RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
| ML23312A092 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/08/2023 |
| From: | Humphrey M Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RS-23-107 | |
| Download: ML23312A092 (1) | |
Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-23-107 10 CFR 50.55a November 8, 2023 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval In accordance with 10 CFR 50.55a, "Codes and standards," Paragraph (g)(5)(iii), Constellation Energy Generation, LLC (CEG), requests NRC approval of the attached relief request associated with the fifth inservice inspection (ISI) interval for Dresden Nuclear Power Station, Units 2 and 3 (DNPS). Relief is requested due to the impracticality of satisfying the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
due to plant design. The fifth ISI interval for DNPS ended January 19, 2023.
The relief request is based on the limitations that precluded completion of full Code examination requirements of ASME Class 1 and 2 welds during the fifth interval. Code examination of the welds was limited due to the materials of construction and design configurations. The DNPS fifth ten-year ISI program plan met the requirements of ASME Code,Section XI, 2007 Edition with 2008 Addenda.
CEG requests approval of these requests by November 8, 2024.
There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (779) 231-5765.
Respectfully, Mark D. Humphrey Sr. Manager - Licensing Constellation Energy Generation, LLC
Attachment:
Dresden Nuclear Power Station 10 CFR 50.55a Request No. I5R-22 Humphrey, Mark D.
Digitally signed by Humphrey, Mark D.
Date: 2023.11.08 08:34:13 -06'00'
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 1 of 18)
- 1. ASME Code Component(s) Affected Code Class:
1 and 2
References:
IWB-2500, IWC-2500, Table IWB-2500-1, Table IWC-2500-1, ASME Code Case N-578-1, Table 1 Examination Category:
B-A, B-D, B-K, C-B, R-A Item Number:
B1.12, B3.90, B10.10, B10.20, C2.21, R1.11, R1.20
==
Description:==
Limited examination coverage Component Number:
See Tables A and B below for specific component identification
2. Applicable Code Edition and Addenda
The Fifth 10-Year Interval of the Dresden Nuclear Power Station (DNPS), Units 2 and 3 Inservice Inspection (ISI) Program ended on January 19, 2023, and was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)
Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components,"
2007 Edition with the 2008 Addenda.
CEG maintains the responsibility to ensure examinations were performed in accordance with the requirements of ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," as amended and mandated by 10CFR50.55a and as modified by the Performance Demonstration Initiative (PDI) Program description. In the case of limited examinations, efforts were made to obtain additional examination coverage. Tables A and B identify whether each listed best effort examination was performed in accordance with the requirements of ASME Section XI, Appendix VIII. Enclosures 1 and 2 provide additional details and information supporting this request.
- 3. Applicable Code Requirement(s)
IWA-2200(c) requires that "All nondestructive examinations of the required examination surface or volume shall be conducted to the maximum extent practical. When performing VT-1, surface, radiographic, or ultrasonic examination on a component with defined surface or volume, essentially 100% of the required surface or volume shall be examined.
Essentially 100% coverage is achieved when the applicable examination coverage is greater than 90%; however, in no case shall the examination be terminated when greater than 90% coverage is achieved, if additional coverage of the required examination surface or volume is practical."
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 2 of 18)
Table IWB-2500-1, Examination Category B-A, Item Number B1.12, requires a volumetric examination of the Reactor Vessel shell longitudinal welds in accordance with Figure IWB-2500-2. The extent of examination is essentially 100% of the required examination volume and surface, as specified in IWA-2200(c).
Table IWB-2500-1, Examination Category B-D, Item Number B3.90, requires a volumetric examination of the Reactor Vessel nozzle-to-vessel welds in accordance with Figure IWB-2500-7. The extent of examination is essentially 100% of the required examination volume, as specified in IWA-2200(c).
Table IWB-2500-1, Examination Category B-K, Item Number B10.10, requires a surface examination of welded attachments to pressure vessels in accordance with Figure IWB-2500-13, Figure IWB-2500-14, or Figure IWB-2500-15. The extent of examination is essentially 100% of the required surface, as specified in IWA-2200(c).
Table IWB-2500-1, Examination Category B-K, Item Number B10.20, requires a surface examination of welded attachments to piping in accordance with Figure IWB-2500-13, Figure IWB-2500-14, or Figure IWB-2500-15. The extent of examination is essentially 100%
of the required surface, as specified in IWA-2200(c).
