ML090820492
| ML090820492 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/20/2009 |
| From: | Cahill S Progress Energy Florida |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML090820492 (97) | |
Text
&Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.55a March 20, 2009 3F0309-01 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Third Ten-Year Inservice Inspection (ISI) Interval Relief Requests #09-001-11, #09-002-11 and #09-003-11
Dear Sir:
Pursuant to 10 CFR 50.55a(g)(5)(iii), Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., hereby submits Relief Requests #09-001-11 and #09-002-11.
In addition, pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5) and 10 CFR 50.55a(a)(3)(i), FPC hereby submits Relief Request #09-003-11. The purpose of these relief requests is to seek approval for limited volumetric examinations performed on ASME Code Class 1 piping and nozzles, ASME Code Class 2 piping and nozzles, and on the ASME Code Class 1 Reactor Pressure Vessel Shell, respectively, during the Crystal River Unit 3 (CR-3) Third Ten-Year Inservice Inspection (ISI) Interval. These examinations covered less than 90 percent of the weld volume required to be examined by the ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, no Addenda. These examinations were limited due to geometry or by interferences with other components.
The Third Ten-Year ISI Interval for CR-3 ended on August 13, 2008.
FPC is requesting approval of these relief requests prior to August 14, 2009.
No new regulatory commitments are made in this submittal.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.
Sincerely, Stephen J. Cahill Manager, Engineering Crystal River Nuclear Plant SJC/dwh
Enclosures:
- 1. Relief Request #09-001 -11
- 2. Relief Request #09-002-11
- 3. Relief Request #09-003-11 xc:
NRR Project Manager Regional Administrator, NRC Region II Senior Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ENCLOSURE I INSERVICE INSPECTION RELIEF REQUEST #09-001-11 THIRD TEN-YEAR ISI INTERVAL
U. S. Nuclear Regulatory Commission 3F0309-01 Page 1 of 7 10 CFR 50.55a Request #09-001 -11 Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1.
ASME Code Component(s) Affected ASME Code Class 1 Piping and Nozzles Categories:
B-D, B-J, B-M-1 and R-A Items:
B3.110, B3.120, B3.130, B3.140, B9.21, B12.40 and R1.20.
- 2.
Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, no Addenda
- 3.
Applicable Code Requirement
ASME Code, Section Xl, Sub-article IWB-2500, states, in part, "Components shall be examined and tested as specified in Table IWB-2500-1." Table IWB-2500-1 requires an examination of applicable Class 1 pressure retaining-welds, which includes 100 percent of weld length once during the ten-year ISI interval for the following Code Categories:
Category B-D:
Items B3.110, B3.120, B3.130 and B3.140 Category B-J:
Items B9.21 Category B-M-1:
Items B12.40 Category R-A:
Items R1i.20 A risk-informed in-service inspection (RI-ISI) program for Crystal River Unit 3 (CR-3) was approved by the NRC on September 20, 2005. The RI-ISI was developed for Class 1 piping welds for the Category B-F and B-J circumferential piping welds in a manner consistent with ASME Code, Section Xl, Code Case N-578. Code Case N-578 requires 100 percent of the required volume of the weld and adjacent base material to be examined for Examination Category R-A, Item R1.20.
Code Case N-460 permits a reduction in examination coverage of Class 1 and Class 2 welds, provided the coverage reduction is less than 10 percent.
CR-3 has adopted Code Case N-460 in the Inservice Inspection (ISI) Program Plan, as permitted by NRC Regulatory Guide 1.147, Revision 15, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1."
- 4.
Impracticality of Compliance At the time CR-3 was constructed, the ASME Boiler and Pressure Vessel Code only addressed nuclear vessels and associated piping up to and including the first isolation valve. The piping codes of record were USAS B31.7, 1968 Edition for nuclear piping, and USAS B31.1.0-1967 Edition for non-nuclear piping.
U. S. Nuclear Regulatory Commission 3F0309-01 Page 2 of 7 10 CFR 50.55a recognizes the limitations to in-service inspection of components in accordance with Section Xl of the ASME Code that are imposed due to early plants design and construction, as follows: 10 CFR 50.55a(g)(1), "For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1, 1971, components (including supports) must meet the requirements of paragraphs (g)(4) and (g)(5) of this section to the extent practical." 10 CFR 50.55a(g)(1) is applicable since the CR-3 construction permit was dated September 25, 1968.
10 CFR 50.55a(g)(4) states, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section Xl of editions of the ASME Boiler and Pressure Vessel Code... to the extent practical within the limitations of design, geometry and materials of construction of the components."
10 CFR 50.55a(g)(5)(iii) states, "If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in
§ 50.4, information to support the determinations."
CR-3 has determined that the following welds were limited from achieving greater than 90 percent of the required examination volume for in-service examinations due to component configuration or physical barriers, which would require a major modification to the existing hardware.
Therefore, relief is being sought from coverage requirements set forth in ASME Code, Section Xl, Sub-article IWB-2500, in accordance with 10 CFR 50.55a(g)(5)(iii). Relief is requested from performing volumetric examinations of the welds listed in Table A to the extent required by the Code.
These examinations are limited by part geometry or interferences with other components such that the reduction in coverage is greater than 10 percent.
TABLE A
= cI~d c.~rhon ~t~l Category Item Summary Diameter Thickness Material Coverage Description Number Percentage B-D B3.110 B2.2.1A N/A 4.75" CC/S*
50 Nozzle To Head Welds B2.2.2A N/A 4.75" CC/S 50 Nozzle To Head Welds B2.2.3A N/A 4.75" CC/S 50 Nozzle To Head Welds B2.2.4A N/A 4.75" CC/S 56 Nozzle To Head Welds B3.120 B2.2.1B N/A 5.0" CC/S 42 Nozzle Inner Radius B2.2.2B N/A 5.0" CC/S 42 Nozzle Inner Radius B2.2.3B N/A 5.0" CC/S 42 Nozzle Inner Radius
U. S. Nuclear Regulatory Commission 3F0309-01 Page 3 of 7 Category Item Summary Diameter Thickness Material Coverage Description Number Percentage B2.2.4B N/A 5.0" CC/S 48 Nozzle Inner Radius B3.130 B3.2.1 N/A 8.4" CC/S 46 Steam Generator Nozzle To Head Weld.
B3.2.2 N/A 8.4" CC/S 63 Steam Generator Nozzle To Head Weld.
B3.2.3 N/A 8.4" CC/S 50 Steam Generator Nozzle To Head Weld.
B3.2.4 N/A 8.4" CC/S 46 Steam Generator Nozzle To Head Weld.
B3.2.5 N/A 8.4" CC/S 63 Steam Generator Nozzle to Head Weld B3.2.6 N/A 8.4" CC/S 49 Steam Generator Nozzle to Head Weld B3.140 B3.2.1.1 N/A 8.4" CC/S 61 Nozzle Inner Radius B3.2.2.1 N/A 8.4" CC/S 48 Nozzle Inner Radius B3.2.3.1 N/A 8.4" CC/S 43 Nozzle Inner Radius B3.2.4.1 N/A 8.4" CC/S 61 Nozzle Inner Radius B3.2.5.1 N/A 8.4" CC/S 48 Nozzle Inner Radius B3.2.6.1 N/A 8.4" CC/S 43 Nozzle Inner Radius 4
1-4 1
4
+
B-J B9.21 B4.5.62 2.5"
.375" 50 Valve to Pipe B4.5.71.3 2.5"
.375" S/S**
50 Valve To Pipe B4.5.71.4 2.5"
.375" SS 50 Pipe to Safe End B4.5.79.4 2.5"
.375" SIS 50 Valve to Pipe B4.5.79.5 2.5"
.375" SIS 50 Pipe To Safe End B4.5.84.2 2.5"
.375" SIS 50 Valve to Pipe B4.5.84.4 2.5"
.375" S/S 50 Pipe to Safe End IB4.5.151 2.5"
.375" S/S 50 Pipe to Tee
U. S. Nuclear Regulatory Commission 3F0309-01 Page 4 of 7 Category Item Summary Diameter Thickness Material Coverage Description Number Percentage B4.5.165 2.5"
.375" S/S 50 Valve To Pipe,
B-M-1 B12.40 B6.6.7 14"
.750" S/S 0
Valve Body To Canopy R-A R1.20 B4.5.108.17 4.0"
.438" S/S 50 Elbow To (RI-ISI)
Valve Examination Details B3.1 10 Pressurizer Nozzle-to-Head Welds: B2.2.1A, B2.2.2A, B2.2.3A and B2.2.4A The pressurizer nozzle-to-vessel head welds are accessible only from the head side, based on the nozzle curvature. The scanning surface of the nozzle is perpendicular to the head surface, which prohibits the ultrasonic wave entering the Code required examination volume at an angle that will integrate the weld volume for in-service flaws.
The non-destructive examination (NDE) techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section Xl Code by the Performance Demonstration Initiative (PDI) for examination of the subject vessel welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
B3.120 Pressurizer Nozzle Inside Radius: B2.2.1B, B2.2.2B, B2.2.3B and B2.2.4B The pressurizer nozzle inside radii are accessible only from the head side, based on the nozzle curvature.
The scanning surface of the nozzle is perpendicular to the head surface, which prohibits the ultrasonic wave entering the Code required examination volume at an angle that will integrate the area volume for in-service flaws. The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section XI Code by the PDI for examination of the subject vessel welds.
(See Attachment A for the cross-sectional view of the weld and limitations.)
B3.130 Steam Generator Nozzle-to-Head Welds: B3.2.1, B3.2.2, B3.2.3, B3.2.4, B3.2.5 and B3.2.6 The steam generator nozzle-to-vessel head welds are accessible only from the head side, based on the designed nozzle configuration. The proximity of the nozzle radius prevented examination coverage from the nozzle side. Scanning was performed from the nozzle. However, the ultrasonic waves did not cover the Code required examination volume at an angle that will integrate the weld volume for in-service flaws. The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section XI Code by the PDI for examination of the subject welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
B3.140 Steam Generator Nozzle Inside Radius: B3.2.1.1, B3.2.2.1, B3.2.3.1, B3.2.4.1, 83.2.5.1 and B3.2.6.1 The steam generator nozzle inside radii are accessible only from the head side, based on the designed nozzle configuration.
The proximity of the nozzle outer radius prevented examination coverage from the nozzle side. Scanning was performed from the nozzle. However, the ultrasonic waves did not cover the Code required examination
U. S. Nuclear Regulatory Commission 3F0309-01 Page 5 of 7 volume at an angle that will integrate the area volume for in-service flaws. The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section Xl Code by the PDI for examination of the subject welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
B9.21 Circumferential Pipe Welds: B4.5.62, B4.5.71.3, B4.5.71.4, B4.5.79.4, B4.5.79.5, B4.5.84.2, B4.5.84.4, B4.5.151 and B4.5.165 The ultrasonic examination of the above pipe welds was limited in coverage due to component configuration and/or immovable physical barriers.
It is not possible to perform the ultrasonic examination from both sides of the weld since one side of the weld was not suitable for scanning based on the scanning surface angle of the component. Therefore, the welds only received a single sided examination or partial single sided examination resulting in less than 90 percent coverage of the required examination volume. The percentage of coverage reported represents the aggregate coverage from all examination angles and scans performed on the weld and adjacent base material.
The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section Xl Code by the PDI for examination of the pipe welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
B12.40 Valve body Weld: B6.6.7 Ultrasonic examination of the above valve to body weld could not be performed due to being inaccessible. The valve would require disassembly for access to the weld. Relief is being sought on the basis that, due to the design of the valve, disassembly of DHV-3 is required for access to the weld, including the removal of a weld joining the clamp to the yoke holding the upper assembly.
DHV-3 had a history of pressure seal ring leakage. Due to the significant consequences of the leakage (DHV-3 is the first isolation valve between the Reactor Coolant System and the Decay Heat System and contains the only weld of this type at CR-3), a modification was implemented during the Third Ten-Year ISI Interval to eliminate the pressure seal ring joint. A canopy was installed over the pressure seal ring joint with Summary Number B6.6.7 being the identifier of the resultant valve body weld. Preservice examinations consisting of ultrasonic and liquid penetrant were performed satisfactorily with no indications.
