainless steel full penetration piping welds, one each for the Reactor Recirculation and Reactor Water Cleanup Systems, had calculated NDE examination coverage of 50 and 75 percent respectively. The limitations encountered during the performance of the ultrasonic (UT) examination were caused by component configuration. In addition, the welds are Category R-A (Westinghouse Owners Group (WOG) WCAP-14572, Revision 1-NP-A) Class 1 piping welds. These 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-side" examinations without completing a single-sided ASME Section XI, Appendix VIII demonstration using flaws on the opposite side of the weld. At the time of the examinations, no Performance Demonstration Initiative Program existed for single-side austenitic welds. Consequently, the percent examination coverage achieved for the two welds was 50 and 75 percent respectively. Enclosure 1 provides BFN Unit 2 request for relief, 2-ISI-18, which addresses the two austenitic stainless steel piping welds examined during Cycle 12.
For 2-ISI-19, TVA has determined that 12 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 XI, Division 1." The components are Reactor Pressure Vessel (RPV) nozzles (ASME Section XI, Code Category B-D, Nozzle-To-Vessel Welds) which had calculated NDE examination coverage ranging between 45 and 89 percent completed. The limitations encountered during the performance of the ultrasonic (UT) examination were caused by component configuration. The nozzle contours limit the accessible UT examination volume. Hence, TVA is submitting BFN Unit 2 request for relief 2-ISI-19 in Enclosure 2.
TVA seeks review of these requests for relief by January 15, 2005, to support resource planning for the Unit 2, Cycle 13 (Spring 2005) refueling outage.
U.S. Nuclear Regulatory Commission Page 3 June 2, 2003 There are no new regulatory commitments in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, Ashok S. BXnagar Enclosures cc (Enclosures):
(Via NRC Electronic Distribution)
Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUESTS FOR RELIEF 2-ISI-18 (See Attached)
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUESTS FOR RELIEF 2-ISI-18 Executive Summary: This request for relief addresses one Reactor Recirculation System and one Reactor Water Cleanup System Full Penetration Piping Welds examined during Cycle 12 in the first period of the Third Ten-Year 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 mandated by 10 CFR 50.55a(g)(4).
An ultrasonic examination was performed on these piping welds of accessible areas to the maximum extent practical due to the configuration. Credit for the one-sided only ultrasonic examination provided 50 percent coverage for weld KR-2-25 and 75 percent coverage for weld RWCU-2-003-G003, 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 flaw on the opposite side of the weld." At this time, there is no Appendix VIII Program for single sided austenitic welds nor is one planned in the future, therefore only 50 percent coverage can be claimed on weld KR-2-25 and 75 percent coverage on weld RWCU-2-003-G003. Under the original ASME Section XI Code requirements, UT coverage attained was 100 percent.
The performance of the ultrasonic examination of the subject areas to the maximum extent practical provides an acceptable level of E1-2
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), it is requested that relief be granted for the third inspection interval.
Unit: Two (2)
ISI Interval: ASME Section XI, Third Ten-Year ISI Inspection Interval (May 25, 2001 to May 24, 2011)
Systems: Reactor Recirculation System (RECIRC)
Reactor Water Cleanup System (RWCU)
Components: 2 Full Penetration Piping Welds ASME Code Class: ASME Code Class 1 ASME Section XI Code Edition: 1995 Edition, 1996 Addenda Code Table: Westinghouse Owners Group (WOG) Topical Report WCAP-14572, Revision 1-NP-A, Table 4.1-1 (Note: Table 4.1-1 in WCAP-14572, Revision 1-NP-A is identical to Table 1 in Code Case N-577)
Examination Category: R-A, Risk-Informed Piping Examinations Examination Item Number: R1.16, Elements Subject to Intergranular Stress Corrosion Cracking IGSCC)
Code Requirement: WCAP-14572, Revision 1-NP-A, Table 4.1-1, Examination Category R1.16, requires volumetric examination of 100 percent of the weld and adjacent base material as depicted in ASME Section XI Code, Figure IWB-2500-8(c).
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(Note: Table 4.1-1 in WCAP-14572, Revision 1-NP-A is identical to Table 1 in Code Case N-577)
Code Requirement From Which Relief Is Requested: Relief is requested from the Risk-Informed Inservice Inspection Program, WCAP-14572, Revision 1-NP-A, Table 4.1-1, Examination Category R-A, Item No. R1.16) to perform essentially 100 percent volumetric examination of weld and adjacent base material.
List Of Items Associated With The Relief Request: Weld KR-2 Pipe to Tee Weld RWCU-2-003-G003 - Pipe to Flued Head Basis for Relief: It is not possible to perform the volumetric ultrasonic examination from both sides of the welds due to the configuration of these components. Also, 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 flaw on the opposite side of the weld." At this time, there are no Appendix VIII Program for single-sided austenitic welds nor is one planned in the future, therefore, only 50 percent coverage for weld KR-2-25 and 75 percent coverage for weld RWCU-2-003-G003 can be claimed.
Under the original ASME Section XI Code requirements UT coverage attained was 100 percent.
Weld KR-2-25 limitations were due the configuration of the component, Pipe to Tee.
Weld RWCU-2-003-G003 limitations were due to the configuration of the component, Pipe to Flued Head.
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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.
Attached is a detailed description of the limitations in Table 1.
Alternative Examination: None. In lieu of the Code required essentially 100 percent volume ultrasonic examination, TVA proposes an ultrasonic examination of accessible areas to the maximum extent practical given the component design 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 mandated by 10 CFR 50.55a(g)(4).
An ultrasonic examination was performed on the piping welds to accessible areas to the maximum extent practical due to the configuration. Credit for the one-sided only ultrasonic examination provided 50 percent coverage on weld KR-2-25 and 75 percent coverage on weld RWCU-2-003-G003, 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 flaw on the opposite side of the weld." At this time, there is no Appendix VIII Program for single sided austenitic welds nor is one planned in the future, therefore only 50 percent coverage on weld KR-2-25 and 75 percent coverage on weld RWCU-2-003-G003 can be claimed. Under the original ASME Section XI Code requirements, UT coverage attained was 100 percent.
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Weld KR-2-25 limitations were due the configuration of the component, Pipe to Tee.
Weld RWCU-2-003-G003 limitations were due to the configuration of the component, Pipe to Flued Head.
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 requests that relief be granted for the third Ten-Year ISI inspection interval.
Implementation Schedule: This request for relief is applicable to the Third Ten-Year inspection interval for BFN Unit 2 (May 25, 2001 to May 24, 2011).
The Reactor Recirculation System and Reactor Water Cleanup System piping welds listed in Table 1 were examined during the first period (Cycle 12) of the Third Ten-Year inspection interval.
References:
Attachment - 2 ISI Sketches
- 2-ISI-0270-C, Sheet 2
- 2-ISI-0272-C, Sheet 1 E1-6
TABLE 1 WELD NPS ISI PERCENT REMARKS NUMBERS DRAWING EXAMINED KR-2-25 28" 2-ISI- 50% Limitations due to 0270-C component configuration and the requirement in 10 CFR 50.55a(b)(2)(xv)(A)(2),
which requires UT of one-side of austenitic welds to be qualified to Appendix VIII Program to claim full code coverage. At this time, there are no Appendix VIII Program for single sided austenitic welds nor is one planned for the future, therefore only 50 percent coverage can be claimed.
RWCU 6" 2-ISI- 75% Limitations due to 003-G003 0272-C component configuration and the requirement in 10 CFR 50.55a(b) (2)(xv) (A) (2),
which requires UT of one-side of austenitic welds to be qualified to Appendix VIII Program to claim full code coverage. At this time, there are no Appendix VIII Program for single sided austenitic welds nor is one planned for the future, therefore only 75 percent coverage can be claimed.
