ML12066A116
| ML12066A116 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/24/2012 |
| From: | Hartz L Virginia Electric & Power Co (VEPCO), Dominion |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-069 | |
| Download: ML12066A116 (56) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 24, 2012 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.12-069 NLOS/ETS Docket No. 50-339 License No. NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ASME SECTION XI INSERVICE INSPECTION PROGRAM 10 CFR 50.55a RELIEF REQUEST N2-13-PRT-002 - LIMITED COVERAGE EXAMINATIONS PERFORMED IN THE THIRD TEN-YEAR INSPECTION INTERVAL In a letter dated September 21, 2011 (Agencywide Documents Access & Management System (ADAMS) ML11270A122), Dominion submitted a relief request for the inservice inspection (ISI) examinations of welds on the reactor vessel and pressurizer performed at North Anna Power Station Unit 2 during the third ten-year ISI interval that did not meet the ASME Code examination coverage requirements (i.e., weld coverage < 90%).
In a January 23, 2012 e-mail, the NRC requested additional information to complete the review of the limited weld examinations. The requested information is included in the attachment to this letter.
If you have any questions or require additional information regarding the attached information, please contact Mr. Thomas Shaub at (804) 273-2763.
Very truly yours, Leslie N. Hartz Vice President - Nuclear Support Services Attachment Commitments made in this letter: None 46(4-T
Serial No.12-069 Response to Request for Additional Information Third Interval ISI Limited Examination Relief Request Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738
Serial No.12-069 Docket No. 50-339 Response to Request for Additional Information ASME Section XI Inservice Inspection Program 10 CFR 50.55a Relief Request N2-13-PRT-002 - Limited Coverage Examinations Performed In the Third Ten-Year Inspection Interval Virginia Electric and Power Company (Dominion)
North Anna Power Station Unit 2
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 1 of 53 Backaround By a letter dated September 21, 2011 (Agencywide Documents Access & Management System (ADAMS) ML11270A122), the Virginia Electric And Power Company (the licensee) submitted Relief Request (RR) N2-13-PRT-002 requesting relief from the weld examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, 1995 Edition of Section XI up to the 1996 Addenda, as amended by Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a (b)(2)(xv)(A)(2). This RR covers North Anna Power Station, Unit 2 on its third inspection interval that ended on December 13, 2010.
The U.S. Nuclear Regulatory Commission (NRC) staff requests that the licensee provide additional information to support the relief from ASME Code Section Xl required volumetric examination of essentially 100% of the seven full-penetration welds.
NRC RAI 1 For Examination Category B-A and B-D items, Requests Al-A5, please address the following questions: Describe the inspection history for these welds including the inspection procedures used and the % coverage obtained in the previous inspections.
Where flaw indications were found in the most recent inspections, none of the recordable indications were recorded in the previous examinations and they were all described as subsurface weld flaws indicative of fabrication. Explain in detail why these recordable indications were not detected by previous examinations and how it was concluded that these indications are fabrication flaws.
Dominion Response Summary No. N2.Bl.11.003, 12050-WMKS-RC-R-l.1 / 4, Enclosure Al-1 (Pg. 9) -
Lower Shell to Bottom Head Spherical Ring The last examination was performed during N2R20 with 76% UT coverage, for which this relief is requested.
There were no recordable indications.
Examinations were conducted using two Trans World System (TWS) manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEXTM. The ultrasonic examinations were performed using examination procedures qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-ISI-801-02, "Automated UT of PWR Vessel Shell Welds" in accordance with Appendix VIII, Supplements 4 & 6.
Examinations of the reactor vessel circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were performed using 45' shear wave, 450 longitudinal wave, and 700 longitudinal wave transducers.
The circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were examined by scanning from four opposing beam directions such that the sound energy from the
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 2 of 53 angle beams pass through the weld metal and adjacent base material from each direction to the maximum extent possible.
The previous examination occurred during N2R14 (2 nd interval) and reported 91%
coverage. Both examinations were performed with remote tooling that had to address the same physical obstructions such as the core support lugs and incore instrumentation nozzles. Similar Appendix VIII demonstrated examination techniques were used for both examinations. The variation in reported examination volume coverage between the two examinations is attributed to the coverage calculation process. The most recent examination used direct input from the examination scan plan that controls the examination tooling and calculated the coverage using a CAD program. The previous examination coverage calculations were performed manually.
The most recent examination coverage calculations are considered more accurate as they used the direct scan positions of the examination tooling.
There were six indications identified during the N2R14 examination.
Each indication was evaluated and found acceptable according to the Code.
The Indication Assessment and Coverage Estimate Breakdowns from the 2 nd interval are attached in Enclosure RAI 1-Al-la.
Summary No. N2.B1.21.001, 12050-WMKS-RC-R-1.1 / 8, Enclosure A2-1 (Pg. 15)-
Bottom Head Spherical Ring to Bottom Head Cap The latest examination was performed during N2R20 with 75% coverage, for which this relief is requested. There were 9 recordable indications identified, evaluated and found acceptable as described in detail in Enclosure A2-1 of the original submittal.
The fabrication type indications detected during the latest examinations that were not detected during the previous examinations are due to advances in examination procedure capabilities. The process for characterizing indications as fabrication-related is based on indication location and signal characteristics.
Examinations were conducted using two TWS manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEX TM. Each ultrasonic examination was performed using an examination procedure qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-1SI-801-02, "Automated UT of PWR Vessel Shell Welds" in accordance with Appendix VIII, Supplements 4 & 6. Evaluation of recordable indications was performed to the acceptance standards of Section Xl, 1995 edition, 1996 Addenda.
The examinations of the reactor vessel circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were performed using 450 shear wave, 45' longitudinal wave, and 700 longitudinal wave transducers.
The circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were examined by scanning from four opposing beam directions such that the sound energy from the angle beams pass through the weld metal and adjacent base material from each direction to the maximum extent possible.
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 3 of 53 The previous examination occurred during N2R14 (2 nd interval) and reported 91.25%
coverage. Both examinations were performed with remote tooling that had to address the same physical obstructions such as the incore instrumentation nozzles. Similar Appendix VIII demonstrated examination techniques were used for both examinations.
The variation in reported examination volume coverage between the two examinations is attributed to the coverage calculation process. The most recent examination used direct input from the examination scan plan that controls the examination tooling and calculated the coverage using a CAD program. The previous examination coverage calculations were performed manually.
The most recent examination coverage calculations are considered more accurate as they used the direct scan positions of the examination tooling.
There were only two indications identified in the 2 nd interval examination.
Both were evaluated and found Code acceptable.
The Indication Assessment and Coverage Estimate Breakdowns from the 2 n interval are attached in Enclosure RAI 1-A2-1a.
Summary No. N2.B1.22.001, 12050-WMKS-RC-R-1.1/5, Enclosure A3-1 (Pg. 33) -
Meridional at 00 The latest examination was performed during N2R20 with 79% coverage, for which this relief is requested. No recordable indications were identified. The examinations were conducted using two TWS manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEXTM. The ultrasonic examinations were performed using examination procedures qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-ISI-801-02, "Automated UT of PWR Vessel Shell Welds" in accordance with Appendix VIII, Supplements 4 & 6.
The examinations of the reactor vessel circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were performed using 450 shear wave, 450 longitudinal wave, and 700 longitudinal wave transducers.
The circumferential, meridional, and bottom head spherical ring-to-bottom head cap welds were examined by scanning from four opposing beam directions such that the sound energy from the angle beams pass through the weld metal and adjacent base material from each direction to the maximum extent possible.
The previous examination occurred during N2R14 (2 nd interval) and reported 100%
coverage. Both examinations were performed with remote tooling that had to address the same physical obstructions such as the incore instrumentation nozzles. Similar Appendix VIII demonstrated examination techniques were used for both examinations.
The variation in reported examination volume coverage between the two examinations is attributed to the coverage calculation process. The most recent examination used direct input from the examination scan plan that controls the examination tooling and calculated the coverage using a CAD program. The previous examination coverage
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 4 of 53 calculations were performed manually.
The most recent examination coverage calculations are considered more accurate as they used the direct scan positions of the examination tooling. There were eight Code acceptable indications identified in the 2 nd interval examination. The Indication Assessment and Coverage Estimate Breakdowns from the 2 nd interval are attached in Enclosure RAI 1-A3-1a.
Summary No. N2.B3.90.001. 12050-WMKS-RC-R-1.1 / 10, Enclosure A4-1 (P-q. 39)-
Reactor Vessel Nozzle-to-Vessel Weld The latest examination was performed during N2R20 with 81 % coverage, for which this relief is requested. There were 7 recordable indications identified and evaluated as acceptable and described in detail in Enclosure A4-1 of the original submittal.
The fabrication type indications detected during the latest examination, which were not detected during the previous examinations, are contributed to advances in examination procedure capabilities. The process for characterizing indications as fabrication related is based on indication location and signal characteristics.