(See Attachment A for representative drawings of DHV-3.)
R1.20 Circumferential Pipe Weld: B4.5.108.17 (RI-ISI)
Ultrasonic examination of the above pipe weld was limited in coverage due to component configuration and/or immovable physical barriers.
It is not possible to perform the ultrasonic examination from both sides of the weld since one side of the weld was not suitable for scanning, based on the scanning surface angle of the component.
Therefore, the weld only received a single sided examination or partial single sided examination resulting in less than 90 percent coverage of the required examination volume. The percentage of coverage reported represents the aggregate coverage from all examination angles and scans performed on the weld and adjacent base material.
The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section XI Code by the PDI for examination of the pipe welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
U. S. Nuclear Regulatory Commission 3F0309-01 Page 6 of 7
- 5.
Burden Caused by Compliance In order to scan all of the required volume for these welds and inside radii, the components would have to be redesigned to allow scanning from both sides of the weld and inside radii, which is impractical. There were no recordable indications, other than geometric indications, found during the inspection of these welds and inside radii.
Based on the components' designed configuration, the coverage obtained did not meet the requirements of the ASME Code, Code Case N-578 or Code Case N-460.
In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested for the components listed in Table A on the basis that the required examination coverage of essentially 100 percent is impractical due to physical obstructions and the limitations imposed by design, geometry, and materials of construction. CR-3 utilized examination techniques qualified to meet the requirements of ASME Section XI, Appendix VIII, as required in 10 CFR 50.55a(g)(6)(a)(c), that achieved the maximum practical amount of coverage obtainable within the limitations imposed by the design of the components and examination techniques. Additionally, VT-2 examinations are performed on the subject components of the Reactor Coolant Pressure Boundary during system pressure tests on a refueling outage frequency. Those examinations were completed each refueling outage and no evidence of leakage was identified for these components.
The mandated requirement in 10 CFR 50.55a(b)(2)(xv)(A)(2) states, 'Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaw on the opposite side of the weld."
The Appendix VIII techniques applied at CR-3 and within the U. S. nuclear industry, (PDI-UT-2), are not qualified for "Detection or length sizing of circumferentially oriented flaw indications when only single side access is available and the flaw is located on the far side of the weld."
Based on the design configuration of the components and available examinations techniques, CR-3 was not able to achieve greater than 90 percent Code coverage of the required examination volume for the components listed above without major modifications to the components.
- 6.
Proposed Alternative and Basis for Use No alternative examinations were planned for these welds during the Third Ten-Year ISI Interval. The use of radiography as an alternate volumetric examination for the above listed components is not practical due to component thickness and geometric configurations.
Other restrictions making radiography impractical are the physical barriers prohibiting access for placement of source, film, image quality indicator, etc.
Additionally, inside radius exams of Class 1 nozzles on pressurizers and steam generators are no longer required by the Code.
Based on the above, with due consideration of the earlier plant design, the underlying objectives of the Code required volumetric examinations have been met.
The examinations were completed to the extent practical and evidenced no unacceptable flaws present. VT-2 examinations performed on the subject Class 1 components during system pressure testing each refueling outage provide continued assurance that the structural integrity of the subject components is maintained.
U. S. Nuclear Regulatory Commission 3F0309-01 Page 7 of 7 Ultrasonic examination of these welds was conducted using personnel qualified in accordance with ASME Section Xl, Appendix VII of the 1998 Edition, no Addenda.
Ultrasonic procedures complied with the requirements of ASME Section V, Article 4 of the 1989 Edition, as amended by Section XI, Appendix I. IWB-2500, Table IWB-2500-1, Examination Category B-P System Leakage Tests and VT-2 visual examinations performed each refueling outage provide adequate assurance of pressure boundary integrity. In addition to the above Code required examinations (volumetric and pressure test), there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through these welds, it would be detected and proper action taken. Specifically, system leak rate limitations are imposed by Improved Technical Specification 3.4.12, "RCS Operational LEAKAGE," and reactor building normal sump rate monitoring provides additional assurance that any leakage would be detected prior to gross failure of the component. The component welds were inspected by volumetric and surface NDE methods during construction and verified to be free from unacceptable fabrication defects.
Therefore, reasonable assurance of quality and safety is based on the achieved coverage and results of the volumetric and/or surface and the pressure testing VT-2 examinations performed.
- 7.
Duration of Proposed Alternative Relief is requested for the Third Ten-Year ISI Interval for CR-3, which was effective from August 14, 1998, ending August 13, 2008.
- 8.
Precedents (Optional)
- 9.
References (Optional)
ENCLOSURE 1 ATTACHMENT A COVERAGE DATA INSERVICE INSPECTION RELIEF REQUEST #09-001-11 THIRD TEN-YEAR ISI INTERVAL
EXAMINATION COVERAGE FOR RELIEF NOZZLE: B2.2.1 AGGREGATE COVERAGE OBTAINED:
-50%
AGGREGATE COVERAGE OBTAINED FOR INSIDE RADIUS: 42%
Zone Coverage Obtained Weld 45%
Adjacent Base Me 55%
Inside Radius: 42%
UPPER SECTION EVALUATION Weld Diaeer 9.3 in.
NoZZle BoreDia L
2.5in.
Area Measurement Volume Calculation Weld 10.48 sq. in.
. 156.9 cu. in.
Adjacent Base Mete 27.77 sq. in.
Adjacent Base Meta 415.7 cu. in.
Inside Radius 2.9 sq. in.
Inside Radius 11.2 cu. in.
Exam.
Area Degrees Volume Volume Angle Beem Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.l (in.)
(cu. in)
- c. in.)
Examined 1
0 n/a 0.0 180.0 0.0 156.9 0%
2 45 1
4.3 180.0 63.8 156.9 41%
3 45 2
0.0 180.0 0.0 156.9 0%
4 45 3
0.5 160.0 7.6 156.9 5%
5 45 4
0.5 180.0 7.6 156.9 5%
6 60 1
7.2 180.0 107.8 156.9 69%
7 60 2
0.0 180.0 0.0 156.9 0%
8 60 3
4.4 180.0 65.3 156.9 42%
9 60 4
4.4 180.0 65.3 156.9 42%
Totals:
317.4 1411.9 22%
Adjacent Base Metal Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(de*.)
Direction (sq. in.)
(in.)
cu., in in.)
Examined 1
0 n/s 7.7 180.0 114.8
- 415.7 28%
2 45 1&2 14.6 180.0 218.0 415.7 52%
3 45 3
7.7 160.0 114.8 415.7 28%
4 45 4
7.7 180.0 114.8 415.7 28%
5 60 1&2 17.6 180.0 263.0 415.7 63%
6 60 3
16.9 180,0 252.7 415.7 61%
7 60 4
16.9 180.0 252.7 415.7 61%
Totals:
1330.8 2910.0 48%
nsde Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axial 0.2 180.0 0.9 11.2 8%
2 45 circ 0.1 180.0 0.4 11.2 3%
3 60 axial 1.5 180.0 5.9 11.2 52%
4 60 ciro 1.4 180.0 5.5 11.2 49%
Totals:
12.7 44.9 28%
LOWER SECTION EVALUATION' Weld Diameter:
9.53 in.
Nozzle Bore Diameter 2.5 In.
Area Measurement Volume Calculation Weld 7.93 sq. in.
Weld 118.7 cu. in.
Adjacent Base Meta 21.71 sq. in.
Adjacent Bass Metal 325.0 cu. in.
Inside Radius 2.5 sq. in.
Inside Radius 9.7 cu. in.
Weld Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
4in (cu. in, (cu. in Examined 1
0 rda 5.5 10.0 817 118.7 69%
2 45 1
7.1 180.0 1057 118.7 89%
3 45 2
0.0 180.0 0.0 1187 0%
4 45 3
6.7 180.0 100.1 118.7 84%
5 45 4
6.7 180.0 100.1 118.7 84%
6 60 1
7.3 160.0 109.3 118.7 92%
7 60 2
0.0 180.0 0.0 118.7 0%
8 60 3
7.2 160.0 107.6 118.7 91%
9 60 4
7.2 180.0 107.6 118.7 91%
Totals:
712.3 1068.4 67%
Adjacent Base Metal Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Ent21 # Ideg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 n/a 11.3 180.0 169.2 325.0 52%
2 45 1&2 16.0 180.0 239.8 325.0 74%
3 45 3
11.3 180.0 169.2 325.0 52%
4 45 4
11.3 180.0 169.2 325.0 52%
5 60 1&2 17.1 180.0 256.6 325.0 79%
6 60 3
15.0 180.0 224.1 325.0 69%
7 60 4
15.0 180.0 224.1 325.0 69%
Totals:
1452.1 2274.9 64%
Inside Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry (Ldeg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu, in.,
Examined 1
45 axial
.1.6 180.0 6.4 9,7 66%
2 45 circ 0.6 180.0 2.2 9,7 23%
3 60 axial 2.1 180.0 6.1 9.7 84%
4 60 circ 1.2 180.0 4.7 9.7 49%
Totals:
21.4 38.6 65%
PRESSURIZER RELIEF NOZZLE TO UPPER HEAD (WELD WP-33)
B2.2.1 UPPER LOWER
EXAMINATION COVERAGE FOR RELIEF NOZZLE: B2.2.2 AGGREGATE COVERAGE OBTAINED:
50%
AGGREGATE COVERAGE OBTAINED FOR INSIDE RADIUS 42%
Zone Coverage Obtained Weld 45%
Adjacent Base Metal: 55%
Inside Radius: 42%
UPPER SECTION E-VALUATION d iameter:
,953 in.
Nozzle Bore iameter:
2.o in.
Area Measurement Volume Calculation Weld 10.48 sq. in.
Weld 156.9 cu. in, Adjacent Base Metal 27.77 sq. In.
Adjacent Base Metal 415.7 cu. in.
Inside Radius 2.9 sq. in.
Inside Radius 11.2 cu. In.
Weld Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry# 6 deg.)
Direction (sq. in.)
(in.)
(cu. in.)
,cu.
in,)
Examined 0
Na 0.0 180.0
- 0.
156,9 0%
2 35/45 1
4.3 180.0 63.8 156.9 41%
3 35/45 2
0.0 180.0 0.0 156,9 0%
4 35/45 3
0.5 180.0 7.6 156.9 5%
5 35/45 4
0.5 180.0 7.6 156.9 5%
6 60 1
7.2 180.0 107,8 156.9 69%
7 60 2
0.0 180,0 0.0 156,9 0%
8 60 3
4.4 180.0 65.3 15689 42%
9 60 4
4.4 180.0 65,3 156.9 42%
Totals:
317.4 1411,9 22%
Adjacent Base Metal
- Exam, Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry (deg.)
Direction (sq. in.)
lin.)
Icu.
In.)
(cu. In.)
Examined 1
0 n/a 7.7 1T0.0 114.8 415.7 28%
2 35/45 1&2 14.8 180.0 218,0 415.7 52%
3 35/45 3
7.7 180.0 114.8 415.7 28%
4 35/45 4
7.7 180.0 114.8 415.7 28%
5 60 1&2 17.6 180.0 263.0 415,7 63%
6 60 3
16.9 180.0 252.7 415.7 61%
7 60 4
1.9 180.0 252.7 415.7 61%
Totals:
1330.8 2910.0 48%
nelde Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
Ideg.)
Directon (sq. in.)
(in.)
(cu. In,)
(cu. In.)
Examined 1
45 axial 0.2 180.0 0.9 11.2 8%
2 45 clrc 0.1 180.0 0.4 11.2 3%
3 60 axial 1.5 180.0 5.9 11.2 52%
4 60 circ 1.4 180.0 5.5 11.2 49%
Totals:
12.7 44.9 28%
LOWER SECTION EVALUATION a 7 iameter in.
o aore Damater.