Table IWC-2500-1, Examination Category C-B, Item Number C2.21, requires a surface and volumetric examination of pressure retaining nozzle welds in vessels in accordance with Figure IWC-2500-4(a), (b), (c), or (d). The extent of examination is essentially 100% of the required surface and volume, as specified in IWA-2200(c).
The Risk-Informed ISI Program (RI-ISI) in accordance with EPRI Topical Report TR-112657, Revision B-A and ASME Code Case N-578-1 was used during the Fifth ISI Interval per Relief Request I5R-02, which was authorized on September 30, 2013 (ML13260A585). The extent of examination requirement for Examination Category R-A, Item Numbers R1.11 and R1.20 per Table 1 of ASME Code Case N-578-1 requires a volumetric examination of essentially 100% of the required volume of the Risk Informed Inservice Inspection (RI-ISI) weld in accordance with Figures IWB-2500-7(a), IWB-2500-8(c), IWB-2500-9, IWB-2500-10, or IWB-2500-11, as applicable.
4. Impracticality of Compliance
In accordance with 10CFR50.55a(g)(5)(iii), relief is requested on the basis that conformance with these ASME Section XI requirements is impractical since conformance would require extensive structural modifications to the component or surrounding structure.
Due to the original design of these components, CEG is unable to satisfy the ASME,Section XI requirements to perform a surface or volumetric examination to the extent required for welds and welded attachments (greater than 90% of the required examination volume or area) identified in Tables A and B due to physical component configuration, interference from permanent plant equipment, single-sided access, etc. CEG would incur significant engineering, material, and installation costs to perform such modifications without
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 3 of 18) a compensating increase in the level of quality and safety. Therefore, relief is requested on the basis that the ASME Section XI requirements to examine these components are impractical.
During outages, when situations were identified where coverage was an issue, DNPS personnel reviewed the systems for alternatives. For the RI-ISI weld population, Examination Category R-A welds, submitted in this relief request, a case-by-case review was performed to determine whether additional or alternative welds could have been examined to supplement the reduced volumetric coverage examination. It was determined that there were no other welds to select that would have resulted in better coverage. This determination was made based on comparison of configurations, delta core damage frequency (CDF) values, the systems involved, and inspection history.
Tables A and B provide a summary of the examination limitations for each component for which relief is requested. The tables also indicate the outage the component was examined, the coverage percentage obtained for each component, and other pertinent design information. This table is the cumulative list of the limited ASME,Section XI examinations performed during the Fifth ISI Interval. Enclosures 1 and 2 provide coverage plots which were extracted from the non-destructive examination (NDE) summary sheets that detail the examination limitations.
Based on the above explanation, CEG requests relief from the ASME,Section XI requirement of IWA-2200(c) that requires at least 90% coverage for volumetric and surface examinations for the items included in this request, based on the position that compliance with the required examination coverage is impractical.
5. Burden Caused by Compliance
Compliance with the applicable ASME Section XI volumetric and surface examination requirements can only be accomplished by redesigning and refabricating the subject and/or surrounding components. Based on this, the ASME Section XI requirements are deemed impractical in accordance with 10CFR50.55a(g)(5)(iii).
6. Proposed Alternative and Basis for Use
CEG has performed the ASME Section XI required examinations for DNPS, Units 2 and 3 to the maximum extent practical (Code Coverage), or best effort, which are documented in Tables A and B. Due to the physical interferences or component geometry, there are no alternative examination techniques currently available to increase examination coverage.
There were no cases in any of the listed examination where the components outside diameter surface features (i.e., weld crowns, weld shrinkage, surface roughness, etc.) could have been conditioned to obtain the required coverage without major modification to the components.
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 4 of 18)
During the Fifth Inservice Inspection Interval, periodic system pressure tests that include VT-2 visual examinations were performed in accordance with ASME Section Xl, Table IWB-2500-1, Examination Category B-P for Class 1 pressure retaining welds and components during each refueling outage, and Table IWC-2500-1, Examination Category C-H for Class 2 pressure retaining welds and components during each inspection period. These periodic system pressure tests and VT-2 examinations provided additional assurance that the structural and leak-tight integrity of the subject components was maintained throughout the Fifth Inservice Inspection Interval.
Volumetric and/or surface examinations were performed to the maximum extent practicable on components in this request, as required by the ASME Section XI ISI Program, the RI-ISI Program, and other applicable augmented examination programs (e.g., IGSCC Program).
7. Duration of Proposed Alternative
Relief is requested for the fifth ten-year inspection interval of the Inservice Inspection Program for DNPS, Units 2 and 3.