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Attachment 2-ISI-18 Two (2) Sketches 2-ISI-0270-C, Sheet 2, Recirculation System Weld Locations 2-ISI-0272-C, Sheet 1, Reactor Water Cleanup, RCIC, and CRD Weld Identification E1-8
RCEfERENCE ORA WINS:
S 2-47W2408-89 S.f. RLAIN)
GE 769E965 (S.E. RPLAOIT)
TVA 47Kl344-2 CE 2-15Jr7S4 KELLOGG SF 2-180 NOTE: THIS DRAWINC SUPERSEDES
-JJ CHU-2068-C ALL SHEErS
-J-DC MATERIAL SPECIrICATIONS:
AJs8. TP 304 4 X 0.J5P NON WAL L HK. (55) 12 X 0.569 NOW. IALL rHK. ()
22 X 1;030 NOI. WALL THK. (SS)
J-LS z8 X . 138- NOW. WAIL rHK. (SS) SUtIO 28 X t.J22 NOW. WALL THK (SS) OISCHARCJ 2' SCH. 80, A76. TP304
__4_ 2' fIrrINGS A182.FJ04
.48, 42 SAFE END REPLACEMENr 12' K 0.6$88 ANW. WPII TNK. ()
SA 403 WP J 6 N. o.
ASME CC-I (EOUIVALENr)
NOTES:
- 1. ALL 2V WELDS ARE SOCKET WELDED EXCEPT WHERE NOTED.
- 2. PIPE SECGNrS CONTAINING TO LONCITrWlUAL SEAMS WILL BE IDENTIFIED AS:
(BASE WELD NO.J-LS-10 (DOWNSTREAM)
(BASE fELD A. J-1S-2D (DOWNSTREAM)
(BASE wELD NO. - Ls-IU (uPSrREAM)
(BASE WELD NO.)-LS-2 VPSrREAM)
THE -LS-l SEAM WFILLBE NO uRICALLY CLOSESr TO OD ON THE PIPE. AND tHE -LS-2 SEAM IrILL BE NUMERICALLY fARTHFRMOST FROM O ON HFEPIPE.
(e.g. -LS-) AT 13O. AND -LS-2 AT JlO')
J. PIPE SMCENTS CONTAINING ONLy ONE LONCITUDINAL SEAM WILL BE IDENTIrIED AS (BASE WELD NO.)-LS-D (DOWNSTREAM)
(BASE WELD NO.)-L S-U (UPSTREAM)
RISK INfORMED W IDS 2-ISI-0270-C, Sheet 2 m
a lb NOINAL N - --
REFERENCE ORAWh?7CS CRD-2-005 RCIC-2-004
- a REC ION Of EHMAAL FATICUC WtALL EKAUINATION ER NUJRC-061 Rfi7§j. _ J-7 THERMAL TEf (UPS TREAM Of VALVE 2-FCV-69-630) NOTE:
THIS DRAWING SUPERSEDES C-2075-C AND CI-2072-C ALL SHETFS)
RCRS-2 rEE MATERIAL SPECIfICATIONS eceos-2-02 STAILESS STEEL a aa -.
flmAlM4 a
T_
ftCAOS-2-OJ ri rrNcs
'RCRO-2-44 6 SA40J IPJI6NC SCH. 80 Ss PIPI NC 6' SAJ76 rPJISNG SCH. 80 SS 6' A76CR rPJo4 SCH. 0 SS 6- A12CR TPJO4 SCH. S Ss CARBON Sfr ----------------------
4 SCu. 80 A-JJJ. CR (SEAMALESS CS CARBON STEEL 6 x 0.562" NOW ALL SCH. 120 CS STAINLESS SEEL I - X 0. 5 - NOIWALL SCH. 100 CS VAt VE 2-69-6JO SA182 rJ16 CRO CAP X* 0. 6 AOW AL SS ASUd CC-I (EOUIVAL ENT)
EZZZ] RISK' INfORMD WELD)
(OL) a, (OL RI Ias INemlpl Wru I ef6 N rRCIC-2-00J NtVINS D
- W.4 .4 0,05 I" - -
.I eam nf I PnFM I Sot I w s PA tlAlfSSf VAit AUID0IIr BROWNS FERRY NUCLEAR PLANT UNIT 2 REACTOR ArEt CLEAN UP CIC.
AN CD WELD Elotfr INATIOW oa A Inna ... Ae I i'ECa1 e45 ._ uHf, OF OT H U e_WI IfF 77Z-
--t --D AT- ----
- -------R----AEM m___- -- .- . - , i , - _lx-- - .
AiL A/9 'iStU OO C AINTAINE OAW l I ( U 2-ISI-0272-C, Sheet 1
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUESTS FOR RELIEF 2-ISI-19 (See Attached)
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUESTS FOR RELIEF 2-ISI-19 Executive Summary: This request for relief addresses 12 Reactor Pressure Vessel (RPV) nozzle-to-vessel full penetration welds. The design configuration of the RPV nozzle-to-vessel weld precludes a 100 percent ultrasonic (UT) examination of the required volume for the full penetration welds of the nozzles listed in Table 1. These examination limitations occur when the ASME Section XI, 1995 Edition, 1996 Addenda, examination requirements are applied in areas of components constructed and fabricated to early plant designs. Based on a construction permit date prior to January 1, 1971, BFN is exempt from meeting certain provisions of the Code requirements for examination access, to the extent practical, within the limitations of design, geometry, and materials of construction of the components in accordance with 10 CFR 50.55a(g)(4).
A UT examination was performed on accessible areas to the maximum extent practical given the physical limitations of the subject nozzle welds utilizing personnel and techniques qualified in accordance with ASME Section XI Appendix VIII. The design configuration limits UT examination of the RPV nozzle-to-vessel weld coverage (percentage) as shown in Table 1. TVA concludes that performance of an UT examination of essentially 100 percent of the RPV nozzle-to-vessel full penetration welds would be impractical. The performance of the UT 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 E2-2
sufficient information to judge the overall integrity of the welds. Therefore, pursuant to 10 CFR 50.55a(g)(5)(iii), it is requested that relief be granted for the Third Ten-Year ISI inspection interval.
Unit: Two (2)
ISI Interval: ASME Section XI, Third Ten-Year ISI Inspection Interval (May 25, 2001 to May 24, 2011)
System: Reactor Pressure Vessel (RPV), System 329 Components: 12 RPV Nozzles, Full Penetration Welds as listed in Table 1 ASME Code Class: ASME Code Class 1 (Equivalent)
ASME Section XI Code Edition: 1995 Edition, 1996 Addenda Code Table: IWB-2500-1 Examination Category: B-D, Full Penetration Welds of Nozzles in Vessels Examination Item Number: B3.90, Reactor Vessel Nozzle-to-Vessel Welds Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires a volumetric examination of essentially 100 percent of the weld and adjacent base material as depicted in Figure IWB-2500-7(a).
Code Requirements From Which Relief Is Requested: Relief is requested from the requirement of ASME Section XI Code, Table IWB-2500-1, Examination Category, B-D, Item No. B3.90 to perform essentially 100 percent volumetric examination of weld and adjacent base material as depicted in Figure IWB-2500-7(a).
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List Of Items Associated With The Relief Request: NlA - RPV Nozzle-to-Vessel Weld N2B - RPV Nozzle-to-Vessel Weld N2F - RPV Nozzle-to-Vessel Weld N2J - RPV Nozzle-to-Vessel Weld N3D - RPV Vessel-to-Nozzle Weld N4A - RPV Nozzle-to-Vessel Weld N4B - RPV Nozzle-to-Vessel Weld N4C - RPV Nozzle-to-Vessel Weld N4D - RPV Nozzle-to-Vessel Weld N4E - RPV Nozzle-to-Vessel Weld N4F - RPV Nozzle-to-Vessel Weld N8A - RPV Nozzle-to-Vessel Weld Basis For Relief Request: The design configuration of the RPV nozzle-to-vessel welds precludes an UT examination of essentially 100 percent of the required volume. The component design configuration limits UT examination coverage of the welds to the percentages listed in Table 1.