T. in.
Area Measurement Volume Calculation Weld 7.93 sq. in.
Weld 118.7 cu. in.
Adjacent Base Metal 21.71 sq. in.
Adjacent Base Metal 325.0 cu. in.
Inside Radius 2.5 sq. in.
Inside Radius 9.7 cu. in.
Weld Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry (deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 nWa 5.5 180.0 81.7 118.7 69%
2 35/45 1
7.1 180.0 105.7 118.7 89%
3 35/45 2
0.0 180.0.
0.0 118.7 0%
4 35/45 3
6.7 180.0 100.1 118.7 84%
5 35/45 4
6.7 180.0 100.1 118.7 84%
8 80 1
7,3 180.0 109.3 118.7 92%
7 60 2
0.0 180.0 0,0 118.7 0%
8 60 3
7.2 180.0 107.6 118.7 91%
9 60 4
7.2 180.0 107.6 118.7 91%
Totals:
712.3 1068.4 67%
Adjacent Base Metal Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry B (ded.)
Direction (sq. in.)
(in.)
(cu. in.% (cu. in.)
Examined 1
4 n/a 11.3 180.0
- 6.
32.0 52%
2 35/45 r&2 10.0 180.0 239.8 325.0 74%
3 35/45 3
11.3 180.0 169.2 325.0 52%
4 35/45 1 4 1`1.3 180.0 169.2 325.0 52%
5 60 1&,2 17:1 180.0 256.6 325.0 790/
6 60 3
15.0 180.0 224.1 325.0 69%
7 60 4
15.2 180.0 224.1 325.0 69%
Totals:
14SLI 2274.9 54%
Inside Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Eri da.)DrcinIsl n)In.
4U in.
Iu, InJ., Examined 1 45 Cafiln (s. i6 180.0 6(4u9,7 66%
2 45 circ 0.6 180.0 2.2 9.7 23%
3 60 axial 2.1 180.0 8.1 9.7 84%
4 60 circ 1.2 180.0 4.7 9.7 49%
Totals:
21.4 3&.6
$5%
PRESSURIZER RELIEF NOZZLE TO UPPER HEAD (WELD WP-335)
UPPER LOWER
EXAMINATION COVERAGE FOR RELIEF NOZZLE: B2.2.3 AGGREGATE COVERAGE OBTAINED:
50%
AGGREGATE COVERAGE OBTAINED FOR INSIDE RADIUS 42%
Zone Coverage Obtained Weld 45%
Adjacent Base Me 55%
Inside Radius: 42%
UPPER SECTION EVALUATION Wd biameter; 9.53 in.
Nozzle ore Diameter:
2.5 In.
Area Measurement volume Calculation Weld 10.48 sq. in.
Weld 156.9 cu. in.
Adjacent Base Meta 27.77 sq. in.
Adjacent Base Mete 415.7 cu. in.
Inside Radius 2.9 sq. in, Inside Radius 11.2 cu. in, Weld Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. In.)
(cu. in.)
Examined 1
0 nla 0.0 180.0 0.0 156.9 0%
2 35/45 1
4.3 190.0 63.8 156.9 41%
3 35145 2
0.0 180.0 0.0 156.9 0%
4 35/45 3
0.5 180.0 7.6 156.9 5%
5 35/45 4
0.5 180.0 7.6 156.9 5%
6 60 1
7.2 180.0 107.8 156.9 69%
7 60 2
0.0 180.0 0.0 156.9 0%
8 60 3
4.4 180.0 65.3 156.9 42%
9 60 4
4.4 160.0 65.3 156.9 42%
Totals:
317.4 1411.9 22%
Adjacent Base Metal Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Enty #
(deg.)
Direction (sq. in.
in.)
cu, in.)
Examined 1
0 n/a 7.7 180.0 114.6 415.7 28%
2 35/45 1&2 14.6 180.0 216.0 415.7 52%
3 35/45 3
7.7 180.0 114.5 415.7 28%
4 35/45 4
7.7 180.0 114.8 415.7 28%
5 60 182 17.6 160.0 263.0 415.7 63%
6 60 3
16.9 160.0 252.7 415.7 61%
7 60 4
16,9 180.0 252.7 415.7 61%
Totals:
1330.8 2910.0 46%
Insade Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(leg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axia" 0.2 180.0 0.9 11.2 b%
2 45 circ 0.1 180.0 0.4 11.2 3%
3 60 axial 1.5 180.0 5.9 11.2 52%
4 60 circ 1.4 180.0 5.5 11.2 49%
Totals:
12.7 44.9 28%
LOWER SECTION EVALUATION Weld biametern Aqa ým
.ozzle BoreDiameter:
2.5 in.
Area Measurement Volume Calculation aeld 7.93 sq. in.
Weld 118.7 cu. in.
Ajacent Base Mets 21.71 sq. in.
Adjacent Base Metal 325.0 cu. in.
Inside Radius 2.5 sq. in.
Inside Radius 9.7 cu. in.
Weid Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent.
Entry
( ideg.)
Direction (sq. in.)
(in.t (cu. in.)
(cu. in.)
Examined 1
0 n/a 5.5 180.0 61.7 116.7 69%
2 35/45 1
7.1 160.0 105.7 118.7 89%
3 35/45 2
0.0 180.0 0.0 118.7 0%
4 35/45 3
6.7 180.0 100.1 118.7 84%
5 35145 4
6.7 180.0 100.1 116.7 64%
6 60 1
7.3 180.0 109.3 118.7 92%
7 60 2
0.0 180.0 0.0 118.7 0%
B 60 3
7.2 180.0 107.6 118.7 91%
9 60 4
7.2 180.0 107.6 118.7 91%
Totals:
712.3 1068.4 87%
Adjacent Base Metal
- Exam, Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry /#
(de.)
Direction (sq. in.)
(in.)
(cu. in.)
(Cu. in.)
Examined 1
0 n/a 11.3 180,0 169.2 325.0 52%
2 35/45 1&2 16,0 180,0 239,8 325.0 74%
3 35145 3
11.3 180.0 169.2 325.0 52%
4 35/45 4
11.3 160.0 169.2 325.0 52%
5 60 1&2 17.1 180.0 256.6 325.0 79%
6 60 3
15.0 180.0 224.1 325.0 69%
7 60 4
15.0 180.0 224.1 325.0 69%
Totals:
1452.1 2274.9 64%
Inside Radius Exam.
Area Degrees Volume Volume Angle Beam Examined Examined Examined Required Percent Entry B de0.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axial 1.6 1;0.0 6.4 9.7 66%
2 45 circ 0.6 160.0 2.2 9.7 23%
3 60 axial 2.1 180.0 8.1 9.7 84%
4 60 circ 1.2 180.0 4.7 9.7 49%
Totals:
21.4 38.8 85%
PRESSURIZER RELIEF NOZZLE TO UPPER HEAD (WELD WP-33)
B2.2.3 UPPER LOWER
EXAMINATION COVERAGE FOR WELD:
B2.2.4 PRESSURIZER SPRAY NOZZLE TO HEAD & INNER RADIUS AGGREGATE COVERAGE OBTAINED:
56%
Zone Coverage Obtained Weld: 52%
Adjacent Base Metal 58%
Inner Radius:
48%
Weld Length:
27.49 in.
BORE 4
Area Measurement Volume Calculation Weld 6.61 sq. in.
Weld 181.7089 cu. in.
Adjacent Base Metal 24.36 sq. in.
Adjacent Base Metal 669.6564 cu. in:
Inner Radius 2.38 sq. in.
Inner Radius 9.52 cu. in.
!X Weld Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.). Examined 1
0 n/a 3.6 27.49 99.8 181.7 55%
,2 45 1
6.1 27.49 168.5 181.7 93%
3 45 2
0.0 27.49 0.0 181.7 0%
4 45 3
3.6 27.49 99.8 181.7 55%
5 45 4
3.6 27.49 99.8 181.7 55%
6 60 1
6.4 27.49 174.8 181.7 96%
7 60 2
0.0 27.49 0.0 181.7 0%
8 60 3
3.6 27.49 99.8 181.7 55%
9 60 4
3.6 27.49 99.8 181.7 55%
Totals:
842.3 1635.4 52%
Adjacent Base Metal Exam.
Area Length Volume Volume Angle Beam Examined. Examined Examined Required Percent Entry #
(deg.).
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 nla 12.4 27.49 339.8 669.7 51%
2 45 1&2 1,8.3 27.49 503.1 669.7 75%
3 45 3
12.4 27.49 339.8 669.7 51%
4 45 4
12.4 27.49 339.8 669.7 51%
5 60 1&2 19.7 27.49 541.8 669.7 81%
6 60 3
12.4 27.49 339.8 669.7 51%
7 60 4
12.4 37.7 466.0 918.4 51%
Totals:
2870.0 4936.3 58%
inner Radius Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent.
Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axial 1.0 12.6 12.6 29.9 42%
2 45 circ 0.6 12.6 7.4 29.9 25%
3 60 axial 1.6 12.6 20.6 29.9 69%
4 60 circ 1.3 12.6 16.7 29.9 56%
Totals:
57.3 119.6 48%
PRESSURIZER SPRAY NOZZLE TO UPPER HEAD WELD (WP34)
P2.N2.T4
/9/,,S-TANGENT POINTS
PRESSURIZER SPRAY NOZZLE (WP34) 62.2.4
Nuclear Genevalion Grouw Summary No B3 2 1 Examiner Brannin, Michael Supplemental Report Report No UT-03-137 Page 2
of
- 3 Level II Examiner Dittrich, Victor W Level II Reviewer WA Site Review Hecht, Jeff W / LV III
.44-Other N/A Date Level N/A ANII Review C. Colarte 44r-Date /t-I/5-03 Date /2-- o3 Comments Examination Coverage for Weld: B32.1 Sketch or Photo L\\SharedIlSldata\\lDDEAL Documentation\\*JO13\\UT_03137a JPG EXAMINATION COVERAGE FOR WELD B3.2 1 STEAM GENERATOR 'A* INLET NOZZLE "WG25" & INNER RADIUS AGGREGATE COVERAGE OBTAINED 46%
Zone Coverage Obtained Weld 29%
Adjacent Base Metal 51%
Inner Radius 61%
Exaeinaffm Voualm Deffnition Weld Length 179 54 in (57 54"PI)
BORE 4513 Area Measurement Volume Calculation Weld 1882 sq in Weld 3343035 cu to Adjacent Base Metal 8418 sq in Adjacent Base Metal 1511368 cu in Inner Radius 456 sq In Inner Radius 205 7928 Cu in Exlfo,12='cov300e cakculatioun, Weld Exam Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg)
Direction (sq in)
(in)
(cu in)
(cu in )
Examined 1
0 n/a 34 1795 6104 33430 18%
2 45 1
155 1795 27829 33430 83%
3 45 2
00 179 5 00 33430 0%
4 45 3
34 1795 6104 33430 18%
5 45 4
34 1795 8104 33430 18%
6 60 1
165 1795 29624 33430 89%
7 60 2
00D 1795 00 33430 0%
8 60 3
34 1795 61854 33430 18%
9 60 4
34 1795 6104 33430 18%
Toials 879705 3008753 29%
Adjacent Base Metal Exam Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent EnxryS (deg )
Direction (sq in)
(in
)
(cu in )
(cu in )
Examined 1
0 (do 382 1795 68584 151137 45%
2 45 1&2 512 1794 91924 151137 61%
3 45 3
38 2 179 5 6858 4 15113 7 45%
4 45 4
382 1795 68584 151137 45%
5 50 1&2 588 1795 105570 151137 70%
6 60 3
382 1795 68584 151137 45%
7 50 4
382 1795 61358 4 151137 45%
Totals*
54041 5 105795 7 51%
Inner Radius Exam Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent
- Entry It (deg )
Direction (sq in)
(in )
(cu i )
(cu i )
Exarmned I
45W6 axial 2 8 141 8 397 0 646 5 61%
2 455M0 tangent 2 8 141 8 397 0 6A8 5 61%
TOWSl 794 0 1293 0 61%
cNuclear Generatwn GroWp Summary No B32.1 Examiner Branni, Michael Examiner DIttrich, Victor W.t4
)
Other NWA Supplemental Report Report No UT-03-137 Page 3
of 3
Level II Reviewer WA Level I11 Site Review Hecht, Jeff W I LV III Level N/A ANII Review G Colarte Date Date //'-1
-o Date
/l 6 i Comments Steam Generator (A) Inlet Nozzle B3.2 1 I B3.2.1.1 Sketch or Photo L \\SharecPlSIdataUDDEAL Documentateon\\RO13\\UT_03_137b JPG STEAM GENERATOR (A) INLI_
NO/LZ E 83 2
1/B3 2 1 1 This Coverage data is representative of B3.2.4 Steam Generator B Inlet Nozzle and B3.2.4.1 Nozzle Inner Radius as well.