8. Precedents
The following similar end of interval impracticality relief requests have been previously authorized by the NRC:
- Dresden Nuclear Power Station, Units 2 and 3 Fourth ISI Interval Relief Request I4R-17 NRC Safety Evaluation dated October 30, 2015 (ADAMS Accession No. ML15265A164)
- Watts Bar Nuclear Plant, Unit 1 Second ISI Interval Relief Request 1-ISI-21 was authorized per NRC Safety Evaluation (SE), dated April 12, 2019 (ADAMS Accession No. ML19071A009).
- Limerick Generating Station, Units 1 and 2 Third ISI Interval Relief Request I3R-23 was authorized per NRC SE dated August 7, 2018 (ADAMS Accession No. ML18192C172).
- Surry Power Station Unit 2 Fourth ISI Interval Relief Requests LMT-R01, LMT-C02, and LMT-C03 were authorized per NRC SE dated February 17, 2017 (ADAMS Accession No. ML16365A118).
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 5 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV Shell/N1A-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 28"/6.25" 60°/3.0/RL 70°/1.0/Shear 60°/1.0/Shear 64.9%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel). This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 2,3) 2/1/RPV Shell/N1B-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 28"/6.25" 60°/3.0/RL 70°/1.0/Shear 60°/1.0/Shear 64.9%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel). This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 4,5) 2/1/RPV Shell/N2C-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 12"/6.25" 60°/3.0/RL 60°/1.0/Shear 74.2%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel). This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 6, 7) 2/1/RPV Shell/N2F-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 12"/6.25" 60°/3.0/RL 60°/1.0/Shear 74.2%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel). This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 8, 9) 2/1/RPV Shell/N2H-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 12"/6.25" 60°/3.0/RL 60°/1.0/Shear 74.2%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel). This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 10, 11)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 6 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV Shell/N5B-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-302B (RPV)/SA-336 (Nozzle) 14"/6.25" 60°/3.0/RL 60°/1.0/Shear 62.8%
Yes The examination was limited due to nozzle configuration (nozzle-to-vessel) and a stabilizer lug below the nozzle. This was a single sided examination. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 12, 13) 2/1/1506-16/M-1164D-296(IWA)
Support Plate Welded Attachment to Piping (LPCI)
IWB-2500-15 Surface (PT) 1 B-K B10.20 D2R25 A358, Gr. 304 (Pipe)/Carbon Steel (Support Plate)
Attachment Thickness 1.219" NA 55%
N/A The examination was limited due to inner attachment welds being inaccessible for 8" along plates A and B. Five recordable rounded indications (none exceeding 7/32")
were detected during this examination.
(Enclosure 1 - Pg. No. 14) 2/1/RPV SHELL/M-1175D-1(IWA)
Stabilizer Bracket Welded Attachment to Reactor Vessel (RPV)
IWB-2500-15 Surface (MT) 1 B-K B10.10 D2R25 SA-302B (RPV)
A-36 (Stabilizer Bracket)
Attachment Thickness 2.5" N/A 56%
N/A The examination was limited due to inaccessibility of a portion of the Stabilizer Bracket. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. No. 15) 2/1/RPV SHELL/N19A-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R25 SA-336 to SA-302B Weld 10"/6.25" 60/3.0/Long 55/1.0/Shear 70.7%
Yes The examination was limited due to nozzle configuration and a permanent insulation support 11.5" below the nozzle boss at Bottom Dead Center. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 16 - 18) 2/1/RPV SHELL/N4A-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R25 SA-336 to SA-302B Weld 12"/6.25" 60/3.0/Long 55/1.0/Shear 74%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 19, 20)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 7 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV SHELL/N4B-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R25 SA-336 to SA-302B Weld 12"/6.25" 60/3.0/Long 55/1.0/Shear 74%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 21, 22) 2/1/RPV SHELL/N4C-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R25 SA-336 to SA-302B Weld 12"/6.25" 60/3.0/Long 55/1.0/Shear 74%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 23, 24) 2/1/RPV SHELL/N4D-2 RPV Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R25 SA-336 to SA-302B Weld 12"/6.25" 60/3.0/Long 55/1.0/Shear 74%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 25, 26) 2/1/RPV SHELL/2-SC1A-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 89%
Yes The examination was limited due to the proximity of the jet pump riser. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 27, 28) 2/1/RPV SHELL/2-SC1B-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 40.2%
Yes The examination was limited due to the shroud repair tie rod. Two recordable flaws were detected during this examination.
These flaws were identified during previous examinations and were determined to be acceptable.