Examinations were conducted using two TWS manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEXTM. All ultrasonic examinations were performed using examination procedures qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-ISI-855-04, "Automated Ultrasonic Examination of Reactor Vessel Nozzle to Shell Welds and Nozzle Inner Radius Regions from the Nozzle Bore" in accordance with Appendix VIII, Supplements 7.
The inlet and outlet nozzle-to-shell welds were scanned from the vessel shell using four opposing beam directions and from the nozzle bore.
Specifically, the parallel and perpendicular scans performed from the shell examined for reflectors oriented perpendicular and parallel to the weld to a depth of at least 15% of the shell thickness (Ts). The perpendicular scan performed from the bore examined for reflectors oriented parallel to the weld for both the inner 15% Ts and outer 85% Ts. The scans performed from the bore used 450 shear wave and 150 longitudinal wave examination angles.
The evaluation of recordable indications was performed to the acceptance standards of Section Xl, 1995 edition, 1996 Addenda.
The seven indications found were not identified in 2 nd interval examination, though they were located within the weld which is indicative of fabrication anomalies. The likely reasons these indications were identified during the N2R20 examination is due to improved examination techniques and equipment.
The 2 nd interval relief Partial 1, which was granted May 24, 2002, obtained relief for 80.25% coverage.
That examination occurred during N2R14 (2 nd interval).
This coverage was essentially the same as the 3 rd interval coverage, and the nozzle configuration was the reason for the limitation. There were no indications identified in
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 5 of 53 the 2 nd interval examination. The Coverage Estimate Breakdowns from the 2 nd interval are attached in Enclosure RAI 1-A4-1a.
Summary No. N2.B3.90.003, 12050-WMKS-RC-R-1.1 / 12, Enclosure A4-2 (P-q. 50) -
Reactor Vessel Nozzle-to-Vessel Weld The latest examination was performed during N2R20 with 81% coverage, for which this relief is requested.
There were no recordable indications.
The examinations were conducted using two TWS manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEXTM.
Each ultrasonic examination was performed using examination procedures qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-ISI-855-04, "Automated Ultrasonic Examination of Reactor Vessel Nozzle to Shell Welds and Nozzle Inner Radius Regions from the Nozzle Bore" in accordance with Appendix VIII, Supplements 7.
The inlet and outlet nozzle-to-shell welds were scanned from the vessel shell using four opposing beam directions and from the nozzle bore. Specifically, the parallel and perpendicular scans performed from the shell examined for reflectors oriented perpendicular and parallel to the weld to a depth of at least 15% Ts. The perpendicular scan performed from the bore examined for reflectors oriented parallel to the weld for both the inner 15% Ts and outer 85% Ts. The scans performed from the bore used 450 shear wave and 150 longitudinal wave examination angles.
The 2 nd interval relief Partial 1, which was granted May 14, 2002, obtained relief for 80.25% coverage. The examination was performed during N2R14 (2 nd interval). This coverage was essentially the same as the 3 rd interval coverage, and the nozzle configuration was the reason for the limitation. There were no indications identified in the 2 nd interval examination. The Coverage Estimate Breakdowns from the 2 nd interval are attached in Enclosure RAI 1-A4-2a.
Summary No. N2.B3.90.005, 12050-WMKS-RC-R-1.1 / 14, Enclosure A4-3 (Pg. 54) -
Reactor Vessel Nozzle-to-Vessel Weld The latest examination was performed during N2R20 with 81% coverage, for which this relief is requested. There were 11 recordable indications identified and evaluated as acceptable, each of which is described in detail in Enclosure A4-3 of the original relief request. The fabrication type indications detected during the latest examinations that were not detected during the previous examinations are due to advances in examination procedure capabilities. The process for characterizing indications as fabrication related is based on indication location and signal characteristics.
Examinations were conducted using two TWS manipulators and AREVA's Autonmated Data Acquisition and Analysis System, ACCUSONEXTM. All ultrasonic examinations were performed using examination procedures qualified by demonstration in accordance with the requirements
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 6 of 53 of Appendix VIII of the ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. These examination requirements were implemented through AREVA procedure 54-1SI-855-04, "Automated Ultrasonic Examination of Reactor Vessel Nozzle to Shell Welds and Nozzle Inner Radius Regions from the Nozzle Bore" in accordance with Appendix VIII, Supplements 7.
The inlet and outlet nozzle-to-shell welds were scanned from the vessel shell using four opposing beam directions and from the nozzle bore. Specifically, the parallel and perpendicular scans performed from the shell examined for reflectors oriented perpendicular and parallel to the weld to a depth of at least 15% Ts. The perpendicular scan performed from the bore examined for reflectors oriented parallel to the weld for both the inner 15% Ts and outer 85% Ts. The scans performed from the bore used 450 shear wave and 150 longitudinal wave examination angles.
Evaluation of recordable indications was performed to the acceptance standards of Section Xl, 1995 edition, 1996 Addenda.
The eleven indications found were not identified in 2 nd interval examination, though they were located within the weld which is indicative of fabrication anomalies. The likely reasons these were found now is due to improved examination techniques and equipment.
The 2 nd interval relief Partial 1, which was granted May 14, 2002, obtained relief for 80.25% coverage.
The examination occurred during N2R14 (2 nd interval).
This coverage was essentially the same as the 3 rd interval coverage, and the nozzle configuration was the reason for the limitation. There were no indications identified in the 2 nd interval examination. The Coverage Estimate Breakdowns from the 2 nd interval are attached in Enclosure RAI 1 -A4-3a.
Summary No. N2.B3.110.001, 12050-WMKS-RC-E-2 / 10, Enclosure A5-1 (Pg. 71) -
Pressurizer Nozzle-To-Vessel Welds The latest examination was performed during N2R16 with 56.6% coverage.
The examinations performed in each interval were performed by scanning the accessible surface with the same examination angles to obtain the maximum examination coverage.
Essentially the same volume was examined during the two intervals.
However, the method of reporting the coverage was more conservative in the 3 rd interval resulting in a lower percentage of reported examination coverage.
The 2 nd interval relief NDE-19 (Part 2 of 6), which was granted August 8, 1995, obtained relief for 72% coverage.
Summary No. N2.B3.110.002, 12050-WMKS-RC-E-2/
11, Enclosure A5-2 (Pq. 76) -
Pressurizer Nozzle-To-Vessel Welds The latest examination was performed during N2R17 with 81%
coverage.
The examinations performed in each interval were performed by scanning the accessible
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 7 of 53 surface with the same examination angles to obtain the maximum examination coverage.
Essentially the same volume was examined during the two intervals.
However, the method of reporting the coverage used in the 3 rd interval resulted in a higher percentage of reported examination coverage.
2 nd interval relief NDE-28, granted October 10, 1996, obtained relief for 66% coverage.
Summary No. N2.B3.110.003, 12050-WMKS-RC-E-2 / 12, Enclosure A5-3 (Pg. 83) -
Pressurizer Nozzle-To-Vessel Welds The latest examination was performed during N2R17 with 81%
coverage.
The examinations performed in each interval were performed by scanning the accessible surface with the same examination angles to obtain the maximum examination coverage.
Essentially the same volume was examined during the two intervals.
However, the method of reporting the coverage used in the 3 rd interval resulted in a higher percentage of reported examination coverage.
The 2 nd interval relief NDE-28, which was granted October 10, 1996, obtained relief for 66% coverage.
Summary No. N2.B3.110.004, 12050-WMKS-RC-E-2 / 13, Enclosure A5-4 (Pg. 88) -
Pressurizer Nozzle-To-Vessel Welds The latest examination was performed during N2R17 with 81% coverage.
The examinations performed in each interval were performed by scanning the accessible surface with the same examination angles to obtain the maximum examination coverage.
Essentially the same volume was examined during the two intervals.
However, the method of reporting the coverage was more conservative in the 3 rd interval resulting in a lower percentage of reported examination coverage.
The 2 nd interval relief NDE-43, which was granted November 21, 2000, obtained relief for 89.9% coverage.
Summary No. N2.B3.110.005, 12050-WMKS-RC-E-2 / 14, Enclosure A5-5 (Pg. 93) -
Pressurizer Nozzle-To-Vessel Welds The latest examination was performed during N2R16 with 56.7% coverage.
Scans were identical to previous examination for the 2 nd interval.
The 2 nd interval relief NDE-20 (Part 1 of 4), which was granted August 8, 1995, obtained relief for 56% coverage.
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 8 of 53 Enclosure RAI 1-Al-1 a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
W4 Limitations:
No 1]
Results:
NI F1 Description/Type:
Lower Shell to Bottom Head Cal. Package ID Circ.
2 Core Support Lugs (Coverage 91%)
Yes [
NRI []
RI Z Number of Indications 6
Status:
Code Acceptable Exam Documentation:
Z Analysis Log
[]
Acquisition Log Scan Printout Indication Documentation:
Z Assessment Sheet I]
Analysis Hard Copy F1 Other (Specify)
Virgini ower Level III Virdinlia wer 9 WesDyne Level III ANII
WesDyne PLANT North Anna UNIT 2
International INDICATION ASSESSMENT ANALYST
_-_LEVEL
_11 DATE 3/25/01 P
E A
K I
zI
- 3.
