ML021130463
| ML021130463 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/12/2002 |
| From: | Swafford P Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PSLTR: #02-0014 | |
| Download: ML021130463 (12) | |
Text
Exel n.
Exelon Generation www.exeloncorp.com Nuclear Dresden Generating Station 6500 North Dresden Road Morris, IL60450-9765 Tel 815-942-2920 10 CFR 50.55a(g)(5)(iii)
April 12, 2002 PSLTR: #02-0014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Relief Request CR-24, Inservice Inspection Program Relief regarding Examination Coverage for Third Inservice Inspection Program Interval
Reference:
Letter from U. S. NRC to 0. D. Kingsley (Commonwealth Edison Company),
"Quad Cities, Units 1 and 2 - Relief Request CR-32 for Third 10-Year Inservice Inspection Interval," dated September 6, 2000 In accordance with 10 CFR 50.55a, "Codes and Standards," paragraph (g)(5)(iii), Dresden Nuclear Power Station (DNPS) is requesting relief from American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements is impractical due to plant design. DNPS is submitting this relief request for those ASME Section XI weld examinations performed during the third Inservice Inspection Interval where the inspection coverage achieved was less than or equal to 90%. Specifically, this includes examinations completed during the first and second periods of the third Inservice Inspection Interval for both Units 2 and 3.
The proposed relief request is for the first and second periods of the third Inservice Inspection Interval for both Units 2 and 3. For Unit 2, the third Inservice Inspection Interval began on March 1, 1992, and the projected end date is January 19, 2003. For Unit 3, the third Inservice Inspection Interval began on March 1, 1992, and the projected end date is October 31, 2002.
This relief request is similar to a request granted for the Quad Cities Nuclear Power Station in the referenced letter.
April 12, 2002 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning his letter, please contact Mr. B. Rybak at (815) 416-2800.
Respectfully, Preston Swafford Site Vice President Dresden Nuclear Power Station cc: Regional Administrator- NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 1 of 10)
COMPONENT IDENTIFICATION Code Classes: 1 2
References:
Subarticle IWB-2500 Subarticle IWC-2500 Examination Categories: B-A, B-D, & B-J C-B, C-C & C-F-2 Item Numbers: B1.22, B1.40, B3.90, B3.100, B9.11 & B9.31 C2.21, C3.20, C3.30, & C5.51
==
Description:==
Volumetric and Surface Examination Coverage Component Numbers: Various, see Table CR-24.1 and TABLE CR-24.2 CODE REQUIREMENT Subarticle IWB-2500 states in part "Components shall be examined and tested as specified in Table IWB-2500-1." Table IWB-2500-1 requires a volumetric examination or a surface and volumetric examination be performed on the component based on Category and Item Number.
The applicable examination area or volume and method required is as shown below from Table IWB-2500-1:
Examination Item Examination Requirements Examination Method Category Number /Figure Number B-A B1.22 IWB-2500-3 Volumetric B-A B1.40 IWB-2500-5 Surface and Volumetric B-D B3.90 IWB-2500-7(a) Volumetric IWB-2500-7(b)
B-D B3.100 IWB-2500-7(a) Volumetric IWB-2500-7(b)
B-J B9.1 1 IWB-2500-8(c) Surface and Volumetric B-J B9.31 IWB-2500-10 Surface and Volumetric Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 2 of 10)
Subarticle IWC-2500 states in part "Components shall be examined and pressure tested as specified in Table IWC-2500-1 ." Table IWC-2500-1 requires a surface examination or a surface and volumetric examination be performed on the component based on Category and Item Number. The applicable examination area or volume and method required is as shown below from Table IWC-2500-1:
Examination Item Examination Requirements Examination Method Category Number /Figure Number C-B C2.21 IWC-2500-4(b) Surface & Volumetric C-C C3.20 IWC-2500-5(a) Surface IWC-2500-5(b)
C-C C3.30 IWC-2500-5(a) Surface C-F-2 C5.51 IWC-2500-7(a) Surface & Volumetric CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from performing a complete coverage examination of the entire volume or area required. Entire volume or area required is defined by ASME Section XI Code Case N 460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1."