(Enclosure 1 - Pg. Nos. 29, 30) 2/1/RPV SHELL/2-SC1C-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 41.4%
Yes The examination was limited due to the shroud repair tie rod. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. No. 31, 32)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 8 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV SHELL/2-SC1D-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 82.7%
Yes The examination was limited due to the proximity of the jet pump diffuser. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 33, 34) 2/1/RPV SHELL/2-SC2A-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 77.9%
Yes The examination was limited due to proximity of the jet pump riser brace, lower and upper specimen brackets. One previously identified indication (non-relevant) was identified during this examination.
(Enclosure 1 - Pg. Nos. 35, 36) 2/1/RPV SHELL/2-SC2B-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 85.7%
Yes The examination was limited due to proximity of the jet pump riser brace, lower and upper specimen brackets.. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 37, 38) 2/1/RPV SHELL/2-SC2C-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 87.7%
Yes The examination was limited due to proximity of the jet pump riser brace, lower and upper specimen brackets. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 39, 40) 2/1/RPV SHELL/2-SC3A-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 74.4%
Yes The examination was limited due to proximity of the feedwater sparger, core spray piping, and core spray pipe repair clamp. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 41, 42)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 9 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV SHELL/2-SC3B-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 71.1%
Yes The examination was limited due to proximity of the feedwater sparger and core spray piping. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 43, 44) 2/1/RPV SHELL/2-SC3C-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 75.0%
Yes The examination was limited due to proximity of the feedwater sparger and core spray piping bracket. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 45, 46) 2/1/RPV SHELL/2-SC3D-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 81.2%
Yes The examination was limited due to proximity of the feedwater sparger and core spray piping. Ten indications were detected during this examination. Eight of these indications were detected during the previous examination, and two additional indications were detected during this examination (attributed to differences in procedure recording criteria). The eight indications were compared to previous examination results, and no changes were observed. All indications were found to meet the acceptance standards.
(Enclosure 1 - Pg. Nos. 47, 48)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 10 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV SHELL/2-SC3E-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 73.7%
Yes The examination was limited due to proximity of the guide rod at 0° azimuth, feedwater sparger and core spray piping. Six indications were detected during this examination. Two of these indications were detected during the previous examination, and four additional indications were detected during this examination (attributed to differences in procedure recording criteria).
The two indications were compared to previous examination results, and no changes were observed. All indications were found to meet the acceptance standards.
(Enclosure 1 - Pg. Nos. 49, 50) 2/1/RPV SHELL/2-SC4C-VERT RPV Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D2R26 SA-302B to SA-302B Weld 6.25" Thickness 45/2.25/Shear 60/2.25/Long 85.0%
Yes The examination was limited due to proximity of a dryer support lug and the N13B nozzle. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 51, 52)
FW-1 (Weld 1) 2/1/1201-8/8-20-A Pipe-to-Valve Weld (RWCU)
IWB-2500-8(c) 1 R-A R1.20 D2R26 A-351-CF8M (valve) to SA-312-TP316L(Pipe) 8"/0.500" 45/5.0/Shear 60/5.0/Shear 70°/2.25/Shear 50%
Yes This examination was limited due to the valve configuration. No volumetric recordable indications were detected.
(Enclosure 1 - Pg. No. 62)
FW-2 (Weld 2) 2/1/1201-8/8-12-A Valve-to-Elbow Weld (RWCU)
IWB-2500-8(c) 1 R-A R1.20 D2R26 A-351 (valve) to A-403 or A-336, Gr. 304L (Pipe) 8"/0.500" 45/2.25/Shear 70°/2.25/Shear 48.2%
Yes This examination was limited due to the valve configuration and proximity to 1/2" sockolet fitting. No volumetric recordable indications were detected.
(Enclosure 1 - Pg. No. 63) 2/1/RPV SHELL/N3C-2 RPV-to-Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R27 SA-302B to SA-336 Weld 20"/6.25" 55°/1.0/Shear 70°/1.0/Shear 60°/2.0/Long 70.1%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 53, 54)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 11 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/1/RPV SHELL/N5A-2 RPV-to-Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R27 SA-302B to SA-336 Weld 14"/6.25" 55°/1.0/Shear 60°/2.0/Long 69.7%
Yes The examination was limited due to the nozzle configuration and the stabilizer bracket. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 55, 56) 2/1/RPV UPP HD/N18A-2 RPV Head-to-Nozzle Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R27 SA-302B to SA-336 Weld 6"/4.125" 55°/1.0/Shear 70°/1.0/Shear 60°/2.0/Long 88.0%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. Nos. 57, 58) 2/2/1302B-12/12-8 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D2R27 SA-182-F1 to SA-285-C Weld 12"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 58.55%
Yes The UT examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. No. 59) 2/2/1303A-8/8-9 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D2R27 SA-182-F1 to SA-285-C Weld 8"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 59.3%
Yes The UT examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. No. 60)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 12 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table A: Isolation Condenser (ISCO), Low Pressure Coolant Injection (LPCI), Reactor Water Cleanup (RWCU), and Reactor Pressure Vessel (RPV).