I N z
d ii W4-PRP 45 0.3 0.160 z
a m
W4-PRP 45*
0.37 0.16 189-260 VGB-21 4
1 DUAL UP P
4.95 0.53 1
Sub 0.369 1
0.008 0.02 1.6 2.0 N/A 286.8 333.6 0.53 (1)
W4-PRP 450 2.17 0.19 189-260 VGB-21 4
2 shear DN P
4.95 2.42 13 Sub 2.17 1
0.095 0.03 1.9 2.0 N/A 284.5 333.8 2.35 (1)
W4-PRP 451 2.44 0.14 189-260 VGB-21 4
3 ser D
P 4.95 2.58 1
Sub 2.44 1
0.07 0.07 1.4 2.2 N/A 287 332.5 2.6 (1
W4.PRP 450 3.27 0.09 189-260 VGB-21 4
4 shear DN P
4.95 3.35 1
Sub 1.6 1
0.045 0.05 0.9 2.2 N/A 318,5 333.8 3.43 (1)
W4-PRP 450 2.32 0.04 170-189 VGB-7 4
5 shear DN P
4.95 2.35 2
Sub 2.32 1
0.02 0.01 0.4 2.0 N/A 307.5 333.6 2.48 (1)
W4-PRP
- 45.
2.93 0.125
- 170-189 VGB-7 4
6 shear UP P
4.95 3.06 1
Sub 1.89 1
0.063 0,06 1.3 2.2 N/A 306 331.8 3.1 (1)
NOTES:
Calibration Data Sheet No. V66,-2, T5 Acquisition Log Sheet No.
JLt4-(1) Code Allowable per ASME Section XI, 1995 Edition; IWB-3510-1.
Analysis Log Sheet No.
k'j *4 it
- Default thru-wall size as per procedure, m
0 C7CD M CD x-90 SCD 0
GD
-. -0 0
C(n (D Co) 0)
C.) S.
5 (0 (0
NERTH ANNA UNIT 2 DIRECTION ORIENTATION PARALLEL SCANS ee/t-'
R,V, COVERAGE ESTIMATE BREAKDOWNS PERP. SCANS ITEM/AREA Zo/rYf'*l ro u
A, elie. WELD NO, 41 BEAM ANGLES I-ro-ck^, sque -
Vill 3 FII I
T..I..
BEAM D IR E C T IO N 5'/ 1 d...L q.......
WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME CCW fy-.3 sv/3 ll-sg9~'
'~zSJ' 9_1__3
'91/3 ql.gg 9.toq gl6 29.,'
UP ( IN q Y?.1 q1221 111- :
.91'i Y4*
_,6_7 DOWN ( OUT )
qg.*
ql'*?
gl
- j.
/
BORE AXIAL A VE7RA GET9 r-
-L
-L w
CM Iq A 7 V /
/_7 CDMBINED AV\\ERAGE
/",°4 ANA L Y&T 09oi-d 0~
"-:1
~..
mD 5 0 CD
-c CD C
0 "0
o m'
-0CD 2s--
.CO ;
CD -
9,cCD j
r CD W* M~
co a 5
D CD I
oloý
SCANS BETWEEN CURE LUGS 332L99 TO TOP OF VESSEL 3281:
. SUPREEM ANGULAR SCANNING BOUNDARIES AREA BE-TWEEN PERP SCANS PARALLEL SCANS 0' -
90 9%4' 80.6*
11.0'
- 79.0' 90' 180° 99,4* -
170.6' l010° -
169.0' 180 270' 189,4" -
260.6' 191.0'
- 259.0" 270 360' 279,4' -
350,6-281,0" - 349,0' CLEVIS INSERT SHOVN x/
Notei Perform scans between support tugs first, 44 Ex.pand the 'betow' scans, If necessary, to obtain maxImum coverage,
-324,91 DTop Per'p 326,4 DTop ParoAtet 1
.329.94 322.68 WP, TO TOP OF VESSEL 80.026 fBottori Perp
-79,284 ll~oottom ParoUeL 4,95 ts m
CD a
E C CL 0.a mCD SCD U
CDC D~
C (D
Ln 60 5
(0 ED R=79.09 Weld 4 NORTH ANNA 2 -
VGB WesDyne Internationat MUNLOWER SHELL TO BOTTOM HEAD CALCULATION OF Dbot POSITION EXAM PROIGRAM PLAN ALL DMENSI°NSnINN'ýgWI SHEET 18 [IF 22 LsovisN t'r*
NOTED
SCANS UNDER CORE LUGS 33299 TO TOP OF VESSEL 3I8,3 CLE 78.5 SH I
329 82,09' DTop SUPREEM ANGULAR SCANNING BOUNDARIES BELOW LUG AT
" PERP SCANS*
PARALLEL SCANS V"
35,0.6,"
9,4' 349V0
- lr VI NET9'0, 9 0,6*
99.4' 79,0* -
01,0"
- vls INSERT JWN 180" 170,6-189.4L 169,0-191.0 2'70" 260,6-279.4v 59 0-281.0' Note, Perp Scans under Lugs 44 for increased Supptement 6 coverage (slngte-slde)
JJTop Perp 326,4 DTop Parallel I
.94 Para(tet 322.68 WP, TO TOP OF VESSEL m
0 0
CD, C_
-79,28* flkottom Parallel 52' DBottom~ Perp 1w 4.95 ts VESSEL R=79,09 Weld 4 NOIRTH ANNA 2 -
VGB WesDyne Internationad CD cCD
- g. -8 0)-~
-0 C/
-c CD CD-.9 ID) co5 3CD (b*
CALCULATION 1Fly Dbot POSITIOIN MM.LOVWER SHELL TO BOTTOM HEAD EXAM PRIGRAM PLAN
%tWLDT°NwQNRN'M SHEET 19 OF 22 I
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 13 of 53 Enclosure RAI 1 -A2-1 a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
Description/Type:
Bottom Head Ring to Disk Circ.
Cal. Package ID 2
W8 0
Limitations:
No C]
Results:
NI E]
Yes Z NRI El Instrumentation Tubes (Coverage 91.25%)
RIl Number of Indications 2
Status:
Code Acceptable Exam Documentation:
Z Analysis Log
[]
Acquisition Log
[]
Scan Printout Indication Documentation:
[
Assessment Sheet Z
Analysis Hard Copy El Other (Specify)
WesDyne Level III
..4..
1*.'A ANII' Virginia Level III Virglnia Power'ISI
WesDyne PLANT North Anna UNIT 2
Interational INDICATION ASSESSMENT ANALYST LEVEL IIl DATE 3/17/01 4/
P E
A K
- z.
0 WRP450 0.125 14-84_1 8
1-8Dual DN P
5.0 1.09 06 Sub 0.79 1
0.06 0.1 1.3 2.5 N/A 23.70 55.90 10 (2)
W8PRP 450 0.125 284-362_1 VGB-6 8
2 Dual DN P
5.00 1.26 2.6 Sub 0.96 1
0.06 0.02 1.3 2.08 N/A 321.50 56.20 1.2-(2)
NOTES:
Calibration Data Sheet No. \\]V&,- I (1) Meridional angle, weld center-line at 560 (see EPP Drawing 21).
Acquisition Log Sheet No.
F.-'(
(2) Code Allowable per ASME Section Xl, 1995 Edition; IWB-3510-1.
Analysis Log Sheet No.
m CD 1L CD
-0 M CD (I) 80-
= C8
- 0.
C/
(0 ks-z 4,CD j ý
NLIRTH ANNA UNIT 2 R,V, COVERAGE ESTIMATE BREAKDOWNS DIRECTION ORIENTATION PARALLEL SCANS PERP, SCANS
- ýCho ITEM/AREA
,aowe...-,/e'..a*.,
0-1p-e W]&
WELD NO, 9
Appcl-) J-ýlllt BEAM ANGLES BEAM JI S-d Ust 4151 s,,A DIRECTION rlIj)ý 41L$,
~e4.%
WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME COW
/dzr" go lzr* go -- ldz-T 4 cW rd go
/10*
-6 oS
/d?1-UP ( IN oi o*Ir l<*r fo 16-C* 1 s DOWN ( OUT
/laS6 lo /rm
- o BORE AXIAL A VERA&GE
,/2F Ei
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0
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0 (
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CIMBINED A VERAGE q/1 2s/o ANAL YST A!
-.t6 MIN CLAD R=79OL9 JO CLAD INDEX INCREMENT = 0,36'1 Cotcutation of Per'p. ancd PQI-oiLet Positions NOTEt THIS DRAWING REPRESENTS UNOBSTRUCTED (IDEAL) SCANS BETWEEN BOTTOM HEAD PENETRATIONS, I WELD B m
CD 2L
_u mCD CL MR CD
-oDC 0D CD CD (a CJ, z
CO CO NORTH ANNA 2 -
VGB WesDyne InternationaL LOWER HEAD CIRC, EXAM PROGRAM PLAN
[AMIDLClSIONS1NNC~i SHEET 21 OF 22 IUNLESS OTM~~WISE NOTE
W5 2 0, PENETRATION No.