Code Case N-460 states in part, "...when the entire examination volume or area cannot be examined.. .a reduction in examination coverage.. .may be accepted provided the reduction in coverage for that weld is less than 10%." DNPS invokes Code Case N-460 for use during the third Inservice Inspection Interval.
NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent"...has been applied to all examinations of welds or other areas required by ASME Section Xl."
Relief is requested from performing an examination of "essentially 100%" of the required volume or area as applicable for the identified components in Table CR-24.1 and Table CR-24.2.
BASIS FOR RELIEF In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that the required "essentially 100%" coverage examination is impractical due to physical obstructions and limitations imposed by design, geometry and materials of construction for the components of Table CR-24.1 and Table CR-24.2.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 3 of 10)
BASIS FOR RELIEF (CONT'D)
DNPS, Units 2 and 3, obtained Construction Permits CPPR-18 and CPPR-22 on January 10, 1966 and October 14, 1966 respectively. The piping systems and associated components were designed and fabricated before the examination requirements of ASME Section XI were formalized and published. Since this plant was not specifically designed to meet the requirements of ASME Section XI, compliance is not feasible or practical within the limits of the current plant design.
Physical obstructions imposed by design, geometry and materials of construction are typical of vessel appurtenances and sacrificial shield, insulation support rings, structural and component support members, adjacent component weldments in close proximity, unique component configurations and dissimilar metal weldments.
Improved examination techniques have been progressively upgraded during this interval to augment the required Section XI examinations. We have used the Electric Power Research Institute (EPRI), the Performance Demonstration Initiative (PDI), Inservice Inspection vendors and other industry sources to encourage the development of and provide an awareness of improved examination techniques to enhance coverage and flaw detection commensurate with radiation dose reduction.
Exelon examination procedures are revised on a continuing basis to incorporate proven techniques for a higher level of safety and quality as they become available. The examinations and techniques used today exceed the examinations conducted in the past on each component.
All components received as a minimum, the required examination(s) applicable to the extent practical due to the limited or lack of access available. The examinations conducted, confirmed satisfactory results evidencing no unacceptable flaws present, even though "essentially 100%"
coverage was not attained. Exelon has concluded that if any active degradation mechanisms were to exist in the subject welds, those degradations would have been identified in the examinations performed.
Based on the above, with our earlier design, the underlying objectives of the code required volumetric and surface examinations have been met. The examinations were completed to the extent practical and evidenced no unacceptable flaws present. Additionally, a VT-2 examination performed on the subject components during system pressure test per examination category B-P each refueling outage and category C-H each period provides additional assurance that the structural integrity of the subject components is maintained.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 4 of 10)
PROPOSED ALTERNATE EXAMINATIONS DNPS will continue to perform best effort examinations in order to achieve the maximum amount of coverage. Additionally, a VT-2 examination performed on the subject components during system pressure test per examination category B-P each refueling outage and category C-H each inspection period is performed.
APPLICABLE TIME PERIOD Relief is requested for the third ten-year interval of the Inservice Inspection Program for DNPS Units 2 and 3.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 5 of 10)
TABLE CR-24.1 UNIT 2 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent B-A RPV 2-THD-M1 MERIDIONAL REACTOR HEAD LIFTING UT B1.22 UPPER HEAD WELD LUG. 86.01 B-A RPV 2-THD-FLGA HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 2-THD-FLGB HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 2-THD-FLGC HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 2-THD-FLGD HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 2-THD-FLGE HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 2-THD-FLGF HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-D RPV N19A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 33 CONFIGURATION.
B-D RPV N19B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.51 CONFIGURATION.
B-D RPV N1A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.07 CONFIGURATION.
B-D RPV N20A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 73.52 CONFIGURATION.