Table A: DNPS, Unit 2, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/
Thickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 2/2/1303B-8/8-8 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D2R27 SA-182-F1 to SA-285-C Weld 8"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 59.3%
Yes The UT examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 1 - Pg. No. 61)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 13 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/1/RPV SHELL/
N19B-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-336 to SA-302B Weld 10"/6.25" 55°/1.0/Shear 60°/3.0/Long 74.6%
Yes The examination was limited due to the nozzle configuration and support ring. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 2, 3) 3/1/RPV SHELL/N1A-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-336 to SA-302B Weld 28"/6.25" 60°/3.0/Long 70°/1.0/Shear 55°/1.0/Shear 70.0%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 4, 5) 3/1/RPV SHELL/N2D-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D2R23 SA-336 to SA-302B Weld 12"/6.25" 60°/3.0/Long 55°/1.0/Shear 80.9%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 6, 7) 3/1/RPV SHELL/
N2E-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R23 SA-336 to SA-302B Weld 12"/6.25" 60°/3.0/Long 55°/1.0/Shear 80.9%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 8, 9) 3/1/RPV SHELL/
N3C-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R23 SA-336 to SA-302B Weld 20"/6.25" 60°/3.0/Long 60°/1.0/Shear 70°/1.0/Shear 70.0%
Yes The examination was limited due to the nozzle configuration and thermocouples. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 10, 11) 3/1/RPV SHELL/
N5B-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R23 SA-336 to SA-302B Weld 14"/6.25" 60°/3.0/Long 55°/1.0/Shear 62.9%
Yes The examination was limited due to the nozzle configuration and stabilizer bracket. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 12, 13) 3/1/RPV SHELL/
N9-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R23 SA508-CL2 to SA-302B Weld 3"/6.25" 60°/3.0/Long 55°/1.0/Shear 73.0%
Yes The examination was limited due to the nozzle configuration and support ring. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 14, 15)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 14 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/1/RPV SHELL/M-1211D-1 (IWA)
Stabilizer Bracket Welded Attachment to Reactor Vessel (RPV)
IWB-2500-15 Surface (PT) 1 B-K B10.10 D3R24 SA-302B (RPV)
A-36 (Stabilizer Bracket) 3.5" Attachment Thickness N/A 60%
N/A The PT examination was limited to the top and two sides of the bracket (due to the bracket configuration), which resulted in 60% coverage of the required area. A supplemental VT-1 examination was performed on the bottom side which covered the remaining 40% of the required area. Two small, rounded indications were detected during the PT examination and were acceptable.
(Enclosure 2 - Pg. No. 16) 3/2/1302A-12/12-8 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D3R25 SA-182-F1 to SA-285-C Weld 12"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 28.25%
Yes The examination was limited due to the nozzle configuration.