Alternative Examination: None. In lieu of the Code require essentially 100 percent volume UT examination, TVA proposes a UT examination of accessible areas to the maximum extent practical given the component design configuration of the RPV nozzle-to-vessel welds.
Justification for The Granting of Relief: The design configuration of the subject nozzle-to-vessel welds precludes UT examination of essentially 100 percent of the required examination volume. Access to the nozzle-to-vessel welds is by a series of doorways in the concrete biological shield wall. Insulation behind these doorways is designed for removal around the nozzle circumference. In order to examine the welds in accordance with the code requirements the RPV would require extensive design modifications. The physical arrangements of E2-4
the nozzle-to-vessel weld precludes UT examination from the nozzle side. The limitations are inherent to the barrel-type nozzle-to-vessel weld design and is compounded by the close proximity of the biological shield wall.
Scanning from the nozzle surface is ineffective due to the weld location and the asymmetrical inside surface where the nozzle and vessel converge. Coverage was increased by scanning from the outside blend radius of the weld where practical. Experience from the automated UT examination performed from the inside surface has shown that the nozzle-to-vessel weld coverage will not be greatly improved even if performed from the inside surface utilizing the current state-of-the-art techniques.
The configuration of the nozzle-to-vessel welds precludes UT examination from the nozzle side due to the weld location and the asymmetrical inside surface where the nozzle and vessel converge. The extent of examination coverage from the vessel side provides reasonable assurance that no flaws oriented parallel to the weld are present.
The areas receiving little or no examination coverage are located toward the outside surface of the reactor vessel in the general area of the nozzle outside blend radius.
(The blend radius restricts the scanning movement and/or transducer contact) The reactor vessel inner-half of the thickness and inside surface are interrogated with the UT beam. Degradation located at the inside surface or inner-half of the vessel would be located. It should be noted that the nozzle inside radius section received essentially 100 percent examination coverage on these nozzles.
Radiographic examination as an alternate volumetric examination method was determined to be impractical due the radiological concerns. Gaining access to the inside surface of the RPV to place radiographic E2-5
film would require extensive personnel protection due to high radiation and contamination levels. Also, due to the varying thickness at the outside blend radius of the weld several radiographs may be required of one area to obtain the required coverage and/or film density. The additional Code coverage gained by radiography is impractical when weighed against the radiological concerns.
Therefore, TVA concludes that performing an UT examination of essentially 100 percent of the nozzle-to-vessel full penetration welds in the RPV would be impractical. Further, it would also be impractical to perform other volumetric examinations (i.e., radiography) which may increase examination coverage. A maximum extent practical UT examination of the subject areas provides an acceptable level of quality and safety. TVA concludes that significant degradation, if present, would be detected during an UT examination performed to the maximum extent practical of the subject welds. As a result, reasonable assurance of operational readiness of the subject welds has been provided.
This request for relief is consistent with a previous Request For Relief 2-ISI-6 for the BFN RPV nozzle-to-vessel full penetration welds submitted and approved by the NRC in the second interval.
Therefore, pursuant to 10 CFR 50.55a(g)(5)
(iii), TVA requests that relief be granted for the Third Ten-Year inspection interval.
Implementation Schedule: This request for relief is applicable to the Third Ten-Year ISI inspection interval for BFN Unit 2 (May 25, 2001 to May 24, 2011).
The nozzle-to-vessel welds listed in Table 1 were examined in the first period (Cycle 12 operation) of the Third Ten-Year ISI inspection interval.
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References:
TVAN Nondestructive Examination Procedure N-GP-28 titled, "Calculation of ASME Code Coverage for Section XI NDE Examinations."
ISI Program Dwgs: 2-ISI-0270-C Sheets 1 and 2 2-ISI-0269-C Sheet 1 of 1 2-ISI-0222-C Sheet 1 of 4 2-ISI-0410-C Sheet 1 of 1 Examination Data Report: NlA - Report No. R-160 (Cycle 12)
N2B - Report No. R-161 (Cycle 12)
N2F - Report No. R-162 (Cycle 12)
N2J - Report No. R-163 (Cycle 12)
N3D - Report No. R-164 (Cycle 12)
N4A - Report No. R-141 (Cycle 12)
N4B - Report No. R-142 (Cycle 12)
N4C - Report No. R-143 (Cycle 12)
N4D - Report No. R-144 (Cycle 12)
N4E - Report No. R-145 (Cycle 12)
N4F - Report No. R-146 (Cycle 12)
N8A - Report No. R-165 (Cycle 12)
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TABLE 1 WELD NUMBER NPS ISI PERCENT REMARKS DRAWING EXAMINED NIA Recirc 28" 2-ISI-0270-C 48.8% Nozzle to Vessel Weld 43 Outlet) and 60 degree shear and 43 and 60 degree longitudinal scanning was restricted due to nozzle configuration. Exams performed from the shell side and outer nozzle blend radius.
N2B (Recirc 12" 2-ISI-0270-C 51.5% Nozzle to Vessel Weld 40, Inlet) 43, 63 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration. Exams performed from the shell side and outer nozzle blend radius.
N2F (Recirc 12" 2-ISI-0270-C 51.5% Nozzle to Vessel Weld 40, Inlet) 60 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration. Exams performed from the shell side and outer nozzle blend radius.
N2J (Recirc 12" 2-ISI-0270-C 51.5% Nozzle to Vessel Weld 40, Inlet) 58 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration. Exams performed from the shell side and outer nozzle blend radius.
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TABLE 1 (Cont.)
NOZZLE NUMBER NPS ISI DRAWING PERCENT REMARKS EXtMINED N3D (Main Steam) 26" 2-ISI-0222-C 47.3% Nozzle to Vessel Weld 41, 58 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration. Exams performed from the shell side and outer nozzle blend radius.
N4A (Feedwater) 12" 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 40, 41, 58, degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No. C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld. Exams performed from the shell side and outer nozzle blend radius.
N4B (Feedwater) 12" 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 42, 59 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No.
C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld. Exams performed from the shell side and outer nozzle blend radius.
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TABLE 1 (Cont.)
NOZZLE NUMBER NPS ISI DRAWING PERCENT REMARKS EXAMINED N4C (Feedwater) 12" 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 40, 42, 60 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No.
C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld. Exams performed from the shell side and outer nozzle blend radius.
N4D (Feedwater) 12' 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 40, 42, 59, degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No.
C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld. Exams performed from the shell side and outer nozzle blend radius.
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TABLE 1 (Cont.)
NOZZLE NUMtBER NPS ISI DRAWING PERCENT REHAPKS EXAMINED N4E (Feedwater) 12" 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 42, 59 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No.
C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld.
Exams performed from the shell side and outer nozzle blend radius.
N4F (Feedwater) 12" 2-ISI-0269-C 45.4% Nozzle to Vessel Weld 40, 42, 59 degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and RPV Circumferential weld No.
C-3-4. The 60 degree RL radial scan was limited by approximately 4.7 percent due to lift off on lower toe of nozzle to vessel weld.
Exams performed from the shell side and outer nozzle blend radius.
N8A (Recirc 4" 2-ISI-0410-C 89.5% Nozzle to Vessel Weld 50 Instr. Nozzle) degree shear and 60 degree longitudinal scanning was restricted due to nozzle configuration and Circumferential RPV weld C-BH-1. The 60 degree radial scan was limited by approximately 4.8 percent due to lift off on upper toe of nozzle to vessel weld.
Exams performed from the shell side.