DISTANCE FROM DISTANCE FROM ELEVATION TO (01,50)
VESSEL rq WELD 16 CL TOP OF VESSEL 30, 31 43,17 22.4 376.9 32, 33 45.59 20.55 375.20 34 47.89 17.91 373.63 35 49.36 16.53 37E,48 36 50.80 14.83 371034 37, 38 51.50 14.19 370.64 39, 40 53.54 2.11 368.9 41 - 44 54,21 11.6 368.3
- 45. 46 56.79 8,84 365,75 47, 48 59.26 6.4 363.1 49, 50 59.86 5.6 32.41 ALL DIMENSIONS ARE NOMINAL AND REFERENCED TO ID,1, OF CLAD SURFACE 270-900 m
Fn 0-:3Ia mCD 0 CD o
CD
-- CD Cn D
' Ca0 0)
Oc8)a 3wE NORTH ANNA 2 -
VGB WesDyne International 1806 VIEW A-A ARRANGEMENT EXAM PROGRAM PLAN ALL 1CEMW SHEET 22 OF 22
-1
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 18 of 53 Enclosure RAI 1-A3-1a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
Description/Type:
Meridional @ 0° Cal. Package ID 2
W5 Limitations:
No 0 Results:
NI El Yes El NRI E]
RI Z Exam Documentation:
Number of indications 8
Status:
Code Acceptable Indication Documentation:
0 Assessment Sheet 0
Analysis Hard copy E]
Other (Specify)
[]
0]
0]
Analysis Log Acquisition Log Scan Printout WesDyne Level III hAb9 4
t/e,/,/0 Virg.
- ower,
,..Level III Virginia Power ISI ANII
WesDyne PLANT North Anna UNIT 2
International INDICATION ASSESSMENT ANALYST LEVEL _J!_ll DATE Dl P
E A
K zz d 0 a,
z
=_,
0 o
D o
0=
- 1 LU WS-MER 45' 0.125 PRP-0 VGB-1 I
shear CW V
5.00 3.100 0.5 Sub 2.8 1
0.6 0.13 1.25 2.741 N/A 7&.02 0.5 3.1 (2)
WS-MER 45 4.443 0.22 PRP-0 VGB-1 5
2 shear CW P
5.00 4.666 1
Sub 0.33 1
1 0.11 0.11 2.2 2.58 N/A 76.57.
0.6 4.5 (2)
W5-MER 45' 0.125 PRP-O VGB-1 6
3 shear CW V
5.00 3.530 0.5 1Sub 1.4 1
0.06 0,13 1.25 2.74 N/A 72.59 0.24 3.53 (2)
WS-MER 45' 0.125 PRP-0 VGB-1 5
4 shear CCW V
5.00 3.790 0.5 Sub 1.8 1
0.06 0.13 1.25 2.74 N/A 71.86 0
3.79 (2)
WS-MER 45 4.704 0.125 PRP-0 VGB-1 5
5 shear CW P
5.00 4.760 1
Sub 0.24 1
0.06 0.03 0.6 2.52 N/A 70.78
-0.4 4.7 (2)
W5-MER 45' 0.125 PRP-0 VGB-1 5
6 shear CW V
5.00 3.700 0.5 Sub 1.3 1
0.06 0.13 1.25 2.74 N/A 68.6 0
3.7 (2)
W5-MER 450 0.125 PRP-0 VGB-1 5
4 shear CW V
5.00 4.350 0.5 Sub 0.652 1
0.06 0.13 1.25 2.74 N/A 71.86 0
4.35 (2)
(2) Code Allowable per ASME Section XW
, 1995 Edition; IWB-351 0-.
Analysis Log Sheet No.
0 3
((
(3) Weld 5 is a meridional weld located at 0 degrees m
CA)
CD C:CD a -
Cl)
M CD 03 CD 0
WesDyne PLANT North Anna UNIT 2
International INDICATION ASSESSMENT ANALYST LEVEL jjA DATE X
P E
A K
I zA z
0 W.
Z; E
~
W
~-
- a.
0
~
I L
-j 0i W5-MER 45' 4.573 0.24 PRP-0 VGB-1 5
8 shear CW P
5.00 4.815 0.5 Sub 0.19 1
0.12 0.24 2.40 3.7 N/A 62.81
-0.2 4.7 (2)
NOTES:
Calibration Data Sheet No. V6.8(4 (1) Depth of indication expressed in meridional angle depicted in technique drawings, EPP, Sheets 20,21 Acquisition Log Sheet No.
L,-*f (2) CodeAllowable perASME Section XI, 1995 Edition, IWB-3510-1.
Analysis Log Sheet No.
(3) Weld 5 Is a meridional weld located at 0 degrees m
07 21 ECD m CD
-00 M CD 5' CD 5'2-D 000 C 3z CD..
0 C
CD
NERTH ANNA UNIT 2 R,V, COVERAGE ESTIMATE BREAKDOWNS DIRECTION ORIENTATION PARALLEL SCANS PERP. SCANS ITEM/AREA
/Awr*0,b"_ viet,3 Q 0,3 WELD NO,
(,,.,,-"
BEAM ANGLES j}2+/- 'ii BEAM 1
D I R E C T I O N WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOlLUME C W
/o
/ 0o.
/00
/00
/00
/100 UP ( IN )
/o0
/00
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/
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CD (D)
CDC CD C
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/00 ANAL YST
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 22 of 53 Enclosure RAI 1-A4-1a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
Description/Type:
Cal. Package ID 1,3 W10 Outlet Nozzle Weld @ 24.980 Limitations:
No L]
Results:
NI [a Yes 0 NRI rl Nozzle configuration (Coverage 80.25%)
RI 0 Number of Indications 0
Status:
Exam Documentation:
Z Analysis Log Z
Acquisition Log Z]
Scan Printout Indication Documentation:
nl Assessment Sheet EL Analysis Hard Copy I
Other (Specify)
WesDyne Level Ill Vir6iniia wer Level III Virgnia Power ISI ANII
NDRTH ANNA UNIT 2 R,V, COVERAGE ESTIMATE BREAKDOWNS ITEM/AREA 670rie xUDZ2
-.O*A 1o DIRECTION PARALLEL SCANS PERP, SCANS WELD NO,
/
(t 2/
ORIENTATION 724J A)
/,18 0 BEAM ANGLES I
r BEAM DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME cow 6cs Q,5
ý,o 46-cOW
- 0.5 (o.6 CW (00s UP ( IN )
DOWNN ( OUT )
BORE AXIAL
/'"r" udZ A VERAG ga m
0 0
2) 2
- _R Fn CD (3
m'o D6 0 D 0 3 m C)CD CD)
CD 2,
C ol D,4
.co a 5(
AVERAGE so-5 CDMBINED ANAL YST
NOZZLE 0', 180° VOLUME EXAMINED -
69%
VOLUME NOZZLE BOSS EXAM VOLUME, SEC. XI, 1986 Ed.
AGGREGATE COVERAGE, TRANSVERSE SCANS -
60.5%
C 0
MCD mCD SCD0
-. 0 (n
00 c 2 z x--' M.
2 2 (D
n CD (0 Co NORTH ANNA 2 -
VGB WesDyne International UOUTLET NOZZLE TO SHELL TRANSVERSE SCAN LIMITATIONS ALL DZIENSIONS IN 1CH I UNLIWS OTHERW=S NO~TEDI MARCH 2001
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 25 of 53 Enclosure RAI 1-A4-1a ED 0
M CL C1j OR
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 26 of 53 Enclosure RAI 1-A4-1a C
O'
-J w
L>
I--
M (M
z
-OC
<0 In-*
I-dd3d NIH S'9L dN~d XVH 99'"T
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Li
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0~
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33 TAN MAX 8, 3 MIN R=74.5 x
z
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,,4.