The UT examination detected two subsurface flaws that exceeded the allowable flaw size. These flaws were previously detected during refueling outage D2R20.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 17, 18) 3/2/1302B-12/12-9 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D3R25 SA-182-F1 to SA-285-C Weld 12"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 28.25%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21 No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 19, 20)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 15 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/1/RPV UPP HD/N18A-2 Nozzle-to-Head Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-508-CL2 to SA-302B Weld 6"/4.125" 55°/1.0/Shear 60°/3.0/Long 70°/1.0/Shear 84.1%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 21, 22) 3/1/RPV UPP HD/N18B-2 Nozzle-to-Head Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-508-CL2 to SA-302B Weld 6"/4.125" 55°/1.0/Shear 60°/3.0/Long 70°/1.0/Shear 84.1%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 23, 24) 3/1/RPV SHELL/N2B-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-336 to SA-302B Weld 12"/6.25" 55°/1.0/Shear 60°/3.0/Long 76.0%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 25, 26) 3/1/RPV SHELL/N4A-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-336 to SA-302B Weld 12"/6.25" 55°/1.0/Shear 60°/3.0/Long 72.6%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 27, 28) 3/1/RPV SHELL/N4B-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-336 to SA-302B Weld 12"/6.25" 55°/1.0/Shear 60°/3.0/Long 72.6%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 29, 30) 3/1/RPV SHELL/N4C-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-336 to SA-302B Weld 12"/6.25" 55°/1.0/Shear 60°/3.0/Long 72.6%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 31, 32) 3/1/RPV SHELL/N4D-2 Nozzle-to-Shell Weld (RPV)
IWB-2500-7 Volumetric (UT) 1 B-D B3.90 D3R25 SA-336 to SA-302B Weld 12"/6.25" 55°/1.0/Shear 60°/3.0/Long 72.6%
Yes The examination was limited due to the nozzle configuration. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 33, 34)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 16 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/1/1302-14/14-9(A)
Flued Head-to-Pipe Weld (ISCO)
IWB-2500-8(c)
IWB-2500-9 IWB-2500-10 IWB-2500-11 Volumetric (UT) 1 R-A R1.20 D3R27 A212 Gr. B FBX (Flued Head)
SA-358 TP304 (Pipe) 14"/0.638" 45°/1.5/Shear 60°/1.5/Shear 60°/2.0/Long 50.0%
Yes This is a stainless steel weld. This is also a single sided exam due to the flued head configuration. The axially scans were unable to be performed on the flued head. Therefore, 50% maximum allowable coverage was claimed in accordance with the ASME Code.
One recordable indication was detected during the examination. This indication was attributed to ID geometry/corrosion resistant cladding and was acceptable.
(Enclosure 2 - Pg. Nos. 35, 36) 3/1/RPV SHELL/3-SC1B-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 42.3%
Yes The examination was limited due to the lower shroud repair. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 37-39) 3/1/RPV SHELL/3-SC2A-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 70.9%
Yes The examination was limited due to the design and location of the Tie Rod Support. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 40-42) 3/1/RPV SHELL/3-SC3A-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 23.5%
Yes The examination was limited due to the feedwater spargers and core spray piping. The lower portion of the weld was also limited due to clearances from the core spray lower sectional replacement hardware, and core spray downcomer proximity to the vessel wall. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 43, 44) 3/1/RPV SHELL/3-SC3B-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 67.9%
Yes The examination was limited due to the feedwater spargers, core spray piping, and core spray piping brackets. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 45, 46)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 17 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/1/RPV SHELL/3-SC3C-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 67.0%
Yes The examination was limited due to the feedwater spargers, core spray piping, and a specimen holder.
One recordable indication (acceptable) was detected during this examination.
(Enclosure 2 - Pg. Nos. 47 - 49) 3/1/RPV SHELL/3-SC3D-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 78.1%
Yes The examination was limited due to the feedwater spargers and core spray piping. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 50, 51) 3/1/RPV SHELL/3-SC4B-VERT Longitudinal Shell Weld (RPV)
IWB-2500-2 Volumetric (UT) 1 B-A B1.12 D3R27 SA-302B to SA-302B Weld 6.25" Thickness 45°/2.25/Shear 60°/2.25/Long 88.5%
Yes The examination was limited due to the dryer support lug. One recordable indication (acceptable) was detected during this examination.
(Enclosure 2 - Pg. Nos. 52, 53) 3/2/1303A-8/8-8 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D3R27 SA-285-C to SA-182-F1 Weld 8.0"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 70.0%
Yes The examination was limited due to the configuration of the shell to nozzle (single-sided exam). No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 54, 55)
ATTACHMENT Dresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I5R-22 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality (Page 18 of 18)
Note:
- 1. The following systems and their abbreviations are listed here for Table B: Isolation Condenser (ISCO), Reactor Feedwater (FW), and Reactor Pressure Vessel (RPV).
Table B: DNPS, Unit 3, List of Components with Limited Examination Coverage Component ID Weld Description (System)1 Exam Requirements (Figure No.)
and Method Class /
Exam Category /
Item Number Outage Examined Material of Construction Diameter/T hickness Exam Angle /
Frequency (MHz) / Mode Actual Coverage Appendix VIII Qualified Exam Remarks 3/2/1303B-8/8-9 Nozzle-to-Shell Weld (ISCO)
IWC-2500-4 Volumetric (UT) 2 C-B C2.21 D3R27 SA-285-C to SA-182-F1 Weld 8.0"/1.188" 45°/2.25/Shear 60°/2.25/Shear 70°/2.25/Shear 70.0%
Yes The examination was limited due to the configuration of the shell to nozzle (single-sided exam). No recordable indications were identified during this examination.