(Nuclear Generation dGroup Supplemental Report Report No UT-03-134 Page 2
of 3
Summary No 133.2.1
-44, -".-
Examiner Tomflnson, Robert Examiner Wilkey, Carl J C 3 Other NJA Level II Reviewer Lareon, Scott I Level III Level II Site Review Hecht, Jeff W. I LV III Level NIA ANI) Review C Colarte Date 10/22/2003 Date 10/22/2003 Date 1Z o4-,
Comments Examination Coverage for Weld* B3.2.1 Sketch or Photo L\\SharedUSldata\\IDDEAL Documentation\\RO13\\UT_03_134a JPG EXAMINATION COVERAGE FOR WELD.
B3 21 STEAM GENERATOR 'A" INLET NOZZLE "WG25" & INNER RADIUS AGGREGATE COVERAGE OBTAINED 4"%
Zone Coverage Obtained Weld 29%
Adjacent Bale Metal 51%
Inner Radius 81%
Exanmnin Volumie tion Weld Length 179 54 in (57 64'PI)
BORE 4513 Area Measurement Volume Calculation Weld 1862 sq in Weld 3343 035 cu in Adjacent BaseMetal 8418 sq in Adjacent Base Metal 1511368 cu in Inner Radius 4 56 sq Iin Inner RadiuS 205 7928 Cu in EMMMt G~lil alulatons Weld Exam Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(deg)
Direction (sq in)
(in)
(Cu m)
(cu in)
Examined 1
0 1118 34 1795 6104 33430 18%
2 45 1
155 1795 27829 33430 83%
3 45
- 2 00 1795 00 33430 0%
4 45 3
34 1795 61D4 33430 18%
5 45 4
34 1795 6104 33430 18%
6 80 1
165 1795 29624 33430 89%
7 60 2
00 1795 00 33430 0%
8 60 3
34 1795.
6104 33430 18%
9 60 4
34 1795 6104 33430 18%
Totals 57975 30087 3 29%
kdJaceit Base Metal Exam Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(degI Direction (sq in) fin (cu in)
(cu in)
Examined 1
0 fie 382 1795 68584 151137 45%
2 45 1&2 51 2 1795 91924 151137 61%
3 45 3
382 1795 68584 151137 45%
4 45 4
382 1795 88584 151137 45%
5 60 1&2 58 8 1795 105570 151137 70%
6 80 3
382 1795 88584 151137 45%
7 60 4
382 1795 68584 151137 45%
Totals 540415 1057957 51%
iner Radlius Exam Area Lenglh Volume Volume Angle Beam Examined Examined Examined Required Percent Entry#
(deg)
Direcbon (sq in)
(in)
(Cu in)
(cu in)
Examined 1
45&60 ai 28 1418 3970 4645 61%
2 45&60 tangent 28 1418 3970 6465 61%
Totals 7940 12930 61%
Nuclear Geneiatioi
(
~Group~
Summary No B32 1 Examiner Tomlinson, Robert Examiner Wilkey, Carl J.
Other WA Supplemental Report Report No S"'Page Level II Reviewer Larson, Scott I Level III C u
- Level II Site Review Hecht, Jeff W. I LV III Level N/A ANII Review C. Colarte UT-03-134 3
of 3
Date 1 042212=13 Date 10/22/2003 Date /U?-o;-*J Comments Steam Generator (A) Inlet Nozzle B3 2.1 1 B3.2.1.1 Sketch or Photo L \\Shared\\lSIdata\\IDDEAL Documentabon\\RO13UT_03_134b JPG STEAM GENERATOR (A)
[NLET NOZZLE 133 2 lI/B3 2 1 1 This Coverage data is representative of B3.2.4 Steam Generator B Inlet Nozzle and B3.2.4.1 Nozzle Inner Radius as well.
1-
EXAMINATION COVERAGE FOR WELD:
B3.2.2/B3.2.2.1 STEAM GENERATOR "A" LOWER HEAD TO NOZZLE 'WG50" & INNER RADIUS AGGREGATE COVERAGE OBTAINED:
63%
Zone Coverage Obtained Weld: 65%
Adjacent Base Metal 63%
Inner Radius:
48%
Weld Length:
118.88 in.
(37.84PI)
B5RE 9Q.26 Area Measurement Volume Calculation Weld 20.92 sq. in.
Weld 2486.97 cu. in.
Adjacent Base Metal 108.64 sq. in.
Adjacent Base Metal 12915.12 cu. in.
Inner Radius 4.95 sq. in.
Inner Radius 446.787 cu. in.
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent
-Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 n/a 18.4 118.88 2192.1 2487.0 88%
2 45 1
17.3
. 76.88 1330.0 1608.3 83%
3 45 1
10.6 42 445.2 878.6 51%
4 45 2
0.0 118.88 0.0 2487.0 0%
5 45 3
18.4 118.8 2190.7 2485.3 88%
6 45 4
18.4 118.8 2185.9 2485.3 88%
7 60 1
17.3 60.88 1055.7 1273.6 83%
8 60 1
13.0 58 752.3 1213.4 62%
9 60 2
0.0 118.88 0.0 2487.0 0%
10 60 3
18.4 118.88 2187.4 2487.0 88%
11 60 4
18.4 118.88 2187.4 2487.0 88%
Totals:
14526.7 22379.4 65%
r.djacent Base Metal Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 n/a 77.4 100.88 7804.1 10959.6 71%
2 0
n/a 59.2
. 18 1065.6 1955.5 54%
3 45 1&2 76.4 76.88 5873.6 8352.2 70%
4 45 1&2 54.5
' 58 3158.1 6301.1 50%
5 45 3
68.6 100.88 6916.3 10959.6 63%
6 45 3
59.2 18 1065.6 1955.5 54%
7 45 4
68.6 100.88 6916.3 10959.6 63%
8 45 4
59.2 18 1065.6 1955.5 54%
9 60 1&2 84.6 60.88 5150.4 6614.0 78%
10 60 1&2 51.5 58 2984.1 6301.1 47%
11 60 3
68.6 100.88 6916.3 10959.6 63%
12 60 3
59.2 18 1065.6 1955.5 54%
13 60 4
68.6 100.88 6916.3 10959.6 63%
14 60 4
59.2 18 1065.6 1955.5 54%
Totals: 57963.7 92144.1 63%
Inner Radius Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axial 3.4 58.4 198.5 288.9 69%
2 45 axial 0.0 31.9 0.0 157.9 0%
3 60 axial 3.3 46.3 153.1 229.0 67%
4 60 axial 0.0 44.0 0.0 217.8 0%
5 45 tangent 2.8 90.3 252.7 446.8 57%
6 60 tangent 2.8 90.3 252.7 446.8 57%
Totals:
857.0 1787.1 48%
STEAM GENERATOR PRIMARY. OUTLET NOZZLE (WGSO)
B5.2.2 /
5,3.2.2, This coverage data is representative for t e following Summary Numbers; B3.2.3, B3.2.5, B3.2.3.1, and B3.2.5.1
EXAMINATION COVERAGE FOR WELD:
63.2.31B3.2.3.1 STEAM GENERATOR "A" OUTLET NOZZLE WG50" & INNER RADIUS AGGREGATE COVERAGE OBTAINED:
50%
Zone Coverage Obtained Weld: 51%
Adjacent Base Metal: 49%
Inner Radius:
43%
WedLnth:
- 11.
in.
)E 90 Area Measurement Volume Calculation e
Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent ntry (deg.)
Direction (sq. in.ý (in.)
(cu. in.)
(cu. i)
Examined 1
0 nla 18.4 93.88 1731.1 1964.0 88%
2 0
n/a 0.0 25 0.0 523.0 0%
3 35 1
17.3 73.88 1281.1 1545.6 83%
4 35 1
13.0 20 259.4 418.4 62%
5 35 1
0.0 25 0.0 523.0 0%
6 35 2
0.0 118.88 0.0
.2487.0 0%
7 45 3
18.4 88.88 1838.9 1859.4 88%
8 45 3
Ae0.0 30 0.0 627.6 0%
9 45 4
18.4 88.88 1638.9 1859.4 88%
10 45 4
0.0 30 0.0 627.6 0%
11 45860 1
17.3 73.88 1281.1 1545.6 83%
12 45860 1
13.0 20 259.4 418.4 62%
13 45860 1
0.0 25 0.0 523.0 0%
14 45860 2
0.0 118.88 0.0 2487.0 0%
15 60 3
18.4 88.88 1638.9 1859.4 88%
16 60 3
0.0 30 0.0 627.6 0%
17 60 4
18.4 88.88 1638.9 1859.4 88%
18 60 4
0.0 30 0.0 627.6 0%
Totals.
11367.9 22382.7 51%
Adjacent Base Metal Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
0 n/a 77.4 a8888 6875.8 9655.9 71%
2 0
n1a 0.0 30 0.0 3259.2 0%
3 35 18.2 76.4 73.88 5643.0 8026.3 70%
4 35 18.2 38.2 20 763.8 2172.8 35%
5 35 18.2 0.0 25 0.0 2716.0 0%
6 45 3
68.6 88.88 6093.6 9655.9 63%
7 45 3
0.0 30 0.0 3259.2 0%
8 45 4
68.6 88.88 6093.6 9655.9 63%
9 45 4
0.0 30 0.0 3259.2 0%
10 458.60 1&.2 84.6 73.88 6252.5 8026.3 78%
11 45860 182 39.7 2
793.6 2172.8 37%
12 458.60 18.2 0.0 25 0.0 2716.0 0%
13 60 3
68.6 88.68 6093.6 9655.9 63%
14 60 3
0.0 30 0.0 3259.2 0%
15 60 4
68.6 88.88 6093.6 9655.9 63%
16 60 4
0.0 30 0.0 3259.2 0%
Totals:
44703.0 90405.9 49%
Inner Radius Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.)
Examined 1
45 axial 3.4 56.0 188.6 277.0 68%
2 45 axial 0.0 34.3 0.0 169.8 0%
3 60 axial 3.3 56.0 185.2 277.0 67%
4 60 axial 0.0 34.3 0.0 169.8 0%
5 45 tangent 2.8 71.3 199.7 353.0 57%
6 45 tangent 0.0 19.0 0.0 94.1 0%
7 60 tangent 2.8 71.3 199.7 353.0 57%
8 60 tangent 0.0 19.0 0.0 94.1 0%
Totals:
773.1 1787.6 43%
EXAMINATION COVERAGE FOR WELD:
B3.2.6/B3.2.6.1 STEAM GENERATOR "B" OUTLET NOZZLE 'WG50" & INNER RADIUS AGGREGATE COVERAGE OBTAINED:
49%
Zone Coverage Obtained Weld: 49%
Adjacent Base Metal: 49%
Inner Radius:
43%
II~.
'ti#
IIIIi Weld Length:
118.88 in.
(37.84"PI)
BORE 90.26 Area Measurement Volume Calculation Weld 20.92 sq. in.
Weld 2486.97 cu. in.
Adjacent Base Metal 108.64 sq. in.
Adjacent Base Metal 12915.12 cu. in.
Inner Radius 4.95 sq. in.
Inner Radius 446.787 cu..in.
Weld Entry #
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 Exam.