B-D RPV N2A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2C-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 6 of 10)
TABLE CR-24.1 UNIT 2 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent B-D RPV N2D-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2E-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2F-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N4A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 25.5 CONFIGURATION.
B-D RPV N4B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 25.5 CONFIGURATION.
B-D RPV N4C-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 25.5 CONFIGURATION.
B-D RPV N4D-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 25.5 CONFIGURATION.
B-D RPV N5B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.06 CONFIGURATION.
REACTOR VESSEL WELDED ATTACHMENT.
B-D RPV N9-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 29.5 CONFIGURATION.
B-D RPV N5B-1 NOZZLE INNER REACTOR VESSEL UT B3.100 NOZZLE RADIUS SECTION WELDED ATTACHMENT. 49.98 B-J REACTOR PD4-D22 LONG SEAM WELD ID BAND. PT B9.11 RECIRCULATION (Long Seam) WELD ADJACENT 88 02011H-12 TO OVERLAY OF UT ELBOW TO PIPE 88 WELD B-J REACTOR PD5-D21 LONG SEAM WELD ID BAND AND WHIP PT B9.11 RECIRCULATION (Long Seam) WELD ADJACENT RESTRAINT. 29 0201IJ-12 TO OVERLAY OF UT PIPE TO ELBOW 29 WELD Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 7 of 10)
TABLE CR-24.1 UNIT 2 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent B-J REACTOR PD6-D19 LONG SEAM WELD ID BAND AND WHIP PT B9.11 RECIRCULATION (Long Seam) WELD ADJACENT RESTRAINT. 29 0201 K-12 TO OVERLAY OF UT PIPE TO ELBOW 29 WELD B-J REACTOR PD8-D10 LONG SEAM WHIP RESTRAINT. PT B9.11 RECIRCULATION (Long Seam) WELD ADJACENT 33 0201D-12 TO OVERLAY OF UT PIPE TO ELBOW 25 WELD B-J REACTOR PD9-D8 LONG SEAM WELD ID BAND AND WHIP PT B9.11 RECIRCULATION (Long Seam) WELD ADJACENT RESTRAINT. 21 0201E-12 TO OVERLAY OF UT PIPE TO ELBOW 15 WELD C-C HPCI M-1151D-155 INTEGRALLY PIPE CLAMP MT C3.20 2304-14 WELDED INTERFERENCE WITH 88.39 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C HPCI M-1151D-132 INTEGRALLY PIPE CLAMP MT C3.20 2305-10 WELDED INTERFERENCE WITH 77.78 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C LPCI M-3214-17 INTEGRALLY PIPE CLAMP MT C3.20 1509-16 WELDED INTERFERENCE WITH 75 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C LPCI M-3209-13 INTEGRALLY PIPE CLAMP MT C3.20 1519-18 WELDED INTERFERENCE WITH 72.73 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C LPCI M-3208-07 INTEGRALLY PIPE CLAMP MT C3.20 1517-14 WELDED INTERFERENCE WITH 80 ATTACHMENT SHEAR LUG ATTACHMENT.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 8 of 10)
TABLE CR-24.1 UNIT 3 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent B-A RPV 3-THD-FLGA HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 3-THD-FLGB HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 3-THD-FLGC HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 3-THD-FLGD HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 3-THD-FLGE HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-A RPV 3-THD-FLGF HEAD TO FLANGE REACTOR HEAD TO UT B1.40 UPPER HEAD WELD FLANGE 71.47 CONFIGURATION.
B-D RPV N12-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 75.31 CONFIGURATION.
B-D RPV N19A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.51 CONFIGURATION.
B-D RPV N19B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.51 CONFIGURATION.
B-D RPV N1A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.07 CONFIGURATION.
B-D RPV N1B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.7 CONFIGURATION.
B-D RPV N2B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2D-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N2E-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 I _CONFIGURATION.
Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 9 of 10)
TABLE CR-24.1 UNIT 3 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent B-D RPV N2G-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.85 CONFIGURATION.