This weld was also received a surface examination (MT) of 100% of the required area in accordance with Examination Category C-B, Item C2.21. No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 56, 57) 3/2/3204B-18/18-1 Valve-to-Tee Weld (FW)
IWB-2500-8(c)
Volumetric (UT) 1 R-A R1.11 D3R27 SA-216-WCB (Valve)
SA-234-WPB (Tee) 18.0"/1.375" 45°/2.25/Shear 78.95%
Yes The examination was limited due to the valve configuration (saddle weld). No recordable indications were identified during this examination.
(Enclosure 2 - Pg. Nos. 58-61)
ENCLOSURE 1 Dresden Nuclear Power Station, Unit 2 10CFR50.55a Relief Request I5R-22 Additional Details and Supporting Information
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 1 of 62)
Weld 2/1/RPV Shell/N1A-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 2 of 62)
Weld 2/1/RPV Shell/N1A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 3 of 62)
Weld 2/1/RPV Shell/N1B-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 4 of 62)
Weld 2/1/RPV Shell/N1B-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 5 of 62)
Weld 2/1/RPV Shell/N2C-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 6 of 62)
Weld 2/1/RPV Shell/N2C-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 7 of 62)
Weld 2/1/RPV Shell/N2F-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 8 of 62)
Weld 2/1/RPV Shell/N2F-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 9 of 62)
Weld 2/1/RPV Shell/N2H-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 10 of 62)
Weld 2/1/RPV Shell/N2H-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 11 of 62)
Weld 2/1/RPV Shell/N5B-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 12 of 62)
Weld 2/1/RPV Shell/N5B-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 13 of 62)
Integral Welded Attachment 2/1/1506-16/M-1164D-296(IWA)
Note: Surface conditioning performed to reduce the size of rounded indications. Reexamination results were acceptable.
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 14 of 62)
Integral Welded Attachment 2/1/RPV SHELL/M-1175D-1(IWA)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 15 of 62)
Weld 2/1/RPV SHELL/N19A-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 16 of 62)
Weld 2/1/RPV SHELL/N19A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 17 of 62)
Weld 2/1/RPV SHELL/N19A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 18 of 62)
Weld 2/1/RPV SHELL/N4A-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 19 of 62)
Weld 2/1/RPV SHELL/N4A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 20 of 62) 2/1/RPV SHELL/N4B-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 21 of 62) 2/1/RPV SHELL/N4B-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 22 of 62) 2/1/RPV SHELL/N4C-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 23 of 62) 2/1/RPV SHELL/N4C-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 24 of 62) 2/1/RPV SHELL/N4D-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 25 of 62) 2/1/RPV SHELL/N4D-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 26 of 62) 2/1/RPV SHELL/2SC1A-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 27 of 62) 2/1/RPV SHELL/2SC1A-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 28 of 62) 2/1/RPV SHELL/2-SC1B-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 29 of 62) 2/1/RPV SHELL/2-SC1B-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 30 of 62) 2/1/RPV SHELL/2-SC1C-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 31 of 62) 2/1/RPV SHELL/2-SC1C-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 32 of 62) 2/1/RPV SHELL/2-SC1D-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 33 of 62) 2/1/RPV SHELL/2-SC1D-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 34 of 62) 2/1/RPV SHELL/2-SC2A-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 35 of 62) 2/1/RPV SHELL/2-SC2A-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 36 of 62) 2/1/RPV SHELL/2-SC2B-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 37 of 62) 2/1/RPV SHELL/2-SC2B-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 38 of 62) 2/1/RPV SHELL/2-SC2C-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 39 of 62) 2/1/RPV SHELL/2-SC2C-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 40 of 62) 2/1/RPV SHELL/2-SC3A-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 41 of 62) 2/1/RPV SHELL/2-SC3A-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 42 of 62) 2/1/RPV SHELL/2-SC3B-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 43 of 62) 2/1/RPV SHELL/2-SC3B-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 44 of 62) 2/1/RPV SHELL/2-SC3C-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 45 of 62) 2/1/RPV SHELL/2-SC3C-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 46 of 62) 2/1/RPV SHELL/2-SC3D-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 47 of 62) 2/1/RPV SHELL/2-SC3D-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 48 of 62) 2/1/RPV SHELL/2-SC3E-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 49 of 62) 2/1/RPV SHELL/2-SC3E-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 50 of 62) 2/1/RPV SHELL/2-SC4C-VERT
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 51 of 62) 2/1/RPV SHELL/2-SC4C-VERT (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 52 of 62) 2/1/RPV SHELL/N3C-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 53 of 62) 2/1/RPV SHELL/N3C-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 54 of 62) 2/1/RPV SHELL/N5A-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 55 of 62) 2/1/RPV SHELL/N5A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 56 of 62) 2/1/RPV UPP HD/N18A-2