Angle (deg.)
0 0
35 35 35 35 45 45 45 45 45&60 45&60 45&60 45&60 60 60 60 60 Direction (sq. in.)
nra 18.4 n/a 0.0
- 1.
17.3 1
13.0 1
0.0 2
0.0 3
18.4 3
0.0 4
18.4 4
0.0 1
17.3 1
13.0 1,
0.0 2
0.0 3
18.4 3
0.0 4
18.4
.4 0.0 (in.)
(cu. in.)
(cu. in.) Examined 93.88 1731.1 1964.0 88%
25 0.0 523.0 0%
73.88 1281.1 1545.6 83%
20 259.4 418.4 62%
25 0.0 523.0 0%
118.88 0.0 2487.0 0%
83.88 1546.7' 1754.8 88%
35 0.0 732.2 0%
83.88 1546.7 1754.8 88%
35 0.0 732.2 0%
73.88 1281.1 1545.6 83%
20 259.4 418.4 62%
25 0.0 523.0 0%
118.88 0.0 2487.0 0%
83.88 1546.7 1754.8 88%
35 0.0 732.2 0%
83.88 1546.7 1754.8 88%
35 0.0 732.2 0%
Totals:
10999.1 22382.7 49%
Area Length Volume Volume Beam Examined Examined Examined Required Percent A.djacent Base Metal Exam.
Angle Area Length Volume Volume Beam Examined Examined Examined Required Percent hntry #
~1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 (deg.)
0 0
35 35 35 45 45 45 45 45&60 45&60 45&60 60 60 60 60 Direction (sq. in.)
n/a 77.4 n/a 0.0
.1&2 76.4 1&2 38.2 1&2 0.0 3
68.6 3
0.0 4
68.6 4
0.0 1&2 84.6 1&2 39.7 1&2 0.0 3
68.6 3
0.0 4
68.6 4
0.0 (in.)
(cu. in.)
(cu. in.) Examined 88.88 6875,8 9655.9 71%
30 0.0 3259.2 0%
73.88 5643.0 8026.3 70%
20 763.8 2172.8 35%
25 0.0 2716.0 0%
88.88 6093.6 9655.9 63%
30 0.0 3259.2 0%
88.88 6093.6 9655.9 63%
30 0.0 3259.2 0%
73.88 6252.5 8026.3 78%
20 793.6 2172.8 37%
25 0.0 2716.0 0%
68.88 6093.6 9655.9 63%
30 0.0 3259.2 0%
88.88 6093.6 9655.9 63%
30 0.0 3259.2 0%
Totals:
44703.0 90405.9 49%
Inner Radius Exam.
Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry #
(deg.)
Direction (sq. in.)
(in.)
(cu. in.)
(cu. in.) Examined 1
45 axial 3.4 56.0 188.6 277.0 68%
2 45 axial 0.0 34.3 0.0 169.8 0%
3 60 axial 3.3 56.0
. 185.2 277.0 67%
4 60 axial 0.0 34.3 0.0 169.8 0%
5 45 tangent 2.8 71.3 199.7 353.0 57%
6 45 tangent 0.0 19.0 0.0 93.9.
0%
7 60 tangent 2.8 71.3 199.7 353.0 57%
8 60 tangent 0.0 19.0 0.0 93.9 0%
Totals:
773.1 1787.2 43%
STEAM GENERATOR PRIMARY OUTLET NOZZLE (WG5O)
B3.2.6
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This drawing is representative for the following Summary Numbers; B4.5.71.3, B4.5.79.4, B4.5.84.2 and B4.5.108.17.
450,600,700 0
700 VAL%
PIPE
This drawing is representative for the following Summary NumbersB4.5.71.4, B4.5.79.5, and B4.5.84.4.
"4L 45 0,600,700 450600 700 I
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SAFE END PIPE
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PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ENCLOSURE 2 INSERVICE INSPECTION RELIEF REQUEST #09-002-11 THIRD TEN-YEAR ISI INTERVAL
U. S. Nuclear Regulatory Commission 3F0309-01 Page 1 of 6 10 CFR 50.55a Request #09-002-11 Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1.
ASME Code Component(s) Affected ASME Code Class 2 Piping and Nozzles Categories:
C-A, C-B, C-F-1 and C-F-2 Items:
C1.10, C2.21, C5.11, C5.21, C5.51 and Augmented 7.1
- 2.
Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, no Addenda.
- 3.
Applicable Code Requirement
ASME Code,Section XI, Sub-article IWC-2500 states, in part, "Components shall be examined and tested as specified in Table IWC-2500-1." Table IWC-2500-1 requires an examination of applicable Class 2 pressure retaining-welds, which includes 100 percent of weld length once during the ten-year ISI interval for the following Code Categories:
Category C-A: Item C1.10 Category C-B: Item C2.21 Category C-F-i: Items C5.11, C5.21 and Augmented 7.1 Category C-F-2: Item C5.51 Code Case N-460 permits a reduction in examination coverage of Class 1 and Class 2 welds provided the coverage reduction is less than 10 percent. CR-3 has adopted Code Case N-460 in the Inservice Inspection (ISI) Program Plan, as permitted by NRC Regulatory Guide 1.147, Revision 15.
- 4.
Impracticality of Compliance At the time CR-3 was constructed, the ASME Boiler and Pressure Vessel Code only addressed nuclear vessels and associated piping up to and including the first isolation valve. The piping codes of record were USAS B31.7, 1968 Edition for nuclear piping, and USAS B31.1.0-1967 Edition for non-nuclear piping.
10 CFR 50.55a recognizes the limitations to in-service inspection of components in accordance with Section Xl of the ASME Code that are imposed due to early plants
U. S. Nuclear Regulatory Commission 3F0309-01 Page 2 of 6 design and construction.
10 CFR 50.55a(g)(1) states, "For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1, 1971, components (including supports) must meet the requirements of paragraphs (g)(4) and (g)(5) of this section, to the extent practical."
10 CFR 50.55a(g)(1) is applicable since the CR-3 construction permit was dated September 25, 1968.
10 CFR 50.55a(g)(4) states, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code... to the extent practical within the limitations of design, geometry and materials of construction of the components."
10 CFR 50.55a(g)(5)(iii) states, "If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in
§ 50.4, information to support the determinations."
CR-3 has determined that the following welds were limited from achieving greater than 90 percent of the required examination volume for in-service examinations due to component configuration or physical barriers which would require a major modification to the existing hardware. Therefore, relief is being sought from coverage requirements set forth in ASME Code, Section Xl, Sub-article IWC-2500 in accordance with 10 CFR 50.55a(g)(5)(iii).
Relief is requested from performing volumetric examinations of the welds listed in Table A to the extent required by the Code. These examinations are limited by part geometry or interferences with other components such than 10 percent.
that the reduction in coverage is greater Table A
- S/S = stainless steel
- CS= carbon steel Category Item Summary Diameter Thickness Material Coverage Description Number Percentage C-A C1.10 C1.1.5 N/A 1.50" S/S*
42.5 Shell to flange C-B C2.21 C1.2.3 N/A 1.50" S/S 45.5 Nozzle to Shell Weld C-F-1 Augment C2.1.190 18"
.375" S/S 50 Reducer to Flange 7.1 C2.1.192A 10"
.365" SIS 50 Pipe to Valve C2.1.605 10"
.365" SIS 50 Valve to Elbow C2.1.625 8.0"
.322" SIS 50 Elbow to Valve X121.020 10"
.365" SIS 50 Pipe to Valve C5.11 C2.1.104 10" 1.0",
SIS 50 Valve to Pipe C2.1.1477 14"
.375" SIS 50 Elbow to Valve C2.1.163 14"
.375" SIS 50 Valve to Elbow C2.1.167 14"
.375" SIS 50 Elbow to Valve C2.1.170 14"
.375" SIS 50 Pipe to Valve C2.1.184 12"
.375" SIS 50 Valve to Elbow
U. S. Nuclear Regulatory Commission 3F0309-01 Page 3 of 6 Category Item Summary Diameter Thickness Material Coverage Description Number Percentage C2.1.503 14"
.375" S'S 50 Elbow to Valve C2.1.507 14"
.375" S/S 50 Flange to Reducer C2.1.526 10"
.365" S/S 50 Flange to Pipe C2.1. 527 10"
.365" S/S 50 Pipe to Flange C2.1.542 14"
.375" SIS 50 Reducer to valve C2.1.543 14"
.375" SIS 50 Tee to Pipe C2.1.548 14"
.375" SS 50 Elbow to Valve C2.1.600 1 8"
.375" S'S 50 Flange to Reducer C5.21 C2.1.1018 3.0"
.438" S/S 50 Pipe to Valve C2.1.1031 4"
.531" S/S 50 Tee to Tee C2.1.1040 2.5"
.375" S/S 50 Pipe to Valve C2.1.1047 4.0"
.531" S/S 50 Valve to Pipe C2.1.1060 2.5"
.375" S/S 87.5 Tee to Elbow C2.1.1067 3.0"
.438" S/S 50 Pipe to Valve C2.1.1070 3.0"
.438" S/S 86.5 Elbow to Pipe C2.1.1084 3.0"
.438" S/S 50 Valve to Reducer C2.1.1096 4.0"
.531" S/S 50 Pipe to Valve C2.1.1097 4.0"
.531" SIS 50 Valve to Pipe C2.1.1098 4.0"
.531" S/S 50 Pipe to Tee C2.1.1207 2.5"
.375" SIS 50 Valve to Pipe C2.1.1223 2.5"
.375" SIS 50 Valve to Pipe C2.1.1272 2.5"
.375" SS 50 Tee to Pipe C2.1.2073 2.5"
.375" SIS 50 Elbow to Flange C2.1.2078 4.0"
.237" SS 50 Elbow to Flange C2.1.2117 3.0"
.438" S/S 80 Elbow to Pipe C2.1.2136 3.0"
.438" S/S 50 Pipe to Valve C2.1.2137 3.0"
.438" S/S 50 Valve to Pipe C2.1.2162 3.0"
.438" S/S 50 Pipe to Valve C2.1.2164 3.0"
.438" SS 50 Tee to Valve C2.1.2169 3.0"
.438" SIS 50 Valve to Pipe C2.1.2173 3.0"
.438" S/S 50 Pipe to Valve C2.1.2174 3.0"
.438" S/S 50 Tee to Pipe C2.1.2175 3.0"
.438" S/S 50 Pipe to Valve C2.1.2176 3.0"
.438" S/S 50 Valve to Pipe C2.1.2199 3.0"
.438" S/S 50 Tee to Pipe C2.1.2200 3.0"
.438" S/S 50 Pipe to Tee C2.1.2202 3.0"
.438" S/S 50 Pipe to Valve C2.1.2238 4.0"
.531" S/S 50 Pipe to valve C2.1.2240 4.0"
.531" S/S 50 Valve to Pipe C-F-2 C5.51 C2.1.118 6.0"
.8" C/S**
74 Sweepolet to Flange C2.1.121 24.0"
.969" C/S 50 Pipe to Valve C2.1.122 6.0"
.8" C/S 79.86 Sweepolet to Flange C2.1.132 10.0"
.5" C/S 50 Valve to Pipe C2.1.290 6.0"
.8" C/S 74 Sweepolet to Flange C2.1.8 24.0"
.969" C/S 75 Pipe to Valve
U. S. Nuclear Regulatory Commission 3F0309-01 Page 4 of 6 Examination Details C1.10 Shell to Flange Weld: Summary Number C1.1.5 Ultrasonic examination of the subject weld was limited in coverage due to component configuration and/or immovable physical barriers. It is not possible to perform a 100 percent ultrasonic examination from both sides of the weld since one side of the weld was not suitable for scanning based on the scanning surface angle of the component (Flange). Therefore, the weld only received a single sided examination or partial single sided examination resulting in less than 90 percent coverage of the required examination volume. The percentage of coverage reported represents the aggregate coverage from all examination angles and scans performed on the weld and adjacent base material.