E2-11
Attachment A 2-ISI-19 Five (5) Sketches 2-ISI-0270-C, Sheets 1 and 2 2-ISI-0269-C, Sheet 1 of 1 2-ISI-0222-C, Sheet 1 of 4 2-ISI-0410-C, Sheet 1 of 1 E2-12
REFERENCE DRAWINGS:
2-47F2408-8.9 (S.E. REAfNTJ CE 769(963 (SE. REPA:T)
A - LOOP TVA 47K1544-2 2Rf I 2RFI 2RF6
~~~GE 2-I5JF 754 KELLGC F 2-80 F 2RF NOTE: THIS DRAWINC SUPERSEDES CHM-2068-C ALL SHEErS MA TERIAL SPECIFICA riONS:
2Rf5 A358. TP 304 4' X 0.337' NO WALL TK. (SS) 2' X 0. 569 NOU. WALL rK. (SS)
KR~IS~\ 22 x .030 N. WALL trHK (SS)
CR-2-O9-LS 28 X 1. 3J- NOU. VALL HK. (SS) SUCrIOA 28- X 1.322" NW. ALL TH. ss) DISCHARCE 2 SCH. 80 A-J76, TPJ04 2" FITTINCS A-182, FJO4 l2-O9 SAFE END REPLACEMENT f
KR _ 3 z I SAX O65fJP Nm, W L HK. (SS) 12 s lt CC-1 AS (ouIvAEN5) 1i Xem, ~~~~~~~~~~~2RXCX
/-KR-~KR2- 2-t s 3~~~~~~~~~~~
?-12 810£svitLo 2RX5 RISER DETAIL NOSrES: . IELDS 2RXI ARE THE NOZZLE rO SAFE-END WELDS
- 2. ALL 2" rELDS ARE SOCKEr WELDED EXCEPr wHERE NOTED,
- 3. PIPE SECMNrS CONTAINING TWO LONGITUDINAL SEAMS WILL BE IDENTIFIED AS:
(BASE WELD NO.)-LS-ID (DOWNSTREAM)
(EASE WELDNO.)-LS-2D (DOWNSTREAM)
(SASE WELD NO.)-LS-fU (UPSTREAM)
(SASE WELDNO.)-LS-2U (UPSTREAM) rHE -S- SAM WILL BE NUMERICALLY CLOSEST rO o ON THEPIPE, AND rHE -LS-2 StAM WILL BE NUMERICALLY rfARrHERMOSr fROW 0" ON HE PIPE.
(e. . -LS-1 AT 130. AND -LS-2 A J10')
43 PIPE SECENTS CONTAINING ONLY ONE LONCITUDINAL SEAM WILL E DENTiFIED AS (BASE WELD NO. )-LS-D (DOWNSTREAM)
I-LS-1 (BASE ELD NO )-LS-U (UPSTREAM)
-L S-2 RISK JAiFORMED fELDS 00J5, 1, AO IN I NOSIWM I IC liw o REVISE l, 'Mr,IMEMO WI 021202102 REV[ CACt r PREPAREt I CHECKER APPM I DATE rTENNSSEE VALLEYAuWNrY BROWNS FERRY NUCLEAR PLANT XR-N-N 2R XN UNI r 2 D NO.
WlEL RECIRCULArION SYSTEM K KELLOGG SHOP ELD L UNIT NO C -CE RIELD WELD UNIT NO. RISER 't IA I NgIf IS SYSTEM T ssrTM LETTER Y AT R.. _ESEARU"ED . .2 C ALL AD HI2STORYRSEARChEO AT ROO CC 2-ISI-0270-C, Sheet 1
RLrVRLNCr RA WINGS-S 2-47#2408-8.9 S.f. R GE 769E963 (S.E. REPLAWVT)
TVA 47K1544-2 CC 2-155f754 ENT)
KELLOGC SF 2-150 NOTE: THIS DRAWING SUPCRSEDErS
- J3 CHM-2068-C ALL SHEETS 33-BC MATERIAL SPECIFICArioNs:
AJSJ. TP 304 4 X .537 N WALLt THK. (SS) 12" X 0.569' NOW. ALL HK. (SS) 22" 1030" NW. WALL THKI.()
J8-LS 2B" x 1.138 NOM. WALL THK. (SS) SCTI 28 X 1.322' N. WALL THK. (SS) DISCHARCE 2- SCH. 80, A376. TP304 2 FITrTINGS AI82,F304 48 42 SAFE END REPLAC'MENT 1?" X 0.688 NW. WALL THK. (SS)
SA 403 P J6 N. G.
ASME CC-I (ECUIVALENT)
NOTES:
- 1. ALL 2 WELOS ARE SOCKET WELDED EXCEPT WHERE NOTED.
- 2. PIPE SEGMENTS CONrAINING TWOLONC)TUDINAL SEAMS WILL BE IDENTIFIED AS:
(BASE WE-LD NO.) -LS-ID (DOWNSTREAM)
(BASE WELD NO.)-LS-2D (DOWNSTREAM)
(ASE WELD NO. -LS-lu (UPSTREAM)
(BASE WELD NO. )-LS-2U (UPSTREAM) rHE -LS-I SEAM fILL BE NUMERICALLY CLOSEST TO o0 ON THE PIPE. AND THE -LS-2 SEAM WILL BE NUMERICALLY FARTHERMosr ROw O ON HE PIPE.
(e. -LS-) AT 130'. AND -LS-2 AT 310")
3 PIPE SEGMENTS CONTAINING ONLY ONE LONcITUDINAL SEAM WILL E IDENTIrIED AS (BASE WELD NO.)-LS-D (DOWNSTREAM)
(BASE ELD NO.)-LS-U (UPSTREAM)
RISK INfORAMED WLDS 0041 AMIN INO LWsicEa I I ez I r d i/-<
REVISED ER 1INS 314021202102 MV OACE Of PPAUEN I CECKER APOVED TE TENNESSr VALLEY AUrTHORITr BROWNS FERRY NUCLEAR PLANT UNI T 2 RECIRCULA TION SYSTEM WrLD LOCATIONS AIU6TJ-2AP . :. se" r f lllLL;_ EDC CL MASI-0270-C 04 ALL A/D HISTORY RESEARCHED a ROCOO CCD _c Z-IS1-UZU-U, Sheet 2
47KI1545-1 47V335-fJ U 1s51-072-c lay. 1) SL#PORT m4P
- AFM-R-36 TMIS ffA1N SLP97COES 0*,067-C ALL S'ES.
I AM &-SO$4"0 so{c4 O M Ar.FG AEIW INA-S m ffW7eU J. is, Soo Cs1 J. if NOZZLES (INNER RADIUS)
N-A-JR N-4-JR N-4C-JR UE, C SOAD O. P N-ID- IR N-4t-M Aim A-n4 , C&W.S -
N-4fr-R ALLDM 1WZ A.A& A'a5 ~*5 .? . r ~ IS I d g NOTES I KFF-2-40 1. GE FEW ELM 1R MADE N TE FZELD 0Y TVA.
- 2. PIPE SEBSE?J LWIrTWN*I SEAMS MILL BE TZIrZED AW (BAE EL) -LS-0 DOSWTEAN)
. - , J-554
+.. 4 4, /_ BC o0' X J2' 6M-2-5 K-EWU7 a-GE FrEw ItQ 5 AE 7UTE.fl tvLOI0 Aid 4A MIS?r zstAIOO Ar vO 2-ISI-0269-C, Sheet 1
REFERENCE OA ING
- 9 KS-"-O2&-LS-k d KN5-S-02P 4?WSII-5 KMS-"-2O-L - ;ZE-2OF S WMA W )J sPPCr MAP NOTe 7 5 (rWAWAI SIPEROEVES 094-2069-C (Sm. 5)
PIPE DArA ASIA CC-S (MEUIVALENTj ASp A-SOS XC70 2 X 0.950 MIO. WALLT. /CS) 6 X 0. 79 NO. WAU TPW. (SCH. 60 CS)
MS-I-az,,firBO NOTE&S ALL FIELD MDS EFW MADCE DY VA KMI-I-00I moTe
- 1. P!)E SEgftWS CONTAINING M L0NSItWINAL SEAS WILL VOWNTfIFIED AM l F (BASE WL NO.)-LS-SO Msr RErAM)
(9ASE ELDO MO.) -LS-2O (ODOW7TRSEAM)
(BASE ELD M.) -LS-lU (LPsrR A z; (BASE ELD N.) -LS-2 (PSrE AN) 8t4S--0 -LS--..