B-D RPV N3C-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 72 CONFIGURATION.
B-D RPV N3D-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 72 CONFIGURATION.
B-D RPV N4A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.49 CONFIGURATION.
B-D RPV N4B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.49 CONFIGURATION.
B-D RPV N4C-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.49 CONFIGURATION.
B-D RPV N4D-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.49 CONFIGURATION.
B-D RPV N5A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.06 CONFIGURATION.
B-D RPV N5B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.06 CONFIGURATION.
B-D RPV N18A-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.4 CONFIGURATION.
B-D RPV N18B-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 20.4 CONFIGURATION.
B-D RPV N8-2 NOZZLE TO NOZZLE, RADIUS BLEND UT B3.90 NOZZLE VESSEL WELD AND WELD 47.24 CONFIGURATION.
B-J REACTOR RRB-59F ELBOW TO PIPE TO ELBOW WELD UT B9.11 RECIRCULATION ELBOW WELD CONFIGURATION. 75.9 0202B-28 B-J MAIN STEAM 8X-15 BRANCH PIPE BRANCH PIPE UT B9.31 3001A-20 CONNECTION CONFIGURATION. 50.5 WELD B-J MAIN STEAM 8X-10 BRANCH PIPE BRANCH PIPE UT B9.31 3001C-20 CONNECTION CONFIGURATION. 51.4 I_ I WELD Revision 0
ISI Program Plan Dresden Nuclear Power Station Units 2 & 3, Third Interval RELIEF REQUEST NUMBER: CR-24 (Page 10 of 10)
TABLE CR-24.1 UNIT 3 COMPONENTS WITH LESS THAN "ESSENTIALLY 100%" COVERAGE Section XI Component Component Component Condition Limiting Examination Category System Number Description Coverage &
& & Coverage Item No. Line Percent C-B ISO 12-8 NOZZLE TO NOZZLE, RADIUS BLEND UT C2.21 CONDENSOR SHELL WELD AND WELD 44.56 1302A-12 CONFIGURATION.
C-B ISO 12-9 NOZZLE TO NOZZLE, RADIUS BLEND UT C2.21 CONDENSOR SHELL WELD AND WELD 44.56 1302B-12 CONFIGURATION.
C-C CRD M-1188D-1120 INTEGRALLY BOXGUIDE MT C3.20 0409A-20 WELDED INTERFERENCE WITH 85.96 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C CORE SPRAY M-3408-24 INTEGRALLY BOX GUIDE MT C3.20 1404-12 WELDED INTERFERENCE WITH 87.30 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C HPCI M-1187D-72 INTEGRALLY BOX GUIDE MT C3.20 2304-14 WELDED INTERFERENCE WITH 56 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C ISO M-1199D-258 INTEGRALLY PIPE CLAMP PT C3.20 CONDENSOR WELDED INTERFERENCE WITH 82.69 1303-12 ATTACHMENT SHEAR LUG ATTACHMENT.
C-C CORE SPRAY M-1186D-1016 INTEGRALLY PUMP TO SKIRT IWA MT C3.30 PMP 3A-1401 WELDED CONFIGURATION. 61.94 ATTACHMENT C-C LPCI M-1200D-1017 INTEGRALLY PUMP TO SKIRT IWA MT C3.30 PMP 3A-1502 WELDED CONFIGURATION. 61.94 ATTACHMENT C-F-2 CRD 6-401 ELBOW TO PIPE ADJACENT PLANT MT C5.51 0408A-6 WELD STRUCTURE. 80.95 UT 78.31 C-F-2 CRD 6-74 TEE TO PIPE ADJACENT PLANT MT C5.51 0408A-6 WELD STRUCTURE. 71.96 C-F-2 LPCI 14-1 (A) PIPE TO VALVE PIPE TO VALVE WELD UT C5.51 1517-14 WELD CONFIGURATION. 86.35 Revision 0