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a,,
120 115 110 105 100 95 90 85 so 75
.. K,...*
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SCD
-. 0 CD CD-0
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LnCD C. 0 C.0 a CD Co
..f i l I 1 1 1 1 1 1 111111! l1 1 1 t 111 111 1 1 !1 1 DISTANCE FROM VESSEL CENTERLINE III111 TAN SCAN INDEX INCREMENT = 0.5'1 IR INDEX INCREMENT = 0.3' NORTH ANNA 2 -
VGB WesDyne Internationa(
TOUTLET IR AND TAN EXAM PROGRAM PLAN ALL DBIMONS IN INCHES SHEET 13 OF 22 UNLESS OTHERWISE NOTED
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 28 of 53 Enclosure RAI 1-A4-1a
-J LiJ
>1
-JL>I U
M 1
19E
,81C 09 017 ot, U11 00S OOE 6
iI j
ý C3 LiJ C3 Ui Zi
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0 Lii Li Li>
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-j 0~
Qf 4a:
CU Cu E3 F-LJ UI V
1:
V v
I I
[,
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062 OT 082 001 COT 012 092 08 092 OL 09 092 022 012 OC2 002 0a 061 0T 081 0
UJ z
,O U, ii i i ~ i i' M
('U 71Z d
c5-U)
Li z
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r MSHZJNI
-13SS3A JO 3NI-lb31N130 0i N131OICIMNI W08-4 30N~iSICI
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N N
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 29 of 53 Enclosure RAI 1-A4-2a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
W12 Limitations:
No El Description/Type:
Outlet Nozzle Weld @ 265.030 Yes N oc (C
Cal. Package ID 1,3 izzle configuration overage 80.25%)
Results:
NI Z NRI E]
RI F1 Number of Indications 0
Status:
Exam Documentation:
[
Analysis Log 0]
Acquisition Log 0]
Scan Printout Indication Documentation:
El Assessment Sheet E]
Analysis Hard Copy
[]
Other (Specify)
WesDyne Level III Virgionwower Level III ANII Vi~bi~id P-ower ISI
NORTH ANNA UNIT 2
DIRECTION PARALLEL SCANS PERP, SCANS ORIENTATION 7.-/r.
RV, COVERAGE ESTIMATE BREAKDOWNS ITEM/AREA Our/ld A~z,OoI
, VWi WELD NO,
/2 C--- 6 5 o3 -
BEAM ANGLES BEAM nd
/
So" DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME c~w 60.E 60-s (so,.
60.5 CCW UP ( IN )
]DOWN ( OUT BORE AXIAL
!6Is-
/(SZ-A VEDRAGE z
m 0
CD (n
ECD CL n M CD a).
CD0U 0o CD
- 0)
(0 CD Q
Cn D
C,) 0)
CLMBINED AVERAGE
~O2Sid ANAL YSST
-I'
~
NOZZLE 0, 180I VOLUME EXAMINED -
69%
NOZZLE 90% 270*
VOLUME EXAMINED 527 NOZZLE BOSS m
E (
- g. -00 go CL =
SCD I D 00 CD (0
(D-CD.-.
0 CD Ln EXAM VOLUME, SEC, XI, 1986 Ed.
AGGREGATE COVERAGE, TRANSVERSE SCANS 605%
NORTH ANNA 2 -
VGB WesDyne International pI]UTLET NOZZLE TO SHELL TRANSVERSE SCAN LIMITATIONS ALL DIDENSIONS IN INCHES UNLESS OTHWISE NOTED MARCH 2001
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 32 of 53 Enclosure RAI 1-A4-3a WesDyne International REACTOR VESSEL WELD EXAMINATION RESULTS
SUMMARY
NORTH ANNA UNIT 2 Weld No.
Description/Type:
Outlet Nozzle Weld @ 145.080 Cal. Package ID 1,3 W14 Limitations:
No [E Results:
NI I]
Yes [
NRI [
Nozzle configuration (Coverage 80.25%)
RI F]
Number of Indications 0
Status:
Exam Documentation:
0]
0]
0]
Analysis Log Acquisition Log Scan Printout Indication Documentation:
F1 Assessment Sheet LI Analysis Hard Copy E]
Other (Specify)
WesOyne Level III Vrginia' r Level IIl ANIII Virgfnia Power ISI
PLANT I UNIT NORTH ANNA 12 OPTICAL DISK# V6 6 5-62
,,S D=
P C
PROCEDURE VGB-ISI-254 REVISION I
WELD #
W14 SE-WI 14NIR
. WELD TYPE: SAFE END Calibration Data Sheet No.
Z.' 4-Acquisition Log sheet No. tkJ 4-/
ANALYSIS LOG Analysis Log Sheet No.
/w__-2_-
WN145NSSE-ON I
10IN
- NRI Weld 14 indication 1 254 deg. - 268 deg.
DK 3-24-01 WN146NSSE-ON 2
W0IN X
from 1990 data. Indication location and length DK 3-24-01 WN145NSSE-ON 5
0 FOC.
X consistent with 1990 data. Amplitude maximum DK 3-24-01 WN145-BIR-ON I
70CCW X
Is 45% DAC(functlon of contact versus immersion DK 3-24-01 WN145-BIR-ON 2
70CW X
Indications previously identified as 4a through DK 3.24-01 WN145-IRS-ON I
7OCCW X
4o were found at amplitudes below recording DK 3-24-01 WN145-IRS.ON 2
7OCW X
threshold (10-18% DAC).
DK 3-24-01 WN.. 4..SE-PAR-ONR 1
7CCW X
DAM 3-24-01 WNI45-SE-PAR-ONR 2
70CW X
DAM 3-24-01 WN145-SE-ONR 3
70,N X
DAM 3-24-01 WNI45-SE-ONR 4
70WUT X
DAM 3-24-01 WN14-SE-NR 3701 X
DM 3-4.0 0
(0
-L E CD SCD
~ 0 CD C
CD-0 CD 0
CD ý;
(0 CD I
EXAMINER
.14/
LEVEL
)
DATE.
6
"--7
/
NORTH ANNA UNIT 2 R,V, COVERAGE ESTIMATE BREAKDOWNS DIRECTION ORIENTATION PARALLEL SCANS T7/u PERP. SCANS LEoa WELD NO,
/9k
/IYS.oe' ITEM/AREA 006t V?-Le O cl BEAM ANGLES BEAM DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME CCW
_0
_ 6S
-S UP ( IN )
DOWN ( OUT )
BORE AXIAL l-a-
,'rd" A VER AGE 66_...
m 0
E7C
("
___-o o
m*
0 3 m 5 CD SD -0
~0 CD0 zz 0
0CD 0ý-
CD)O c:
c' CO C
AVERA GE go2S S CLiMBINED ANAL YST e~q -~ /
NOZZLE 0, 180°
'VOLUME EXAMINED -
69%
NOZZLE 90, 270" VOLUME EXAMINED 52%
NOZZLE BOSS m
-5 ECD CL =
M CD x.
CD 0 U)
'0 CD CD C-OCD --
Cn D 3 rlj L CD Co C.)O EXAM VOLUME, SEC. XI, 1986 Ed.
AGGREGATE COVERAGE, TRANSVERSE SCANS -
60.5%
NORTH ANNA 2 -
VGB WesDyne Internationai FIUTLET NOZZLE TO SHELL TRANSVERSE SCAN LIMITATIONS ALL DMENSIONS IN INCM I UNIESOTHERWISE NOTED MARCH 2001 I
70,110.250.290 NOZZLE SECTION AT; 270 90 0
30 U.J z
25 -
a:
w z
- r 20 Ni z
2:
0 I i i i I I
i I I
i t
i i I i iL
-Ii I I I i
I
.ýj II II lIl I II I 120 115 1 10 Jos 100 95 90 85 80 75 0[STANCE FROM VESSEL CENTERLINE (in) m cn
-5( 3 0)
-I mCD 0 CD o c 0o CD 0)--'--
c MCD) 0 Co O)
W.
a
- 3 CO(
REACTOR VESSEL INSERVICE INSPECTION NORTH ANNA UNIT 2 TECHNIQUE DRAWING OUTLET NOZZLE WESTINGHOUSE ELECTRIC CORPORATION MMDT-ISI -VGB--CAMP-0t I9~
4 - ~
~1
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 37 of 53 NRC RAI 2 -- Sections B2, B3, B4, B5, B6, and R1 To determine the level of safety significance for each weld and/or attachment, NRC staff needs to know which system would be impacted by a leak or failure of the weld or welded attachment in question. This information is provided in the enclosures for some, but not all welds. To assist the NRC staff in assessing each weld and welded attachment, please provide.a table for all welds and welded attachment in Request Numbers B2, B3, B4, B5, B6, and R1 that describes the locations of each weld or welded attachment, the components joined by each weld, and the systems to which each welds or welded attachment belongs.
An example where enough information was given was in section R1 Weld 9 (R1-9). The enclosure described weld Ri1-9 as a reactor coolant pump discharge to cold leg pipe weld. This identifies the system, location, and the components joined by the weld.