The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section Xl Code by the PDI for examination of the pipe welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
C2.21 Nozzle to Shell Weld: Summary Number C1.2.3 Ultrasonic examination of the subject weld was limited in coverage due to component configuration and/or immovable physical barriers. It is not possible to perform a 100 percent ultrasonic examination from both sides of the weld since scanning was performed on the shell side only. The scanning surface of the pipe is perpendicular to the shell surface which prohibits the ultrasonic wave entering the Code required examination volume at an angle that will integrate the weld volume for in-service flaws.
Therefore, the weld only received a single sided examination or partial single sided examination resulting in less than 90 percent coverage of the required examination volume. The percentage of coverage reported represents the aggregate coverage from all examination angles and scans performed on the weld and adjacent base material.
The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section Xl Code by the PDI for examination of the pipe welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
C5.11, C5.21, C5.51 and Auqmented 7.1 Circumferential Pipe Welds: Summary Numbers C-F-1 and C-F-2 Ultrasonic examination of the above pipe welds was limited in coverage due to component configuration and/or immovable physical barriers.
It is not possible to perform a 100 percent ultrasonic examination from both sides of the weld since one side of the weld was not suitable for scanning based on the scanning surface angle of the component. Therefore, the welds only received a single sided examination or partial single sided examination resulting in less than 90 percent coverage of the required examination volume. The percentage of coverage reported represents the aggregate coverage from all examination angles and scans performed on the weld and adjacent base material.
The NDE techniques and procedures used incorporate examination techniques qualified under Appendix VIII of the ASME Section XI Code by the PDI for examination of the pipe welds. (See Attachment A for the cross-sectional view of the weld and limitations.)
U. S. Nuclear Regulatory Commission 3F0309-01 Page 5 of 6
- 5.
Burden Caused by Compliance In order to scan all of the required volume for these welds, the components would have to be redesigned to allow scanning from both sides of the weld, which is impractical.
There were no recordable indications (other than geometric indications) found during the inspection of these welds.
Based on the components designed configuration, the available coverage will not meet the requirements of the ASME Code, Code Case N-578 or Code Case N-460.
In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested for the components listed in Table A on the basis that the required examination coverage of "essentially 100 percent" is impractical due to physical obstructions and the limitations imposed by design, geometry, and materials of construction. CR-3 utilized examination techniques qualified to meet the requirements of ASME Section Xl, Appendix VIII, as required in 10 CFR 50.55a(g)(6)(a)(c), that achieved the maximum practical amount of coverage obtainable within the limitations imposed by the design of the components and examination techniques. Additionally, VT-2 examinations are performed on the subject components of the Reactor Coolant Pressure Boundary during system pressure tests on a periodic frequency. Those examinations were completed and no evidence of leakage was identified for these components.
The mandated requirement in 10 CFR 50.55a(b)(2)(xv)(A)(2)
- states, "Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaw on the opposite side of the weld."
The Appendix VIII techniques applied at CR-3, (PDI-UT-2), are not qualified for "Detection or length sizing of circumferentially oriented flaw indications when only single side access is available and the flaw is located on the far side of the weld."
Based on the design configuration of the components and available examinations techniques, CR-3 was not able to achieve greater that 90 percent Code coverage of the required examination volume for the components listed above without major modifications to the components.
- 6.
Proposed Alternative and Basis for Use No alternative examinations were performed for these welds during the Third Ten-Year ISI Interval. The use of radiography as an alternate volumetric examination for all the above listed components is not practical due to component thickness and geometric configurations.
Other restrictions making radiography impractical are the physical barriers prohibiting access for placement of source, film, image quality indicator, etc.
With due consideration of the earlier plant design, the underlying objectives of the Code required volumetric examinations have been met. The examinations were completed to the extent practical and evidenced no unacceptable flaws present. VT-2 examinations performed on the subject Class 2 components during periodic system pressure testing provide continued assurance that the structural integrity of the subject components is maintained.
Ultrasonic examination of the welds was conducted using personnel qualified in accordance with ASME Section XI, Appendix VII of the 1998 Edition, no Addenda.
U. S. Nuclear Regulatory Commission 3F0309-01 Page 6 of 6 Ultrasonic procedures complied with the requirements of ASME Section V, Article 4 of the 1989 Edition as amended by Section XI, Appendix I. IWC-2500, Table IWC-2500-1, Examination Category C-H System Leakage Tests and VT-2 visual examinations performed on a periodic basis provide adequate assurance of pressure boundary integrity.
In addition to the above Code required examinations (volumetric and pressure test),
there are other activities which provide a high level of confidence that, in the unlikely event that leakage did occur through these welds, it would be detected and proper action taken.
Specifically, system leak rate limitations imposed by Improved Technical Specification 3.4.12, "RCS Operational LEAKAGE," and reactor building normal sump rate monitoring, provide additional assurance that any leakage would be detected prior to gross failure of the component. The component weld was inspected by volumetric and surface NDE methods during construction and verified to be free from unacceptable fabrication defects.
Therefore, reasonable assurance of quality and safety is based on the achieved coverage and results of the volumetric and/or surface and the pressure testing VT-2 examinations performed.
- 7.
Duration of Proposed Alternative Relief is requested for the Third Ten-Year ISI Interval for CR-3, which was effective from August 14, 1998, ending August 13, 2008.
- 8.
Precedents (Optional)
- 9.
References (Optional)
ENCLOSURE 2 ATTACHMENT A COVERAGE DATA INSERVICE INSPECTION RELIEF REQUEST #09-002-11 THIRD TEN-YEAR ISI INTERVAL
c*Nuclear Generation Group Supplemental Report Report No.:
UT-07-O01 Page:
4 of 4
Summary No.: C1.1.5 Examiner: Downs, William R.
Examiner: N/A Other: N/A Level:
111-PDI Level:
N/A Level:
N/A Reviewer:
tely;0edlws Site Review:
I ANII Review: Wyatt, Thomas W.
Date:
-o-7 Date: //-
A2-4,7 Date:
7 7'-
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UT-07-115 Page:
3 of 3
Summary No.: C2.1.1060 Examiner: Gahan, Timothy L.
Examiner: NIA Other: N/A Level:
II-PDI Level:
N/A Level:
N/A Reviewer: -~~Of M/V 6srl4P' Date:/V Site Review:, 7'-1A/4 Date: _
ANII Review: Wyt, Thomas W.
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IV-I Iv Comments: Coverage Calculations (Calculations provided by Shearer, Nicholas H. 11/16/07)
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Nuclear Generation Group Supplemental Report Report No.:
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UT-07-1 15 2
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Summary No.: C2.1.1060 Examiner: Gahan, Timothy L.
Examiner: N/A Other: N/A 774-Level:
IH-PDI Level:
N/A Level:
N/A Reviewer:
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Site Review:
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ANII Review: Wyatt, ThomasW/
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Nuclear l
l Gene'ation Group Supplemental Report Report No.:
UT-07-092 Page:
2 of 3
Summary No.: C2.1.118 Examiner: Downs, William R.
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IlIi-PDI Level:
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N/A Reviewer:
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Page:
UT-07-092 3
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Summary No.: C2.1.118 Examiner: Downs, William R.
Examiner: N/A Other:
N/A Level:
III-PDI Level:
N/A Level:
N/A Reviewer:.
,2,..%
Date:
Site Review:
Date:
ANII Review: Wyatt, Thomas W.
Date:
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UT-07-093 Page:
2 of 3
Summary No.: C2.1.290 Examiner: Downs, William R.
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N/A Level: III-PDI Level:
N/A Level:
N/A Reviewer:
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Examiner: N/A Other: N/A UT-07-093 3
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Date:
Date: 'i '1
-7 Date:.L//Z Level:
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Nuclear Generation Group Supplemental Report Report No.:
UT-07-094 Page:
2 of 2
Summary No,: C2.1.8 Examiner: Downs, William R.
Examiner:
N/A Other: N/A Level:
III-PDI Level:
N/A Level:
N/A Reviewer: JAq,,4 "s'";
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This drawing is representative of the following Summary Numbers; C2.1.543, C2.1.1031, C2.1.1098, C2.1.1272,C2.1.2174, C2.1.2199, and C2.1.2200. The cast Tee material causes the same limitations as a pipe to valve configuration.
Only 50 percent coverage is credited for each exam.
The drawing is not to scale.
600 45.0 PIPE TEE
The following drawing is representative of the following summary numbers; C2.1.190, C2.1.526, C2.1.527, C2.1.600, C2.1.2073, and C2.1.2078.
The drawing is not to scale.
IL 45 0,600,700 3E 70° 700 FLAN(
PIPE
This drawing is representative of the following Summary Numbers;C2.1.192A, C2.1.605,C2.1.625, C2.1.104, C2.1.1477,C2.1.163, C2.1.167, C2.1.170, C2.1.184, C2.1.503, C2.1.542, C2.1.548, C2.1.1018, C2.1.1040, C2.1.1047, C2.1.1067, C2.1.1096, C2.1.1097, C2.1.1207, C2.1.1223, C2.1.2136, C2.1.2137, C2.1.2162, C2.1.2164, C2.1.2169,-C2.1.2173, C2.1.2175, C2.1.2176, C2.1.2202, C2.1.2238, and C2.1.2240.
The drawing is not to scale.
IL 450,600,700 450 600 700 1
VAL%
PIPE
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ENCLOSURE 3 INSERVICE INSPECTION RELIEF REQUEST #09-003-11 THIRD TEN-YEAR ISI INTERVAL
U. S. Nuclear Regulatory Commission 3F0309-01 Page 1 of 6 10 CFR 50.55a Request #09-003-11 Proposed Alternative In Accordance with 10 CFR50.55a(g)(6)(ii)(A)(5) and 10 CFR 50.55a(a)(3)(i)
--Reactor Pressure Vessel Shell Weld Examination--
- 1.
ASME Code Component(s) Affected Reactor Pressure Vessel Lower Shell-to-Transition Piece Weld, Unique Identifier B1.2.1 Reactor Pressure Vessel Nozzle Belt Intermediate Shell Weld, Unique Identifier B1.2.3 Reactor Pressure Vessel Lower Shell to Lower Head Weld, Unique Identifier B1.2.2 Reactor Pressure Vessel Long Seam at 247 degrees, Unique Identifier B1.1.5 Reactor Pressure Vessel Long Seam at 67 degrees, Unique Identifier B1.1.6 Reactor Pressure Vessel Outlet Nozzle-to-Shell Weld, Unique Identifier B1.4.7A Reactor Pressure Vessel Outlet Nozzle-to-Shell Weld, Unique Identifier B13.4.8A
- 2.
Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, no addenda.
- 3.
Applicable Code Requirement
ASME Code, Section Xl, Sub-article IWB-2500 states, in part, "Components shall be examined and tested as specified in Table IWB-2500-1." Table IWB-2500-1 requires an examination of applicable Class 1 pressure retaining-welds, which includes essentially 100 percent of weld length once during the ten-year ISI interval for the following Code Categories:
Category B-A: Item Numbers B1.11 and B1.12 Category B-D: Item Number B3.90 10 CFR 50.55a(g)(6)(ii)(A)(2) requires licensees to implement the examination requirements of the 1989 Edition of ASME Section Xl for reactor vessel shell welds.
Subsection IWB, Table IWB-2500-1, "Examination Category B-A," Item B1.11, requires a 100 percent volumetric examination of all shell welds for the third ten-year ISI interval.
As defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), 100 percent, as used in Table IWB-2500-1, means more than 90 percent of the examination volume of each weld, where the reduction in coverage is due to interference by another component, or part geometry.
U. S. Nuclear Regulatory Commission 3F0309-01 Page 2 of 6 Code Case N-460 permits a reduction in examination coverage of Class 1 and Class 2 welds provided the coverage reduction is less than 10 percent. CR-3 has adopted Code Case N-460 in the Inservice Inspection (ISI) Program Plan, as permitted by NRC Regulatory Guide 1.147, Revision 15.
- 4.