?Wf -S-S JWAM WLL M I$.M=I ALLY CLOSFSr TO0 LWON95PIPE AAV 77W-LS--~B SCAM NILL BE MAWECALLY ARrWST F 07 ON 7H6PrPE.
(e.g. -LS-1 AT 30: AO -LS-2 AT 3100) 192-Ls-J 2. PZPE SEBMS CONTAZNIM OK B LS-2-32'LSL * / - )92-LS-2 , l LONWZITuOrAL SEAN WILL BE 2004 rrIFED AS:
-I-SOS-LS (BASE NLELD NO.)-LS-D 0hWNSTR EA M)
I-I-S0B (B4SE LD AO.)-LS-U SM M')
1-I-OS-! 5 6" ~~M--X-t t 6d7l FC-old05-L 7atLA Bug-f-S I~~~AS rJTi~~~~~i 06 P95--sI I32 K- SOP iLO 6- FlELD EL CV.4v-O/$
MAM,EAM wir NO.
.0 D tO.
P I>
1
\~~a-2-11 SNO--LS2 I-2-00J i
I-.2j -LS
/
~~~~-IW S-2-ODS-LS
- 3JL
-MAC 5 -0 FCV-O-OJ-BC ME J taW 3tNF J3 x.I A I1 ;IDL I C T 9EQ 1:Tr67 0
RttitlD PR Rs KCI R OOntt 001 M-VAV56 Rty I wOt RF I RtpAC EN C"CK T AFROwoTDATC aug-I-Ia lTZlS001 tE70fSSgM* EL VALEY AUI
-- LsI I-BROAWS FERRY MCLEA OANrr D A. R ?-30-LS2u r2 0481 (lil~~~~~VMT k- mOL,e. NR7S DEr lNRES MAZN SFAM STE OELI VET A t ac
.1TST-C.C 1003 ALL A/0 HISTOCY RESIARCHCO AT l000 In ... ..... - i I 2-ISI-0222-C, Sheet 1
0-12D3J3 GE ( 4-8J271) 769E957 0 (84P64-88J5271)
CHM-2046-C (NOZZLE LOCATIONS)
NOTEt THIS DtRAI^NG SUPERSEDES IS, -0156-A MATERIAL SPECIFICArIONS DISSIMILAR METAL ELD NOZZLE A OR a NBA OR NS NODZZLE TO VESSEL WELD JP-2-lX 0 0 0
APPROXIMATELY 10 3/4" I
2-ISI-0410-C, Sheet 1 I
ALL A/D HIST1 RfUEAR"C At O I I
11,IN 9qt.!- ",1:7
Attachment B 2-ISI-19 Weld Examination Data Reports NlA - Report No. R-160 (Excerpt)
N2B - Report No. R-161 (Excerpt)
N2F - Report No. R-162 (Excerpt)
N2J - Report No. R-163 (Excerpt)
N3D - Report No. R-164 (Excerpt)
N4A - Report No. R-141 (Excerpt)
N4B - Report No. R-142 (Excerpt)
N4C - Report No. R-143 (Excerpt)
N4D - Report No. R-144 (Excerpt)
N4E - Report No. R-145 (Excerpt)
N4F - Report No. R-146 (Excerpt)
N8A - Report No. R-165 (Excerpt)
E2-13
Weld Examination Report R-160 (Excerpt)
00403 't -
FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 28" Recirculation Outlet Nozzle to Vessel Weld NIA The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of A" on each side of the fusion line (Required Examination Area). This Includes the outer 65% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configurabon of the nozzle weld blend radius wth the 60 degree RL scans. The weld blond radius configuraton rstbicts the examination coverage. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100°h coverage. The examination mltatons are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS Recuired Examination Area: 46.08 sq. In.
Inner 16% of Weld: 6.21 sq. In.
60° Radial Scan from Shell Area Examined: 30.24 sq. in.
600 Tangential Scan from Shell Area Examined: 8.52 sq. In.
Percent of 600 RL Scans Completed: (30.24+ 8.52) ÷ 2 = 19.38i+46.06x100= 42.1%
Inner 16% of Weld Area Examined: 6.21 sq. in.
Total Percent Examinaton Completed: = (6.21 + 8.52 + 30.24) - 2 = 22.49 48.06 x 100 = 48.8%
Page _. of __
0 ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 28" RECIRCULATION OUTLET NOZZLE TO VESSEL WELD NIA NOZZLE Il I
C) c>
Il bpf
_ __ I I
I I
I 1-I 0 Page Lt of h
00408 1>' - ( tec Table 1. Browns Ferry Recirculation Outlet Nozzle (NI)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 24.188 Weld End R 29.153 Taper Angle, ID 15 Taper Angle, OD 0 Zbore 144.375 Rbore 13.138 Rnozzle 26.5 Rbi 3 Rbo 5.75 Rvi 125.6875 Rvo 131.9375 Table 2. Spreadsheet Model Techniques for Recirculation Outlet Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(60 to 78) Vessel Shear Wave 43 +/-106 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Recirculation Outlet Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientation 60 +/-(60 to 78) Vessel 31.90 33.66 9.92 14.77 10 43 +/-106 Blend 27.34 30.03 7.66 15.76 12 Page '2 of 8
Weld Examination Report R-161 (Excerpt)
00411 W-\(
A FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Recirculation Inlet Nozzle to Vessel Weld N2B The Ultrasonic examination volume Is the Nozzle to Sheg weld and adjacent base material for a distance of Y" on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15%e thickness as measured from the Inside diameter surface. The 60 degree RL, radlal scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination llmitations were encountered from the exsting configuration of the nozzle weld blend radius with the 60 degree RL scans. The weld blend radius configuration restricts the examination coverage. All other angles used for ultrasonic examination of the Inner 15V of the weld yielded 100%h coverage. The examination limitations are shown In square Inches in order to simplify calculations. See the applicable Ultrasonic Examination Limitation Sketch.
CALCULATIONS Reauired Examination Area: 32.83 sq. In.
Inner 15% of Weld: 4.19 sq. In.
600 Radial Scan from Shell Area Examined: 23.04 sq. In.
600 Tannential Scan from Shell Area Examined: 6.6sq. In.
Percent of 600 RL Scans Completed: (23.04 + 6.6) + 2 = 14.82 32.83 x 100= 45.1%
Inner 16% of Weld Area Examined: 4.19 sq. In.
Total Percent Examination Comnleted: = (4.19 + 6.6 + 23.04)
- 2 = 16.92 + 32.83 x 100 = 51.5%
Page S of i>__
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" RECIRCULATION INLET NOZZLE TO VESSEL WELD N2 NOZZLES I\
1: \
I . \.
- ~~ ; I 1- *. ,: I i
- ~ ~~
1 -
Page of &
00416 Table 1. Browns Ferry Recirculation Inlet Nozzle (N2)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 10.813 Weld End R 15.153 Rbore 5.94 Rnozzle 12.5 Rbi 2.25 Rbo 3.5 Rvi 125.375 Rvo 131.625 Table 2. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(36 to 66) Vessel Shear Wave 40 +/-120 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misoientation 60 +/-(36 to 66) Vessel 16.56 20.48 9.92 14.76 6 40 +/-120 Blend 12.93 14.02 7.63 11.14 4 Page of 3
Weld Examination Report R-162 (Excerpt)
00419 FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Recirculation Inlet Nozzle to Vessel Weld N2F The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of y1" on each side of the fusion line (Required Examination Area). This Includes the outer 8x% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85S of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate exarination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozzle weld blend radius with the 60 degree RL scans. The weld blend radius configuration restricts the examination coverage. All other angles used for ultrasonic examinabon of the Inner 15% of the weld yielded 100%h coverage. The examination limitations are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Limitation Sketch.
CALCULATIONS Reauired Examination Area: 32.83 sq. In.
O Inner 15% of Weld: 4.19 sq. In.
60° Radial Scan from Shell Area Examined: 2304 sq. In.