Dominion Response Complete component ID, including the isometric drawing, line number with line size or component ID and weld number is located in column 2 of Table 1 on Pages 5 & 6 of 383 in the original request for all welds. For clarification the information is tabulated below:
Line NoJ System Comp. ID Description B2 Pressure Vessels - Intearallv Welded Attachments (Cateaorv C-C. Item No. C3.10)
WS-1 RH WS-2 RH WS-3 SI 2-RH-E-1 B 2-RH-E-1 B 2-SI-TK-2 Residual Heat Removal Exchanger Lower Support Residual Heat Removal Exchanger Lower Support Boron Injection Tank Support B3 Piping - Inte-qrally Welded Attachments (Category C-C, Item No. C3.20)
SW-92 MS 45H 46H 52H 66H FW FW QS SI 32"-SHP-401 16"-WFPD-424 16"-WFPD-424 8"-QS-403 3"-SI-456 32" Main Steam Line Off Steam Generator 2-RC-E-1A 16" Feedwater Line To Steam Generator 2-RC-E-1A 16" Feedwater Line To Steam Generator 2-RC-E-1A 8" Discharge line from Quench Spray Pump 2-QS-P-1A Inside QS Pump House 3" Safety Injection Line near 2-SI-MOV-2836 in the Auxiliary Building B4 Pumps - Integrally Welded Attachments (Cateqory C-C, Item No. C3.30)
WS-01 CH WS-02 CH WS-03 CH 2-CH-P-1 B 2-CH-P-1 B 2-CH-P-1 B Centrifugal Charging Pump 2-CH-P-1 B Lug Centrifugal Charging Pump 2-CH-P-1 B Lug Centrifugal Charging Pump 2-CH-P-1 B Lug Centrifugal Charging Pump 2-CH-P-1 B Lug WS-04 CH 2-CH-P-1 B
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 38 of 53 Nominal Wall Thickness fnr Pininai > NPS 4 UCatennrv C-F-l_
Pr,
(_irn" if,=r~nnil-Pininn \\Alile
>':I/R in U*
UlllmtJl II1*1
- 1 III*AI I
lull IU VV*IU*
- llU II I.
Item No. C5.11) 6A 4A 66 RS RS RS 2
SI 1
RH SW-56 RH B6 Circumferer (Category C-F-SW-49W CH 2A CH SW-64 SI 23A SI 12"-RS-407 12"-RS-408 1 0"-RS-41 0 16"-SI-407 6"-SI-570 6"-SI-570 8"-CH-605 8"-SI-440 1 0"-RH-413 6"-RH-417 ntial Piping Welds >1/5 in.
1, Item No. C5.21) 3"-CH-402 3"-CH-403 3"-SI-424 3"-SI-423 3"-SI-536 3"-SI-571 12" Upstream Piping Weld at 2-RS-MOV-255A near inlet of Outside Recirculation Spray Pump 2-RS-P-2A 12" Downstream Piping Weld at 2-RS-MOV-255B near inlet of Outside Recirculation Spray Pump 2-RS-P-2B 10" Upstream Piping Weld at 2-RS-MOV-256B on discharge of Outside Recirculation Spray Pump 2-RS-P-2B outside reactor containment Discharge side of manual valve 2-QS-33, at Refueling Water Storage Tank 2-QS-TK-1, 16" Charging Pump Suction Line Boron Injection Tank 2-SI-TK-2 Discharge 6" Nozzle To Safe End Weld Boron Injection Tank 2-SI-TK-2 Inlet 6" Nozzle To Safe End Weld 8" Charging Pump Suction Pipe on downstream side of 2-CH-MOV-2115D, Auxiliary Building 8" Charging Pump Suction Pipe on downstream side of 2-CH-MOV-2863A, Auxiliary Building 10" RHR Return Piping on inlet side of 2-RH-MOV-2720B in Reactor Containment Weld at 6" elbow off of RHR Return Piping in Reactor Containment Nominal Wall Thickness for Piping > NPS 2 and < NPS 4 3" HPSI Pipe To MOV-2370 in the radioactive pipe chase 3" HPSI Pipe To MOV-2370, weld on the downstream side of 2-CH-MOV-86A, Auxiliary Building 3" HPSI Piping From Boron Injection Tank 2-SI-TK-2 Outside Reactor Containment 3" HPSI Piping To Boron Injection Tank 2-SI-TK-2 on Downstream side of 2-SI-MOV-2867A Outside Reactor Containment 3" HPSI Piping To Boron Injection Tank 2-SI-TK-2 on Upstream side of 2-SI-MOV-2869B Outside Reactor Containment 3" HPSI Piping To Boron Injection Tank 2-SI-TK-2 on Upstream side of 2-SI-MOV-2867B Outside Reactor Containment 7A SI SI 24A
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 39 of 53 B6 Circumferential Pipincq Welds >1/5 in. Nominal Wall Thickness for Pipingq > NPS 2 and < NPýS 4 (Category C-F-i, Item No. C5.21)
(continued) 26 SI 3"-SI-571 3" HPSI Piping To Boron Injection Tank 2-SI-TK-2 on Downstream side of 2-SI-MOV-2867B Outside Reactor Containment SW-39W CH 2"-CH-422 2" HPSI Pipe to MOV-2373 at a 3" to 2" reducer R1 Risk-Informed PiDina Welds (Cateaorv R-A. Item No. R1.11) 2 20 1
2 1
2B 80 SW-5 9
SW-43 21 33 SW-49 SW-36 SW-9 SW-17 RC SI RC RC RC RC RC RC RC RC RC RC RC RC RC RC 6"-RC-421 3"-SI-417 6"-RC-417 6"-RC-417 6"-RC-420 6"-RC-420 6"-RC-419 14"-RC-41 0 27 1/2"-RC-403 27 1/2"-RC-403 27 1/22"-RC-406 27 1/2"-RC-409 27 1/22"-RC-409 29"-RC-407 6"-RC-438 6"-RC-439 6" Weld at Nozzle Into 29" Hot Leg From Low Head Safety Injection Upstream side of check valve inside reactor containment at penetration on 3" HPSI line from Boron Injection Tank Weld on downstream side of check valve 2-SI-92 on piping to Loop 1 Cold Leg Piping to inlet nozzle weld to Loop 1 Cold Leg Weld on downstream side of check valve 2-SI-106 on piping to Loop 3 Cold Leg Piping to inlet nozzle weld to Loop 3 Cold Leg Weld on downstream side of check valve 2-S1-100 on piping to Loop 2 Cold Leg Pressurizer Nozzle-To-Safe End weld on the Surge Line, examined prior to full structural weld overlay Weld at Reactor Coolant Pump 2-RC-P-1A discharge, Loop 1 Cold Leg 6" Schedule 160 Nozzle to Loop 1 Cold Leg Weld, with thermal sleeve, line from Low Head Safety Injection Weld at Reactor Coolant Pump 2-RC-P-1 B discharge, Loop 2 Cold Leg Weld at Reactor Coolant Pump 2-RC-P-1 C discharge, Loop 3 Cold Leg 6" Schedule 160 Nozzle to Loop 3 Cold Leg Weld, with thermal sleeve, line from Low Head Safety Injection Hot Leg to 14" Schedule 160 Nozzle Weld, with thermal sleeve, Pressurizer Surge Line Nozzle-To-Safe End weld at Pressurizer to safety valve 2-RC-SV-2551 B line, examined prior to full structural weld overlay Nozzle-To-Safe End weld at Pressurizer to safety valve 2-RC-SV-2551A line, examined prior to full structural weld overlay
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 40 of 53 R1 Risk-Informed Piping Welds (Category R-A, Item No. R1.11)
N-SE29 IN. RC 29"-RC-401 Steam Generator 2-RC-E-1A integrally forged hotleg nozzle to safe end weld N-SE31 IN. RC 31"-RC-402 Steam Generator 2-RC-E-1A integrally forged coldleg nozzle to safe end weld 22 RC 27 1/22"-RC-406 Weld on inlet side of Loop Stop Valve 2-RC-MOV-2593, Reactor Coolant Pump 2-RC-P-1 B discharge side, Loop 2 Cold Leg
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 41 of 53 NRC RAI 3 -- Section B4 To demonstrate impracticality, the reason for the reduced inspection coverage is required. While the coverage maps are effective at showing where the welds were not inspected, nothing in the submittal explains why these regions were not inspected. Explain in detail the causes of the lack of access to these areas.
Dominion Response The integrally welded lugs are attached to the sides of the Centrifugal Charging Pump in four locations as shown in the attached figures and photos (Figures 1 -
5).
As shown, the bottom of these supports is inaccessible because of the pump support pedestal on which the lugs rest. All accessible portions of the welds were examined.
RAI 3 Figure 1 Charging Pump 2-CH-P-IB Top View ANC
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 42 of 53 RAI 3 Figure 2 Charging Pump 2-CH-P-1B Elevation View CHARGING PUMP PUMP BASE' ELEVATION VIEW
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 43 of 53 RAI 3 Figure 3 Charging Pump 2-CH-P-1B End View DISCHARGE NOZZLE END VIEW
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 44 of 53 RAI 3 Figure 4 Charging Pump 2-CH-P-1B Photo
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 45 of 53 RAI 3 Figure 5 Charging Pump 2-CH-P-1B, Weld WS-01 Lug Photo
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 46 of 53 NRC RAI 4 -- Section B5 While the data sheets provided in the enclosures partially described the ultrasonic techniques used to inspect the welds, the refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for both axial and circumferential scans were not always clear. Please provide a table describing the weld, the angles, modes, and frequencies used for axial scans and the angles, modes, and frequencies used for circumferential scans.
Coverage of some piping welds has been improved by removing weld crowns. For several welds in Section B5 the coverage maps show that the transducers appear to stop at the edge of the weld crown.