Determination of Limits of Weld Volume Examination Examinations were performed using two Trans World System manipulators and AREVA's Automated Data Acquisition and Analysis System, ACCUSONEX.
All ultrasonic examinations were performed using examination procedures and personnel qualified by demonstration in accordance with the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with Editions up to and Addenda through 2000, as modified by the Performance Demonstration Initiative (PDI) program. These examinations were performed to the acceptance standards of ASME Boiler and Pressure Vessel Code,Section XI, 1989 edition, no addenda. These examinations were performed to the maximum extent possible.
Examinations of the reactor vessel circumferential, longitudinal, and nozzle-to-shell welds, scanned from the vessel shell, were performed using 45 degree shear wave, 45 degree longitudinal wave and 70 degree longitudinal wave transducers.
The circumferential and longitudinal welds were examined by scanning from four opposing beam directions such that the sound energy from the angle beams pass through the weld material and adjacent base material from each direction to the maximum extent possible. The nozzles to shell welds (inlet and outlet) were scanned from the vessel shell using four opposing beam directions and from the bore with beams looking radially.
The scans from the bore used 45 degree shear wave and 15 degree longitudinal wave transducers.
The inside radius sections of the inlet and outlet nozzles were also examined by enhanced visual testing.
For each required scan, the amount of sound beam that passed though the required examination volume has been plotted on scaled cross sectional drawings of each component configuration (see Attachment B). The examination coverages reported in the following table have been determined by averaging the amount of coverage obtained from each of the required scans for the required examination volume.
These examinations are limited by part geometry or interferences with other components, such that the reduction in coverage is greater than 10 percent.
Identifier Description Category Item Coverage Limitation B1.2.1 RPV Lower Shell to-B-A B1.11 46 The core guide lugs and Transition Piece flow distributors interfere with scan paths.
B 1.2.3 RPV Nozzle Belt B-A B1.11 90 Inlet and outlet nozzles Intermediate Weld interfere with the scan paths.
B1.2.2 RPV Transition B-A B1.11 0
Core guide lugs and Piece to Bottom flow distributors prevent Head inspection B1.1.5 RPV Long Seam, at B-A B1.12 88.1 Core guide lugs and 247 degrees flow stabilizers prevented full movement of the head
U. S. Nuclear Regulatory Commission 3F0309-01 Page 3 of 6 Identifier Description Category Item Coverage Limitation B1.1.6 RPV Long Seam, at B-A B1.12 88.1 Core guide lugs and 67 degrees flow stabilizers prevented full movement of the head B1.4.7A A Outlet Nozzle to B-D B3.90 69.8 Surface Geometry RPV Shell Weld B1.4.8A B Outlet Nozzle to B-D B3.90 69.8 Surface Geometry RPV Shell Weld Examination Details Component B1.2.1: Reactor Pressure Vessel Lower Shell-to-Transition Piece Weld The pre-service records reported the examination coverage as "best effort" due to the interferences with core guide lugs and flow stabilizer vanes (see Attachment A, FPC Drawing 135546E, for lug and vane locations).
No pre-service indications were recorded.
During the First Ten-Year ISI Interval examination, the core guide lugs and flow stabilizer vanes were reported as limitations and no indications were recorded.
During the Second Ten-Year ISI Interval examination, the average amount of coverage was calculated to be 29 percent.
During the Third Ten-Year ISI Interval examination, the average amount of coverage has been calculated to be 46 percent. Twelve (12) sections of the weld between the 12 lugs were accessible for examination.
No unacceptable indications have been recorded.
Although the weld area beneath the lugs received no ultrasonic examination coverage, no flaws were identified during a remote VT-3 visual examination of the lug areas. This weld is located outside of the area of highest irradiation in the reactor vessel. (See Attachment B for coverage data.)
Component B13.2.3: Reactor Pressure Vessel Nozzle Belt Intermediate Weld No limitation areas were reported during the pre-service examination of this component.
The weld was examined to the maximum extent possible.
No relevant pre-service indications were recorded.
During the First Ten-Year ISI Interval examination, only 5 percent of the weld length was examined to satisfy the requirements of Table IWB-2500 of the 1974 Edition of ASME Section XI through Summer 1975 Addenda.
No indications were recorded.
During the Second Ten-Year ISI Interval examination, a total of 75 percent of the weld was examined. No unacceptable indications were recorded.
U. S. Nuclear Regulatory Commission 3F0309-01 Page 4 of 6 During the Third Ten-Year ISI Interval examination, a total of 90 percent of the weld was examined.
The remaining ten percent was not accessible due to scanning interferences with the inlet nozzle openings and the outlet nozzle boss extensions. (See Attachment B for coverage data.)
Component B1.2.2: Reactor Vessel Transition Piece to Bottom Head Weld The subject weld is the reactor vessel transition-piece-to-bottom-head-weld. This weld is located below the beltline region and is not subject to the majority of the neutron flux escaping from the core. An evaluation of neutron embrittlement as a potential damage mechanism has been performed with the conclusion that service induced degradation of the transition-piece-to-bottom-head-weld as a result of corrosion, fatigue, nuclear or thermal embrittlement mechanisms is extremely unlikely.
This weld has been visually and ultrasonically inspected once during pre-service inspection (essentially 100 percent coverage).
The volumetric examination method utilized during the pre-service inspection was performed with the manual contact method.
There were no reportable or recordable indications detected during this inspection.
During the First Ten-Year ISI Interval vessel inspection, the weld was partially inspected (approximately 5 percent) using the immersion method of ultrasonic inspection. This was acceptable as per the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition through the Summer of 1975 Addenda, and Regulatory Guide 1.150. The extent of this examination was acceptable since the 1974 Edition of ASME Section XI, Table 2500-1, Category B-A, only required the examination of 5 percent of this weld. The examination was performed using the ARIS II remote scanner, a device that utilized immersion ultrasonic techniques.
The examination revealed no baseline indications, no reportable indications and no recordable indications.
Although the use of immersion testing allowed the weld to be inspected with inspection equipment at a distance of up to twenty inches away from the weld, access for examination of this weld was limited by the flow stabilizers, the core support lugs and the incore instrumentation nozzles.
Since that inspection was performed, improvements in volumetric examination methods have shown the contact method to be much more accurate and reliable than the immersion method.
As a result, equipment designed to use the immersion technique has been abandoned and modern reactor vessel inspection equipment has been designed to utilize the contact examination method.
Relief was granted from this inspection during the Second Ten-Year ISI Interval under Relief Request #95-030 (TAC NO. M93755).
The Third Ten-Year ISI Interval volumetric inspections were not able to be performed using modern automated reactor vessel inspection equipment. The implementation of the requirements of Appendix VIII of the ASME Boiler and Pressure Vessel Code, Section Xl, 1995 Edition with Editions up to and Addenda
U. S. Nuclear Regulatory Commission 3F0309-01 Page 5 of 6 through 2000, as modified by the PDI program, place stringent controls on the methodology utilized in performing this inspection.
Access to the weld from the vessel exterior presents safety and As Low As Reasonably Achievable hazards. Access to the weld to perform the inspection from the outside using a manual contact ultrasonic method would require concrete removal in the cavity and suspension of an inspection team between the exterior of the vessel and inside the shield wall by harnesses.
The reactor vessel interior was subject to VT-I and VT-3 inspections in Refueling Outage 15 during the Fall of 2007 which included all welds and interior attachments.
VT-2 inspections on the exterior of the vessel were performed during the inservice leak test performed during start-up.
No indications were identified during these inspections.
Components B1.1.5 and B1.1.6: RPV Long Seam The Reactor Pressure Vessel (RPV) long seam welds on the lower head to lower shell section are limited by the geometry of the core positioning lugs and the flow stabilizers(see Attachment A, FPC Drawings 135544E and 135546E).
The location of the obstructions prevented the scanning head of the inspection tool to achieve required coverage. During the Second Ten-Year ISI Interval, 94 percent coverage was achieved using a different inspection methodology that was not approved through the PDI process.
Inspections performed as directed by Appendix VIII of the ASME Boiler and Pressure Vessel Code,. Section Xl, 1995 Edition with Editions up to and Addenda through 2000, as modified by the PDI program, are more stringent in transducer selection which allowed for 88.1 percent required coverage for these longitudinal welds.
No unacceptable indications have been identified during the Pre-service, First Ten-Year ISI Interval, Second Ten-Year ISI Interval, or Third Ten-Year ISI Interval examinations of these longitudinal welds.
(See Attachment B for coverage data.)
Components B1.4.7A and B1.4.8A: Reactor Pressure Vessel Outlet Nozzle to Shell Welds The outlet nozzle extension geometry has provided the same limitation area during the Pre-service, First Ten-Year ISI Interval, and Second Ten-Year ISI Interval volumetric examinations of these nozzle welds (see Attachment A, FPC Drawing 135540E). The boss extension limits the circumferential scan coverage to 26 percent. However, 100 percent of the required weld volume and adjacent base material has received 2 axial angle beam scans from the nozzle bore. No unacceptable indications have been identified during the Pre-service, First Ten-Year ISI Interval, Second Ten-Year ISI Interval or Third Ten-Year ISI Interval examinations of these outlet nozzle-to-shell welds.
(See Attachment B for coverage data.)
U. S. Nuclear Regulatory Commission 3F0309-01 Page 6 of 6
- 5.
Proposed Alternative and Basis for Use None.
In lieu of the ASME Code requirement of essentially 100 percent volumetric examination, CR-3 proposes ultrasonic inspections of accessible areas to the maximum extent practical, given the design configuration of the Reactor Pressure Vessel Welds, and VT Inspections of all accessible areas sufficient for continued safe operation.
Additionally, system leak rate limitations are imposed by Improved Technical Specification 3.4.12 and reactor building normal sump rate monitoring provides additional assurance that any leakage would be detected prior to gross failure of the component.
- 6.
Duration of proposed Alternative Relief is requested for the Third Ten-Year ISI Interval of the Inservice Inspection Program for CR-3 which was effective from August 14, 1998, ending August 13, 2008.
- 7.
Precedents (Optional)
NRC granted relief for Augmented Reactor Vessel Shell Weld Examination under Relief Request #98-009-11 on August 5, 1999 (TAC NO. MA1 642).
NRC granted relief for RPV Lower Head to Bottom Shell Weld under Relief Request
- 95-030 on April 14, 1996 (TAC NO. M93755).
- 8.
References (Optional)
ENCLOSURE 3 ATTACHMENT A VESSEL DRAWINGS INSERVICE INSPECTION RELIEF REQUEST #09-003-11 THIRD TEN-YEAR ISI INTERVAL 126951 E 135540E 135543E 135544E 135546E Arrangement Reactor Vessel Long Section Reactor Vessel Detail and Sub-Assembly Outlet Nozzles Vessel Radiographic Outline Vessel Head and Support Assembly Detail Vessel Assembly and Final Machining
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by lh.ýpýIV 45'0 7' r~fr,
,z r~~
~
ifo 7
5 957.5O0ýO0Q Section E"Tab 2 P..ae',jb30:6f 53 EU --
~-
- LC 1_,.
27ý713
, f OW tAROE
>*AS"EUET-r~R ~.jj)
Wde~Idoerntifcaton~
TWS ýNo`.-: W09V 15% & 85%TCoverage Plot "Unlimnitedl' Upper Scan in bolh,Axil ýZ,'bnd Circumierenlil
& Direcions
"..i(dS~n - Perpendl~ular.to weld 51t,90657501-000 5,5ctiibn E,, Tab.!2P Page, :ý,l 6f 513 t
ROW S 2201 0
4M14 4t3iq12 17-", 26 (1#
yf 12 Icn u~ ~i
~4.1 6~
L F Weld !den fificatio.n TWS N~:o9 CR-3¶No,.:B1.21 1%.8?T:Gvrg Clo t-!i~t~YL Sý;I cnjnfol xF taiAN and Circumf rert;,ai &Prjr Qj= S~m n l
P~
a 0 eI.{1 a6.