60° Tanaential Scan from Shell Area Examined: 6.6 sq. In.
Percent of 60° RL Scans Completed: (23.04 + 6.6) + 2= 14.82 32.83 x 100 =45.%
Inner 16% of Weld Area Examined: 4.19 sq. In.
Total Percent Examination Comoleted: = (4.19+6.6+23.04) .2= 16.92T32.83 x 100 = 51.5%
Page !.. of 8
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" RECIRCULATION INLET NOZZLE TO VESSEL WELD N2 NOZZLES I \
l\
- ~~ / 1 Page ,A. of m
00424 Table 1. Browns Ferry Recirculation Inlet Nozzle (N2)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 10.813 Weld End R 15.153 Rbore 5.94 Rnozzle 12.5 Rbi 2.25 Rbo 3.5 Rvi 125.375 Rvo 131.625 Table 2. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(36 to 66) Vessel Shear Wave 40 +/-120 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientation 60 +/-(36 to 66) Vessel 16.56 20.48 9.92 14.76 6 40 +/-120 Blend 12.93 14.02 7.63 11.14 4 Page g of
Weld Examination Report R-163 (Excerpt)
00427 FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Recirculation Inlet Nozzle to Vessel Weld N2J The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of Y on each side of the fusion ine (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The ZoneI and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozle weld blend radius with the 60 degree RL scans. The weld blend radius configuration restricts the examination coverage. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100% coverage. The examination limitations are chown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS Reauired Examination Area: 32.83 sq. In.
Inner 15% of Weld: 4.19 sq. In.
60° Radial Scan from Shell Area Examined: 23.04 sq. In.
600 Tannential Scan from Shell Area Examined: 6.6 sq. In.
Percent of 600 RL Scans Completed: (23.04+6.6) 2= 14.82 + 32.83 x 100 45.1 Inner 15% of Weld Area Examined: 4.19 sq. In.
Total Percent Examination Completed: = (4.19 + 6.6 + 23.04) - 2= 16.92 . 32.83 x 100 = 51.5%
Page 3? of
- 0 ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" RECIRCULATION INLET NOZZLE TO VESSEL WELD N2 NOZZLES 7\
0 I . . I Ir
- .'---: I 1V.T Page 4+/- of 8_
00432 Table 1. Browns Ferry Recirculation Inlet Nozzle (N2)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 10.813 Weld End R 15.153 Rbore 5.94 Rnozzle 12.5 Rbi 2.25 Rbo 3.5 Rvi 125.375 Rvo 131.625 Table 2. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(36 to 66) Vessel Shear Wave 40 +/-120 Blend Shear Wave S
Table 3. Spreadsheet Model Techniques for Recirculation Inlet Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Mlsorientation 60 +/-(36 to 66) Vessel 16.56 20.48 9.92 14.76 6 40 +/-120 Blend 12.93 14.02 7.63 11.14 4 Page 8 of ___
Weld Examination Report R-164 (Excerpt)
00435 A Pt FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 26" Main Steam Nozzle to Vessel Weld N3D The Uitrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of %" on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozzle weld blend radius with the 60 degree RL scans. The weld blend radius configuration restricts the examination coverage. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100% coverage. The examination limitations are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS Reauired Examination Area: 43.36 sq. In.
Inner 15% of Weld: 5.29 sq. in.
60° Radial Scan from Shell Area Examined: 27.39 sq. in.
600 Tangential Scan from Shell Area Examined: 8.33 sq. in.
Percent of 600 RL Scans ComDleted: (27.39 + 8.33) 2= 17.86 + 43.36 x 100 = 41.0%
Inner 15% of Weld Area Examined: 5.29 sq. in.
Total Percent Examination Comnleted: = (5.29 + 8.33 + 27.39) + 2 = 20.51 + 43.36 x 100 = 47.3%
Page 3.. of 8
- S ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 26" MAIN STEAM NOZZLE TO VESSEL WELD
, NOZZLE
~~~~~~~N3D I
I~~~~~~~~~ :\
I Page < of
00440 .
Table 1. Browns Ferry Main Steam Nozzle (N3)
I Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 19.219 Weld End R 23.965 Rbore 12.063 Rnozzle 21.313 Rbi 3.063 Rbo 4.75 Rvi 125.6875 Rvo 131.9375 Table 2. Spreadsheet Model Techniques for Main Steam Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(54 to 74) Vessel Shear Wave 40 +/-115 Blend Shear Wave S
Table 3. Spreadsheet Model Techniques for Main Steam Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientation 60 +/-(54 to 74) Vessel 26.57 27.65 10.04 14.96 8 40 +/-115 Blend 22.03 24.19 7.29 12.54 14 0
Page 2 oZ
Weld Examination Report R-141 (Excerpt)
00302 FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4A The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of V' on each side of the fusion line (Required Examination Area). This Includes the outer 85 thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial sans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85 of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozzle weld blend radius and the adjacent reactor shell weld with the 60 degree RL scans. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100°h coverage. The examination limitations are shown In square Inches In order to simplify calculations. See tho applicable Ultrasonic Examination Lmitation Sketch.
CALCULATIONS Reauired Examination Area: 34.89 sq. In.
O Inner 15% of Weld: 4.37 sq. In.
600 Radial Scan from Shell Area Examined: 23.99 sq. in.
600 Tanaential Scan from Shell Area Examined: 6.63 sq. in.
Percent of 600 RL Scan Limited from the Adiacent Reactor Shell Weld:
Percent of 600 RL Scans Completed: (23.99 + 6.63)
- 2 = 15.31 + 34.89 x 100 = 43.88% - 4.7% = 39.2%
Inner 16 of Weld Area Examined: 4.37 sq. in.
Total Percent Examination Completed: (4.37 + 6.63 + 23.99) + 2= 17.50 34.89 x 100 = 50.1% - 4.7% = 4A%
Page -3 of W
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I . \
. *' - I 0 Page 4 of \
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD 00301 N4 NOZZLES Lu lb e C-3-+
NK
/
/
/
I I
I 1I 0 II I
/
/
/
/
I'l 6o r-L KAbIkL CAP &.,AS LIMIT 151 APP? o"K l ELy bU T27 LIFTOPF' oAJ Lo"3E-P TbE of 6L O cwrEL".
Page Z.5 of *11
00313 (
FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INNER RADIUS EXTENSION (NUREG 0619, ZONE 3)
THERMOCOUPLE PAD LIMITATIONS N4 NOZZLES Each Thermocouple Pad limits Inner Radius Extension scan by 2.90. There are 2 Thermocouple pads located at approximately 270° on N4A, N4B, N4D and N4F. (See attached Litation Sketch)
Total Circumferentbal Measurement of Nozzle Boss: 81.75" Total Scan Umitation: 2.9( x 2 = 5.80' 5.80' + 81.75' x 100 = 7% Umitaton 100% - 7YO = 93%
Total Nozzle Inner Radius Extension Coverage 93%
Page Ito of A2i.
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INSIDE RADIUS EXTENSION (NUREG 0619, ZONE 3)
N4 NOZZLES 817,CIRC(.
63, W.
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Weld Examination Report R-142 (Excerpt)
00332 R Iqc FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4B The Ultrasonic examinaton volume Is the Nozzle to Shell weld and adjacent base material for a distance of Vim on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thIckness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85%C of the weld examination volume. The Zone- and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozle weld blend radius and the adjacent reactor shell weld with the 60 degree RL scans. All other angles used for ultrasonic examination of the Inner 15I of the weld yielded 100% coverage. The examination limItations are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Umitatlon Sketch.
CALCULATIONS Reautred Examination Area: 34.89 sq. In.
Inner 15% of Weld: 4.37 sq. In.
600 Radial Scan from Shell Area Examined: 23.99 sq. in.
600 Tangential Scan from Shell Area Examined: 6.63 sq. In.
Percent of 600 RL Scan Umited from the Adiacent Reactor Shell Weld: 4.7 Percent of 600 RL Scans Completed: (23.99 + 6.63) + 2 = 15.31 34.89 x 100 = 43.88% - 4.7% =
Inner 1* of Weld Area Examined: 4.37 sq. in.