For each weld, discuss if greater coverage can be obtained by grinding or machining the weld crowns flush with the pipe.
The overall size of a weld, commonly described by the weld diameter, is needed to help determine the safety significance of a weld and the possible consequences of a leak or failure in the weld. Please provide the outer diameters of welds B5-5, B5-6, and B5-8. For dissimilar metal welds, the cracking rates are influenced by the weld alloys and the temperatures at the welds. For welds B5-5 and B5-6, the welds are listed as dissimilar metal welds, but the weld metal is not specified. What are the weld metal alloys for these welds and what are the operating temperatures of these welds?
Dominion response The data sheets provided fully describe the Code required examination data collected for each of these examinations.
Examinations performed earlier in the interval had different requirements, in some cases, and the procedures and processes were different than those used later in the interval. Table 1, attached, tabulates the requested refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for each of the scans, as recorded on the data sheets.
When performing single sided ultrasonic examinations using ASME Section XI, Appendix VIII, Supplement 2 qualified procedures, effective examination coverage is limited to the near side of the weld. The examination coverage on the far side of the weld centerline is addressed as "best effort" coverage applying supplemental examination techniques.
Removing the weld crown for weld configurations limited to single side examinations will not provide additional qualified examination volume coverage. For the limited examinations included in this request, there will be no significant increase in coverage by removing weld crowns.
The weld size was provided on each of the data sheets provided in the original submittal, as well as in the line numbering nomenclature provided for each weld (Section 4.B5, page 155).
Line numbers include three parts:
- 1) the first number designates the line size, 2) the letter designation for the applicable system (i.e., RC - Reactor Coolant, SI - Safety Injection, etc.), and 3) a unique designation number for each line. The line numbering is more clearly stated in Table 1. Enclosure B5-5 is for a 6-inch weld on a Safety Injection system line (page 190). Enclosure B5-6 is for a 6-inch weld on a Safety Injection system line (page 199). Enclosure B5-8 is for an 8-inch weld on a Safety Injection system line (page 211).
Enclosure B5-5, weld SW-73, is the nozzle-to-safe end weld at the inlet of the Boron Injection Tank (BIT).
Enclosure B5-6, weld SW-55, is the nozzle-to-safe end weld at the discharge of the Boron Injection Tank.(BIT). The boron injection tanks have carbon steel inlet and outlet nozzles which have Alloy 82/182 butter and welds connecting them to stainless steel safe ends. The tank is heated by strip heaters that maintain the temperature between about 145 0F and 155 0F so that the boric acid will not
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 47 of 53 precipitate out of solution. Because the water chemistry in the tank does not closely resemble normal reactor coolant and because the normal operating temperature is lower, the susceptibility of the nozzle butter and welds to PWSCC is considered very low.
NRC RAI 5 -- Section B6 While the data sheets provided in the enclosures partially described the ultrasonic techniques used to inspect the welds, the refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for both axial and circumferential scans were not always clear. Please provide a table describing the weld, the angles, modes, and frequencies used for axial scans and the angles, modes, and frequencies used for circumferential scans.
The overall size of a weld, commonly described by the weld diameter, is needed to help determine the safety significance of a weld and the possible consequences of a leak or failure in the weld. Please provide the diameters of welds B6-2 and B6-8.
Dominion Response The data sheets provided fully describe all the Code required examination data collected for each of these examinations. Examinations performed earlier in the interval had different requirements, in some cases, and the procedures and processes were different than those used later in the interval. Table 1, attached, tabulates the requested refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for each of the scans, as recorded on the data sheets.
The weld size was provided on each of the data sheets supplied in the original relief request provided in the original submittal, as well as in the line numbering nomenclature provided for each weld (Section 4.B6, page 225). Line numbers include three parts: 1) the first number designates the line size, 2) the letter designation for the applicable system (i.e., RC - Reactor Coolant, SI - Safety Injection, etc.), and
- 3) a unique designation number for each line. The line numbering is more clearly stated in Table 1.
Weld # 2A, Enclosure B6-2 (Pg. 232), is a 3-inch Chemical and Volume Control (CH) system component.
Weld # SW-39W, Enclosure B6-8 (Pg. 273), is a 2-inch Chemical and Volume Control (CH) system component.
RAI 6 -- Section R1 While the data sheets provided in the enclosures partially described the ultrasonic techniques used to inspect the welds, the refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for both axial and circumferential scans were not always clear. Please provide a table describing the weld, the angles, modes, and frequencies used for axial scans and the angles, modes, and frequencies used for circumferential scans.
The overall size of a weld, commonly described by the weld diameter, is needed to help determine the safety significance of a weld and the possible consequences of a leak or failure in the weld. Please provide the diameters of welds R1-10, R1-15, R1-16, R1-17, and R1-18.
Serial No.12-069 Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 48 of 53 Dominion Response The data sheets provided in the original relief request fully describe all the Code required examination data collected for each of these examinations.
Examinations performed earlier in the interval had different requirements in some cases, and the procedures and processes were different than those used later in the interval. Table 1, attached, tabulates the requested refracted ultrasonic angles, wave modes (shear or longitudinal), and frequencies used for each of the scans, as recorded on the data sheets.
The weld size was provided on each of the data sheets provided in the original submittal, as well as in the line numbering nomenclature provided for each weld (Section 4.R1, page 279).
Line numbers include three parts:
- 1) the first number designates the line size, 2) the letter designation for the applicable system (i.e., RC - Reactor Coolant, SI - Safety Injection, etc.), and 3) a unique designation number for each line. The line numbering is more clearly stated in Table 1.
Weld # SW-43, Enclosure R1-10 (Pg. 335), is a 27 1/2-inch Reactor Coolant (RC) system component.
Weld # SW-9, Enclosure R1-15 (Pg. 353), is a 6-inch Reactor Coolant (RC) system component.
Weld # SW-17, Enclosure Rl-16 (Pg. 361), is a 6-inch Reactor Coolant (RC) system component.
Weld # N-SE29 IN., Enclosure R1-17 (Pg. 369), is a 29-inch Reactor Coolant (RC) system component.
Weld # N-SE31 IN., Enclosure R1-18 (Pg. 369), is a 31-inch Reactor Coolant (RC) system component.
Serial No.12-069, Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 49 of 53 Table 1 Page 1 of 5 Scan te2 Coverage Exam Weld Line # No Enclosure Exam Note1 Date Page Angle Mode Frequency 6A 12"-RS-407 42.50%
85-1 Up/Dwn/CW/CCW 3/24/2010 158 450 Shear 2.25MHZ Up/Dwn/CW/CCW 159 600 Shear 2.25MHZ Up/Dwn 160
- 70.
Shear 2.25MHZ 4A 12"-RS-408 88%
85-2 Up/Dwn/CW/CCW
.9/6/2002 177 450 Shear 5.0MHZ Up/Dwn/CW/CCW 177 600 Shear 1.5MHZ 66 10"-RS-410 50%
85-3 Up/Dwn/CW/CCW 3/21/2010 180 450 Shear 5.0MHZ Up/Dwn/CW!CCW 181 600 Shear 5.OMHZ Up/Dwn 182 700 Shear 5.0MHZ Up 183 700 Shear 2.25MHZ 2
16"-SI-407 48%
85-4 Up/Dwn/CW/CCW 4/4/2010 185 450 Shear 5.0MHZ Up/Dwn/CW/CCW 186 600 Shear 5.0MHZ Up/Dwn 187 700 Shear 5.0MHZ Up/Dwn 188 700 Shear 2.25MHZ SW-73 6"-SI-570 54.50%
B5-5 CW/CCW 10/8/2005 191 450 Longitudinal 2.0MHZ Up/Dwn 191 450 Shear 1.5MHZ CW/CCW 191 60' Longitudinal 2.0MHZ Up/Dwn 191 400 Longitudinal 2.0MHZ Up/Dwn 191 400 Shear 1.5MHZ SW-55 6"-SI-570 60.50%
B5-6 CW/CCW 4/8/2006 200 450 Longitudinal 2.0MHZ Up/Dwn 200 450 Shear 1.5MHZ CW/CCW 200 600 Longitudinal 2.0MHZ Up/Dwn 200 40 Longitudinal 2.0MHZ Up/Dwn 200 400 Shear 1.5MHZ 14 8"-CH-605 50%
B5-7 Dwn/CW/CCW 3/31/2007 208 600 Shear 5.0MHZ Up 209 700 Shear 2.25MHZ 1
8"-SI-440 49.50%
85-8 Up/Dwn/CW/CCW 10/5/2005 213 450 Shear 5.0MHZ Up/Dwn/CW/CCW 213 600 Shear 5.0MHZ Up/Dwn/CW/CCW 213 700 Shear 2.25MHZ 1
10"-RH-413 50%
85-9 Up/Dwn/CW/CCW 4/5/2010 215 450 Shear 2.25MHZ Up/Dwn/CW/CCW 216 600 Shear 2.25MHZ Up/Dwn 217 700 Shear 2.25MHZ Up/Dwn 218 600 Longitudinal 2.0MHZ SW-56 6"-RH-417 88%
B5-10 Up/Dwn/CW/CCW 3/27/2007 220 600 Shear 5.0MHZ Dwn 221 700 Shear 2.25MHZ SW-49W 3"-CH-402 47%
86-1 Dwn 4/8/2007 227 700 Shear 2.25MHZ Up/CW/CCW 228 60° Shear 2.25MHZ
Serial No.12-069.
Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 50 of 53 Table 1 Page 2 of 5 Scan Coverage Exam Weld Line # Note 2 Enclosure Exam Note 1 Date Page Angle Mode Frequency 2A 3"-CH-403 63%
B6-2 Up/Dwn 10/10/2005 234 450 Shear 5.0MHZ Up/Dwn 234 60' Shear 5.0MHZ Up/Dwn 234 700 Shear 5.0MHZ Up/Dwn/CW/CCW 234 70-Shear 2.25MHZ SW-64 3"-SI-424 50%
B6-3 Up/CW/CCW 4/1/2007 238 60° Shear 5.0MHZ Dwn 239 70-Shear 2.25MHZ 23A 3"-SI-423 47%
86-4 CW/CCW 3/26/2007 243 450 Shear 5.0MHZ Dwn/CW/CCW 245 60' Shear 5.0MHZ Up 247 700 Shear 2.25MHZ 7A 3"-SI-536 50%
16-5 Up/CW/COW 10/11/2008 250 450 Shear 2.25MHZ Up/CW/CCW 251 600 Shear 2.25MHZ Dwn 252 700 Shear 2.25MHZ 24A 3"-SI-571 50%
B6-6 Up/CW/CCW 257 450 Shear 5.0MHZ Up/CW/CCW 258 600 Shear 5.0MHZ Up/CW/CCW 259 700 Shear 5.0MHZ Dwn 260 700 Shear 2.25MHZ 26 3"-SI-571 50%
86-7 Dwn/CW/CCW 4/2/2010 265 450 Shear 5.0MHZ Dwn/CW/CCW 266 600 Shear 5.0MHZ Dwn/CW/CCW 267 700 Shear 5.0MHZ Up 268 70*
Shear 2.25MHZ SW-39W 2"-CH-422 88%
86-8 Up/Dwn 10/6/2005 275 450 Shear 5.0MHZ Up/Dwn 275 600 Shear 5.0MHZ Up/Dwn/CW/CCW 275 700 Shear 5.0MHZ Up/Dwn/CW/CCW 275 700 Shear 2.25MHZ 2
6"-RC-421 89%
Ri-1 Up/Dwn/CW/CCW 9/21/2008 286 450 Shear 2.25MHZ Up/Dwn/CW/CCW 287 60' Shear 2.25MHZ Up/Dwn 288 700 Shear 2.25MHZ Dwn 289 600 Longitudinal 2.0MHZ
Serial No.12-069, Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 51 of 53 Table 1 Page 3 of 5 Scan Coverage Exam Weld Line #
%ote2 Enclosure Exam "ote 1 Date Page Angle Mode Frequency 20 3"-SI-417 53%
R1-2 Up/Dwn/CW/CCW 10/12/2005 296 450 Shear 5.0MHZ Up/Dwn/CW/CCW 296 60' Shear 5.0MHZ Up/Dwn/CW/CCW 296 70° Shear 2.25MHZ 1
6"-RC-417 50%
R1-3 Dwn/CW/CCW 4/2/2010 297 450 Shear 2.25M HZ Dwn 298 60, Shear 2.25MHZ Up 299 60° Longitudinal 2.0MHZ 2
6"-RC-417 88%
R1-4 Up/Dwn/CW/CCW 4/2/2010 301 450 Shear 2.25MHZ Up/Dwn 302 600 Shear 2.25MHZ Up/Dwn 303 600 Longitudinal 2.0MHZ 1
6"-RC-420 50%
R1-5 Up/Dwn/CW/CCW 9/21/2008 305 450 Shear 2.25MHZ Up/Dwn/CW/CCW 306 60' Shear 2.25MHZ Up 307 700 Shear 2.25MHZ Dwn 308 600 Longitudinal 2.0MHZ 2B 6"-RC-420 50%
R1-6 Up/Dwn/CW/CCW 9/21/2008 310 450 Shear 2.25MHZ Up/Dwn/CW/CCW 311 600 Shear 2.25MHZ Up 312 700 Shear 2.25MHZ Dwn 313 600 Longitudinal 2.0MHZ 80 6"-RC-419 50%
R1-7 Up/CW/CCW 3/28/2007 316 600 Shear 2.25MHZ Dwn 317 600 Longitudinal 2.0MHZ SW-5 14"-RC-410 75%
R1-8 Up/Dwn/CW/CCW 5/5/2004 322 450 Shear 1.0MHZ Up/Dwn 10/6/2005 328 400 Longitudinal 2.0MHZ Up/Dwn 328 500 Longitudinal 2.0MHZ Up/Dwn 328 450 Shear 1.5MHZ CW/CCW 328 420 Longitudinal 1.5MHZ CW /CCW 328 40-Shear 1.5MHZ 9
27 /2'-RC-403 49.90%
R1-9 CW/CCW 3/27/2007 331 450 Longitudinal 1.0MHZ Up/Dwn 332 450 Longitudinal 1.0MHZ
Serial No.12-069 V Docket No. 50-339 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 52 of 53 Table 1 Page 4 of 5 Scan Coverage Exam Weld Line #
%t2 Enclosure Exam Note1 Date Page Angle Mode Frequency SW-43 27 W'-RC-403 36%
Rl-10 Up/Dwn 9/29/2002 336 450 Longitudinal 1.0MHZ CW/CCW 336 450 Longitudinal 1.0MHZ 21 27 12"-RC-406 50%
R1-11 CW/CCW 3/29/2010 339 450 Longitudinal 1.0MHZ Dwn 340 450 Longitudinal 1.0MHZ Up 341 600 Longitudinal 1.0MHZ 33 27 1/22"-RC-409 75%
Ri-12 Dwn/CW/CCW 9/22/2008 344 450 Longitudinal 1.0MHZ Up 345 600 Longitudinal 1.0MHZ SW-49 27
'"-RC-409 35%
Ri-13 Dwn/CW/CCW 9/22/2008 347 450 Longitudinal 1.0MHZ SW-36 29"-RC-407 52%
R1-14 Up/CW/CCW 9/22/2008 350 450 Longitudinal 1.0MHZ SW-9 6"-RC-438 63%
Ri-15 Up/Down 10/6/2005 354 450 Longitudinal 2.0MHZ Up/Down 10/6/2005 354 600 Longitudinal 2.0MHZ Up/Down 10/6/2005 354 450 Shear 1.5MHZ CW/CCW 10/6/2005 354 340 Longitudinal 1.5MHZ CW/CCW 10/6/2005 354 400 Shear 1.5MHZ SW-17 6"-RC-439 53%
R1-16 Up/Down 10/6/2005 362 450 Longitudinal 2.0MHZ Up/Down 10/6/2005 362 600 Longitudinal 2.0MHZ Up/Down 10/6/2005 362 450 Shear 1.5MHZ CW/CCW 10/6/2005 362 340 Longitudinal 2.0MHZ CW/CCW 10/6/2005 362 400 Shear 1.5MHZ N-SE29 IN.
29"-RC-401 80%
Rl-17 Up/Down 10/1/2002 370 450 Longitudinal 1.0MHZ CW/CCW 10/1/2002 370 450 Longitudinal 1.0MHZ Up/Down 10/1/2002 370 34' Longitudinal 1.0MHZ N-SE31 IN.
31"-RC-402 80%
Rl-18 Up/Down 10/1/2002 374 450 Longitudinal 1.0MHZ CW/CCW 10/1/2002 374 450 Longitudinal 1.0MHZ Up/Down 10/1/2002 374 340 Longitudinal 1.0MHZ
Serial No.12-069?,
Docket No. 50 Response to Request for Information Third Interval ISI Limited Examination Relief Request Page 53 of 53 Table 1 Page 5 of 5 Scan Coverage Exam Weld Line # Nte2 Enclosure Exam Note 1 Date Page Angle Mode Frequency 22 27 '/2"-RC-406 50%
R1-19 Up 3/29/2010 378 450 Longitudinal 1.0MHZ CW/CCW 3/29/2010 377 450 Longitudinal 1.0MHZ Dwn 3/29/2010 379 600 Longitudinal 1.0MHZ NOTES:
1 Up Axial scan on the upstream side of weld Dwn Axial scan on the downstream side of weld CW Circumferential scan in the clock-wise direction CCW Circumferential scan in the counter clock-wise direction 2
The "Line #" is made up of the nominal pipe size (in inches), the system designator, and a unique identifying number.
RC - Reactor Coolant System SI - Safety Injection System CH - Chemical and Volume Control System RS - Recirculation Spray System FW - Feedwater System MS - Main Steam System RH - Residual Heat Removal System QS - Quench Spray System