- (e ea" ao-_
510065756000 1 Secdion E, TbA 2 05ge 32 of 53
CoVerage LaVout & Calculations Weid
Description:
Nozzre Best o Upper Shclt ASME Code Item No.: B.i 1 CR-3 Weld ID:
!3.
2.3 ASME Code Figure No:.ý IWB-2500O1 TWSWcId Designator:,-W02 AREVA Drawing No.: 8019749 AGGREGATE COVERAGE: 90'.0 %
Zone Coverage Obtained Inne~r15%,'T' 854 1 Outer 85 T:.
.941"'
ExaminationVolume Definiticn Vi end Eeth; 275 0$ ci:
'"Area Measurefuent Vo1Wme" Ca1Cu~ition inner I5%T See:Noies q qi
- In ner 35%T Outer.55%T See Noes,sq :in
!&uter :'*5%T
'3:3 Limitations
- Limits scan' by:
Corpens.tjvn(s}
iExamination CoveraceCamu(a:tio s (Tr aeio Sc,ý,Sd - E taiton Exm-r Arua L'*.O£*h Volkmii Volkmco.
Ange.
Beamr.
Exarmned Examnrndc Ex '*itcsd,Roquired Peccent
&2;,Z :.
?2L,45:L: LU:&Dowr*
S~ee 4'-o s
.6244.2 7194i5:
6.8*/,
Y-en.s
- Nczz
,"LW4SL C'W
$K.',........
6090; 7164;6 c,p,,
'es Tot~J:
6 gba 7194:5 65!4%:
OUTER 857T1 Ex*m.
.A*n Ler
- 'olu1£ VOum 6.&:
2 Un, See NP otes 3778,5; 4368435
-6.*6%Y Yes
[;z~
S 4SL?45S C. *"
S-es NLte*
43C72.7 4 5643,6 9S-
&7.
. Y~'*t No~7IeY
~tL~S f'C ~
t
~
4L2~.446 96.7%
Yes Nazzles' 51-9065750-000 S'ecl on E; Tab,2:
.-Page.. 6 0of '5ý3
SUpporttChaOs forAreaExaimined:
dTa A'e b~oý I-x~i7ie 4Yedfi~at I ~kHnrIz6rih1 A~A~'I Z-W1&IW-X
,5.3.1 86;98.
.527'62 1i33',166 8077,86 OUTZA&
Z-W 1531 74"39:
451*27
,1138.;91 o
69094
-1&OTZ15.31 73759' 40464:
1.126:ý66' 6835.00 X-Y.&,* Z 15.31 86.98
,527:62 133166:
80775T86 OUT X & X-Y 15.31 73.9 5
46:
.44A 1126.66'ý 6835.00 VW-,X & OUT X 1.5.31i 74*39 j 451:27'
!38:911 6908.94
.Total:
71,94.5 4,364-3.e6 AiZ.W&:,VV-X 15,31,1 77,76 524.67
.190.51
'803270
'OUT Z & Z-W 1.5.31 6058,.
- 440.1:2
'927:48,"
-,6 7 3,24 Y-7-Z,& O:UCT Z 15.31 6ý0:ý58, 434:30 927:48',
66,49-1A3
).
53, 77162539.85
-9J5!
.8265. 10 S,OL!tT:*dX.&'Y 15.219!
6O0.58;,
- 34'232
'9274a8
,:664.9!:4
',wx.&.OUTX*
15 31 8
60058 4..'1
,927.4.
.738.08 Total 6090.94,
-430 7.Z7
- .~~~~~
~~~
.- _,,&:W:153!
78,5
. :17,7,;66 1I205,66 73t;9 OUT 7i&Z-W 1.31 1 6t'30
, 371"88, 93.5,5693.48 Y Z.& OJJT Z
[15.31 j
C14*
37;2,64 940,49, 5705.12
'XT-Y & :Y,-Z.
Ii5.
j1 -83!s 51.:32.
"280.53.
7,67512i 01.T X &XY 15.31 6ith 3 72.64 940.9
.570512 V
w-X 0& T, 1
10
- 3.
317'.8, 93850 j 5693:8 Total ;'6244.2
.37785.4 51ý9'o6,5750ý-660 51-9065750-000,Sect~ion E, 'Tab.2 Pg f5 Pagq 7"of 53:
.315 Weddenlificlatio-n-,
-9T0C-0 rqge Plot Typi'&o Cros,,S&ab (B otg ;ans.A x Crc) 51-9065150-6oo SEection 'E, Tab 2 PageS8~of 53ý
I /
ý372.64; ýsq in,
/C
/I3NoB12 15% ~ ~
~
~
~
2 85/
O~a t
6~~
&edcli
~ed Vlew'- ~ ~
~
~
~
/
/rs
-atb~iNzl.
oldn Eaajl 51-0065'7k-000-0Section E, Tab,2, Page 9ýof 53
524C57,sq in
- 40.
2,sq in I I.,
- irn 5.3985 WS Nb.ýWq2 16c' &
T C-ov&r~efli'P Pzý1t* fbciumf.n!161a~-
a~fe to wel d) 51 :90d657'506000 Section E, Tab 2.
Page TVO olf 53 E-71" 1--
527.*62 sq in Y;
,z 86698 s-.q in
.45,':.27 s~
451'27 sq in
- 74*39 sq in I4~~
,in
-/
-77I 73-59, sq in' 73*9 s-q iin 4,4644 5q in.
K B9 qin A Wvkld;ciintificatipn,
~TWS No. VW12S
- CR-3 No.: B1. 2,3~
1.5%.'& 85,%,T Total Cr&t'*S'ectio~nai Arda Wow.,- Ctc5.siSedrfph a:'Nozzft Ccnent~ine EJ.ev.Mon
- 5 1 906 5,750-00 Seto E a 2Pg lAf5 SecSME, Tab 2 -,
Page I 1,6f -53
Coveragle Layo ut&, Calculatins Atel'ýd
Description:
LgSea
\\ei C.R-"3 Weld ID:ý BiA.-&
bi,
,TWS Weld.Des~ignator.:: Wbb &,!,,'7 ASME Code item No;: -i12 ASME Code 1Figr.e,N o.: IVB-2500f-2.
AREVA Drawig No.o:
iQ 9749:
AGGRGATEý COVERAGE,:S881%
ZoneCoverage OQbtaineid innar 1%:Qt~8%:
8:%
Limi~tations Liit can,by:.
Com p.emaIOOWs Lu~s Flow St~iI"ers Or 'entingr full
'nym,~d
~.
Brezakigcfrrsc~c&no m~pjhf A
r~n a
imze'scan cavcrafx, INNER 150%T' 2
7Lj 4 L Qw 12-73 492
~
1 90 l~,
h u~&F:o.tbtz 3a 70-4S 1
KZ7 123 4708
~
3 90B 8
[YL Lugs-&, 8rb$tn i
To ri !
2449, 3 f3723:3,,
6~
TOUTER-85%/'T Ln~
C~r Y6§:~
L~wdE~'c rqre
~
rQ~I~ 4..5&1 22126, 1 c5 s INNER 15T(LIMI1TATIONS)
An icle Exri
-3rind E
n n itn~i deis Per'.erý 7 L4L ~ ~
19 130 20 90 Lf YV
- 7.
1yWzs & F S. bza s OUTER 85%/T (LIMITATIONS)
Ex4 51i 7erS-t
-71
-0n
`553
'L~g-2 EL35 cwtil 41 6
259 I 05 531 ~ ~
- 5.
Y Lugs E t, TotI: 38523.9 169 3 23.2' 51-9065750-000 5,Section E, Tab.,2e Palge- -1 9;o.f 53
AA S
.ý i.
TWS No.:
- v'06
&*I 1 ~
cy
~ 71cd(A 5 1 -906575ý-oc,ý'-)
Section E, Tab 22 pa (I a 2, f") 0
15%.&85%
CvergePlo (Ckica -
erpendicular to weld)
Weld Identfictio TWVS No. VV~OS & WO7'
-CR-3 No.:1 5'! -w'65 0Section, E, Tab2:2 Paq&2.11.of 5'ý
75.65 sq in 12.73
-Sq in WedIden tifct-IC4(o.n
~TWS No.: %N06 & WV07
~CF-3,N.: 8I1A.5 & 8i41.6~
15% & 85%/,T Tolal `Cro Setionaf Area
,51-9065750-000 Sbectin E, Tab 2' Page 22,f 53
~Z7Z.
Vow rm r1 A -11 View frorWV&Vessel ID looking but "U Nlimited'. Upoer Scan Regionsshown,(W06 & WO7 circlod}
I 51 -W'657,56ý-ibob 9Section E, Tab 2 P*,ge,"23:6,or53*'
My i'ý.
I M7 "V;
uq p
lw Th'!ý'-Th 10,-
B z~j~~W07;
-u ThtC-7
- 09. ~~x Liprcnxtf View troýf 61~ I0,10Ok'ing bq'u't ýLiniifqdt' L6(er.Scaiý Reio W0 h
WO dr'6160
<WedI&Pen~tificationl
-nWs No:,W067& %V07 CIR 3 No.:B1V1:.&ZiB 51-9065750-000 Section tE, Tab 22 Page,,24 of 513;
Coverage Layout &.Calculations Neld
Description:
..utlet Nozzleto Shell-@x Xaxis & Z axisý,
ASMVIE Code Item No-: B3.90 ASME Code FigureNo.:.vB-2500-7<.
CR-3 Weld ID (TWS Weld DesignatOr), B,4.74A (W15) and
-.48A(,W2,3 AIREVA pDrra ing No,-4: 8019t7?49;.
AGGREG'ATECOVERAGE: 69.8%
.Zon.iie :Co6ve*a ge:..Obt~a.!n.ed:
1inner 15%T.,:
Outer 5 1000%
Examination Vo u hie Definlt0on
.Area, Measurement" Volume-( altul ltion,'ý'
Lmitatins
- Limits-scan nby:
- compensation(),
Y~s W~ld/scan'sHie 9eiphiry:
.Exahi'nnatio~n Cover~ag e.'Calculatiohns (ie'ated oS ;Dual Sided.Exaemi*;io4n })"
INNER 15%T Exa.
Lc.qi im V ue, (t.. m (ue.q 'red Pexent
[
'1j45L
'B6F:iR':dia1i:.*ut
- 360!
t3d000
,i3.0*00*9 1LXJG0.%
" *Y'*
4 7 0 U 4 5 L C O W 66
,~L1 0 0Y s
Th~a'is*
2081:6 52"0"00 39.6%
OUTER 85%T Anl ~
a
~
f.k.Exa!in.
Requi ( ed P~ren-,tL 1."'5LI4~5S :Bor~e:~adia.ut
'36a
.:C2 59':2, 12859'2 1L.}0F0%
No Toa/s:t 12859.2 :"2859.2 100O**.
51 ý466ý 57,56, _,60"b" 05 -ect
¢ion E.. Tab 2;ýP Raae 38: of, 53;
92.85 9q in 7.95 sq in 81.30 sq fn 6%9sq i (ThtI) 1~~~~
I 5TCvr~
pk', (R ad il Sa n Peprdcikv~
rom,JQzzle &org)
'.Weld lientifica fon CR3~ No. (TWS No.): B 1 A 7A (I, 15), B,1.- t~W"23)i 51-9065750-0,OT
'Section E, Tjýb,2,-
Paoe 39 bf 53,
0.61 h.
4.41 s in 15%T ~iyea~jePioffk'6
-C, --PSi -
R jrp i6iicuae tb~w&6 r" i IeUI m i~cain qowabn Boteel I(
5'1 7.906,5750-000
,Seconio E, Tab2e42' Pa'ge.40, of 53 777-
0.00,-i; 16 5%T Coverae F46t uC~ tmfeer Thal. S.SeaP - P~iraell to wvekd ftrom Shell ID) 7Weld ldpr~ififktion CR3ý No. (TWSNo.): B1A47eA W:)BAA(
151 -'90,65,750-000 51
-9065750-QOO S'6tticn'E, 76b.2 ae 1of P';4ge.'4.11 bf-,5-3' r