Total Percent Examination Comuleted: (4.37 + 6.63 + 23.99) + 2= 17.50 + 34.89 x 100 = 50.1% - 4.7% = 45A%
Page i of e
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I.
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ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 00317 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES 4,o L JTAbAL SeCA t,AS LtMITCb JS AooKtA&MafLy LI.7'f4 bUl C Llr-raFF oJ Lot,)Ep TDE oF 6TI &rCL>.
0 Page ' of e
00328 At FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT BROWNS FERRY UNIT-2 12m FEEDWATER NOZZLE INNER RADIUS EXTENSION (NUREG 0619, ZONE 3)
THERMOCOUPLE ATTACHMENT PAD UMITATIONS N4B Each Themocouple Attachment Pad limits Inner Radius Extension scan by 2.90*. There are 2 Thermocouple Atachment Pads located at approximately 2700 on N4A, N4B, N4D and N4F. (See attached Umitation Sketch)
Total Circumferential Measurement of Nozzle Boss: 81.75 Total Scan Umitation: 2.90' x 2 = 5.80 5.80' + 81.75 x 100 = 7% Limitation 100% - 7% = 93%
Total Nozzle Inner Radius Extension Coverage = 93%
Page I( of L
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INSIDE RADIUS EXTENSION (NUREG 0619, ZONE 3)
N4 NOZZLES 57, I1d./I ,i C0 2
-MERrCOUPLE LImITAT70 Pagel,> of X..!
00330 I>-
Table 1. Browns Ferry Feedwater Nozzle (N4)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 11.25 Weld End R 15.60 Rbore 6 Rnozzle 13 Rbi 3 Rbo 3.75 Rvi 125.6875 Rvo 131.8125 Table 2. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surrace Mode of Propagation 60 +/-(35 to 67) Vessel Shear Wave 40 +/-120 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Mn MP Max MP Max Angle Skew Surface Misorientation 60 +/-(35 to 67) Vessel 17.27 20.71 9.73 14.44 20 40 +/-120 Blend 13.45 14.55 7.64 11.35 6 0
18 Ate
Weld Examination Report R-143 (Excerpt)
-"B :Z.
00335 p FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4C The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of Y on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thickness as measured from the nside diameter surface. The 60 degree RL, radial scans were used to emmine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone- and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the existing configuration of the nozzle weld blend radius and the adjacent reactor sliell weld with the 60 degree RL scans. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100 coverage. The examination limitations are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS Reaufred Examination Area: 34.89 sq. In.
O Inner 15% of Weld: 4.37 sq. In.
600 Radial Scan from Shell Area Examined: 23.99 sq. in.
60° Tannential Scan from Shell Area Examined: 6.63 sq. In.
Percent of 60° RL Scan Lmited from the Adiacent Reactor Shell Weld:
Percent of 600 RL Scans Comnleted: (23.99 + 6.63) + 2 = 15.31 + 34.89 x 100 = 43.88% - 4.7% = 39.2%
Inner 16% of Weld Area Examined: 4.37 sq. in.
Total Percent ExamInation Completed: (4.37 + 6.63 + 23.99) + 2 = 17.50 + 34.89 x 100 = 50.1% - 4.7% =45.4%
Page of I e
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES IP I .
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ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 00337 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES
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00348 Table 1. Browns Ferry Feedwater Nozzle (N4)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surrace Dimensions (inches) Dimensions (inches)
Weld Start R 11.25 Weld End R 15.60 Rbore 6 Rnozzle 13 Rbi 3 Rbo 3.75 i
I Rvi 125.6875 Rvo 131.8125 Table 2. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-(35 to 67) Vessel Shear Wave 40 +/-120 Blend Shear Wave 0
Table 3. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew -. Surface Misorientation 60 (35 to 67) Vessel 17.27 20.71 9.73 14.44 20 40 +/-120 Blend 13.45 14.55 7.64 11.35 6 LIc ot( o
Weld Examination Report R-144 (Excerpt)
00351 At FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4D The Ultrasonic examinalon volume Is the Nozzle to Shell weld and adjacent base material for a distance of VP on each side of the fusion line (Required Examination Area). This Includes the outer 85 thickness and the Inner 15% thickness as measured from the Inside dlameter surface. The 6D degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld exambnation volume. The Zone-1 and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonlc examination limitations were encountered from the existing configuraton of the nozzle weld blend radius and the adjacent reactor shell weld with the 60 degree RL scans. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100% coverage. The examination limitations are shown In square Inches In order to simpify calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS
. Inner 15% of Weld:
34.89 sq. In.
4.37 sq. In.
600 Radial Scan from Shelf Area Examined: 23.99 sq. in.
600 Tanoential Scan from Shell Area Examined: 6.63 sq. in.
Percent of 60 RL Scan Umited from the AdJacent Reactor Shell Weld:
Percent of 600 RL Scans Completed: (23.99 + 6.63) + 2 = 15.31 + 34.89 x 100 = 43.88% - 4.7% = 39.2%
Inner 1% of Weld Area Examined: 4.37 sq. in.
Total Percent Examination Completed: (4.37 + 6.63 + 23.99) + 2 = 17.50 + 34.89 x 100 = 50.1% - 4.7% = A%
Page 3 of
0 ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I
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ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 00353 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES
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00364 FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INNER RADIUS EXTENSION (NUREG 0619, ZONE 3)
THERMOCOUPLE ATTACHMENT PAD LIMITATIONS N4D Each Thermocouple Attachment Pad limits Inner Radius Extension scan by 2.90'. There are 2 Thermocouple Attachment Pads located at approximately 2700 on N4A, N4B, N4D and N4F. (See attached Umitation Sketch)
Total Circumferential Measurement of Nozzle Boss: 81.75' Total Scan Umitation: 2.90' x 2 = 5.80' 5.80' + 81.75' x 100 = 7%Limitaton 100% - 7%= 93%
Total Nozzle Inner Radius Extension Coverage = 93%
Page 1(,e of 0P
0 ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INSIDE RADIUS EXTENSION (NUREG 0619, ZONE 3)
N4 NOZZLES 81.758"CISC 0
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TR E rnO C0l0 E LI m ITATIlo Page >) of L
00366 Table 1. Browns Ferry Feedwater Nozzle (N4)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 11.25 Weld End R 15.60 Rbore 6 Rnozle 13 Rbi 3 Rbo 3.75 Rvi 125.6875 Rvo 131.8125 Table 2. Spreadsheet Model Techniques for Feedwater Nozzle-to-Sheli Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 60 +/-35to 67) Vessel Shear Wave 40 +120 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Mn MP Max MP MaX Angle Skew Surface Misorientation 60 +/-(35 to 67) Vessel 17.27 20.71 9.73 14.44 20 40 +/-120 Blend 13.45 14.55 7.64 11.35 6 l 9 1(0
Weld Examination Report R-145 (Excerpt)
00369
- S A
FRAMATOME ANP ULTRASONIC EXAMINATION LMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4E The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of Y2" on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone-1 and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encountered from the exisUng configuraton of the nozzle weld blend radius and the adjacent reactor shell weld with the 60 degree RL scans. A other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100°h coverage. The examination limitations are shown In square Inches In order to simplify calculations. See the applicable Ultmsonic Examinatlon Umiaton Sketch.
CALCULATIONS Reaulred Examination Area: 34.89 sq. In.
Inner 15% of Weld: 4.37 sq. In.
60° Radial Scan from Shell Area Examined: 23.99 sq. In.
600 Tanaenffal Scan from Shell Area Ecamined: 6.63 sq. in.
Percent of 600 RL Scan Umited from the Adiacent Reactor Shell Weld:
Percent of 600 RL Scans Comnoleted: (23.99 + 6.63) + 2 = 15.31 + 34.89 x 100 = 43.88% - 4.7% = 39.2%
Inner 15% of Weld Area Examined: 4.37 sq. in.
Total Percent Examination Comnleted: (4.37+6.63 + 23.99). 2= 17.50 + 34.89 x 100 = 50.1% - 4.7YO = 64%
Pages of W_
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I :\
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ULTRASONIC EXAMINATION LIMITATION SKETCH R IqS-BROWNS FERRY UNIT-2 00371 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I. ~~~~~
40" L PA6bAL CAP t.A5 LIMIT6% 5I APko)U lt>rfLy z.7*4 bUC7 LIrOfF bfJ LoEL Tb E of 6, LrECLb.
Page 5s Of\ .
1:.( C4c 00382 Table 1. Browns Ferry Feedwater Nozzle (N4)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
WeldStartR 11.25 WeldEndR 15.60 Rbore 6 Rnozzle 13 Rbi 3 Rbo 3.75 Rvi 125.6875 Rvo 131.8125 Table 2. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surfice Mode of Propagation 60 +/-(35 to 67) Vessel Shear Wave 40 +/-120 Blend Shear Wave Table 3. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientaton 60 +/-(35 to 67) Vessel 17.27 20.71 9.73 14.44 20 40 +/-120 Blend 13.45 14.55 7.64 11.35 6 0
I(Q lb
Weld Examination Report R-146 (Excerpt)
00385 A
FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 12" Feedwater Nozzle to Vessel Weld N4F The Ultrasonic examInation volume Is the Nozzle to Shell weld and adjacent base material for a distance of Y% on each side of the fusion line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thIckness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entre weld examination volume and the tangential scans were used to examine the outer 85% of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitations were encounteed from the existing configuration of the nozle weld blend adius and the adjacent reactor shell weld with the 60 degree RL scans. All other angles used for ultrasonic examination of the Inner 15% of the weld yielded 100% coverage. The examination limitations are shown In square Inches In order to smplIfy calculations. See the applicable Ultrasonic Examination Umitation Sketch.
CALCULATIONS Reaulred Examination Area: 34.89 sq. In.
Inner 15% of Weld: 4.37 sq. In.
60° Radial Scan from Shell Area Examined: 23.99 sq. in.
60° Taniential Scan from Shell Area Examlned: 6.63 sq. in.
Percent of 600 RL Scan Limited from the Ad1acent Reactor Shel Weld: 4.7%
Percent of 600 R. Scans Completed: (23.99 + 6.63) + 2 = 15.31 + 34.89 x 100 = 4388% - 4.7% 39.2%
Inner 15% of Weld Area Examined: 4.37 sq. in.
Total Percent Examination Completed: (4.37 + 6.63 + 23.99)
- 2 = 17.50 + 34.89 x 100 = 50.1% - 4.7% = 4A%
Page-?of
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES I
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ULTRASONIC EXAMINATION LIMITATION SKETCH 00387 l k BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE TO VESSEL WELD N4 NOZZLES il I,
60' r-L F,ALe SC-AP w AS LIAIT', 51 APZo'kjuArELy bUC Th LFrOFF cLJ LoDEP, ToE OF 6, £AELb.
Page .&. of t
00398 A
FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INNER RADIUS EXTENSION (NUREG 0619, ZONE 3)
THERMOCOUPLE ATTACHMENT PAD LIMITATIONS N4F Each Thermooouple Attachment Pad limits Inner Radius Extenslon scan by 2.9r. There are 2 Thermocouple Attachment Pads located at approdmately 270° on N4A, N4B, N4D and N4F. (See attached Umitation Sketch)
Total Circumferential Measurement of Nozzle Boss: 81.75' Total Scan Umitation: 2.90' x 2 = 5.80' 5.80 + 81.75 x 100 = 7%LUmitation 100% - 7% = 93%
Total Nozzle Inner Radius Extenslon Coverage = 93%
Page l(O of 1' IL ('cr
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 12" FEEDWATER NOZZLE INSIDE RADIUS EXTENSION (NUREG 0619, ZONE 3)
N4 NOZZLES 803c 75 c 63,7s.
3?.7 0
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00400 Table 1. Browns Feny Feedwater Nozzle (N4)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld StartR 11.25 WeldEndR 15.60 Rbore 6 Rnozzle 13 Rbi 3 Rbo 3.75 Rvi 125.6875 Rvo 131.8125 Table 2. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shel Weld.
Probe Angie Probe Skew Scan Surface Mode of Propagation 60 +/-(35 to 67) Vessel Shear Wave 40 +/-120 Blend Shear Wave 0
Table 3. Spreadsheet Model Techniques for Feedwater Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientation 60 +/-(35 to 67) Vessel 17.27 20.71 9.73 14.44 20 40 +/-120 Blend 13.45 14.55 7.64 11.35 6 t&
Weld Examination Report R-165 (Excerpt)
00443 ' '-"
At FRAMATOME ANP ULTRASONIC EXAMINATION LIMITATION REPORT 4" Jet Pump Instrumentation Nozzle to Vessel Weld N8A The Ultrasonic examination volume Is the Nozzle to Shell weld and adjacent base material for a distance of
%" on each side of the fuslon line (Required Examination Area). This Includes the outer 85% thickness and the Inner 15% thickness as measured from the Inside diameter surface. The 60 degree RL, radial scans were used to examine the entire weld examination volume and the tangential scans were used to examine the outer 85%A of the weld examination volume. The Zone-I and Zone-2 examinations were combined to calculate examination coverage.
Ultrasonic examination limitatons were encountered from the existing configuration of the nozzle weld blend radius and the adjacent reactor shel weld with the 60 degree RL scans. All other angles used for ultasonic examination of the Inner 15%K of the weld Vielded 100% coverage. The examination limitations are shown In square Inches In order to simplify calculations. See the applicable Ultrasonic Examination Llntatlon Sketch.
CALCULATIONS Required Examination Area: 13A43 sq. In.
Inner 15% of Weld: 1.61 sq. In.
600 Radial Scan from Shell Area Examined: 12.96 sq. in.
60° Tangential Scan from Shell Area Examined: 10.76 sq. in.
Percent of 600 RL Scan Limited from the Adiacent Reactor Shell Weld: 4.8%
Percent of 600 RL Scans Comoleted: (12.96 + 10.76) + 2= 11.86+13.43 x 100 = 88.3% - 4.8%= 83.S%
Inner 15%Of Weld Area Examined: 1.61 sq. in.
Total Percent Examination Comoleted: (1.61 + 10.76 + 12.96) 2 = 12.67 + 13.43 x 100 = 94.3% - 4.8% =AmJ.
Page 2 of
ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 4" JET PUMP INSTRUMENTATION NOZZLE TO VESSEL WELD N8A NOZZLE
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00445 ULTRASONIC EXAMINATION LIMITATION SKETCH BROWNS FERRY UNIT-2 4" JET PUMP INSTRUMENTATION NOZZLE TO VESSEL WELD N8A NOZZLE SfLL X N c40
Page of
00447 Table 1. Browns Ferry Jet Pump Instrumentation Nozzle (N8)
Geometry Inputs to Spreadsheet Model for Nozzle-to-Shell Weld Examination Inside Surface Outside Surface Dimensions (inches) Dimensions (inches)
Weld Start R 3.3125 Weld End R 4.6875 Rbore 2.094 Rnozzle 4.125 Rbi 0.75 Rbo 0.75 Rvi 125.6875 Rvo 131.9375 Table 2. Spreadsheet Techniques for Jet Pump Instrumentation Nozzle-to-Shell Weld.
Probe Angle Probe Skew Scan Surface Mode of Propagation 50 :t15 to 45) Vessel Shear Wave Table 3. Spreadsheet Techniques for Jet Pump Instrumentation Nozzle-to-Shell Weld.
Probe Probe Scan Min R Max R Min MP Max MP Max Angle Skew Surface Misorientation 50 +/-(15 to 45) Vessel 6.51 10.39 7.79 10.75 8 Page '4 of