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 57 of 62) 2/1/RPV UPP HD/N18A-2 (Contd)
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 58 of 62) 2/2/1302B-12/12-8
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 59 of 62) 2/2/1303A-8/8-9
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 60 of 62) 2/2/1303B-8/8-8
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 61 of 62) 2/1/1201-8/8-20-A
ENCLOSURE 1 Dresden Generating Station, Unit 2 10CFR50.55a Relief Request I5R-22 (Page 62 of 62) 2/1/1201-8/8-12-A
ENCLOSURE 2 Dresden Nuclear Power Station, Unit 3 10CFR50.55a Relief Request I5R-22 Additional Details and Supporting Information
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 1 of 61) 3/1/RPV SHELL/ N19B-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 2 of 61) 3/1/RPV SHELL/ N19B-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 3 of 61) 3/1/RPV SHELL/N1A-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 4 of 61) 3/1/RPV SHELL/N1A-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 5 of 61) 3/1/RPV SHELL/N2D-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 6 of 61) 3/1/RPV SHELL/N2D-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 7 of 61) 3/1/RPV SHELL/ N2E-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 8 of 61) 3/1/RPV SHELL/ N2E-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 9 of 61) 3/1/RPV SHELL/ N3C-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 10 of 61) 3/1/RPV SHELL/ N3C-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 11 of 61) 3/1/RPV SHELL/ N5B-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 12 of 61) 3/1/RPV SHELL/ N5B-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 13 of 61) 3/1/RPV SHELL/ N9-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 14 of 61) 3/1/RPV SHELL/ N9-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 15 of 61) 3/1/RPV SHELL/M-1211D-1 (IWA)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 16 of 61) 3/2/1302A-12/12-8
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 17 of 61) 3/2/1302A-12/12-8 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 18 of 61) 3/2/1302B-12/12-9
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 19 of 61) 3/2/1302B-12/12-9 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 20 of 61) 3/1/RPV UPP HD/N18A-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 21 of 61) 3/1/RPV UPP HD/N18A-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 22 of 61)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 23 of 61) 3/1/RPV UPP HD/N18B-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 24 of 61) 3/1/RPV UPP HD/N18B-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 25 of 61) 3/1/RPV SHELL/N2B-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 26 of 61) 3/1/RPV SHELL/N2B-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 27 of 61) 3/1/RPV SHELL/N4A-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 28 of 61) 3/1/RPV SHELL/N4A-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 29 of 61) 3/1/RPV SHELL/N4B-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 30 of 61) 3/1/RPV SHELL/N4B-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 31 of 61) 3/1/RPV SHELL/N4C-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 32 of 61) 3/1/RPV SHELL/N4C-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 33 of 61) 3/1/RPV SHELL/N4D-2
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 34 of 61) 3/1/RPV SHELL/N4D-2 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 35 of 61) 3/1/1302-14/14-9(A)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 36 of 61) 3/1/1302-14/14-9(A) (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 37 of 61) 3/1/RPV SHELL/3-SC1B-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 38 of 61) 3/1/RPV SHELL/3-SC1B-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 39 of 61) 3/1/RPV SHELL/3-SC1B-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 40 of 61) 3/1/RPV SHELL/3-SC2A-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 41 of 61) 3/1/RPV SHELL/3-SC2A-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 42 of 61) 3/1/RPV SHELL/3-SC2A-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 43 of 61) 3/1/RPV SHELL/3-SC3A-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 44 of 61) 3/1/RPV SHELL/3-SC3A-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 45 of 61) 3/1/RPV SHELL/3-SC3B-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 46 of 61) 3/1/RPV SHELL/3-SC3B-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 47 of 61) 3/1/RPV SHELL/3-SC3C-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 48 of 61) 3/1/RPV SHELL/3-SC3C-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 49 of 61) 3/1/RPV SHELL/3-SC3C-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 50 of 61) 3/1/RPV SHELL/3-SC3D-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 51 of 61) 3/1/RPV SHELL/3-SC3D-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 52 of 61) 3/1/RPV SHELL/3-SC4B-VERT
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 53 of 61) 3/1/RPV SHELL/3-SC4B-VERT (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 54 of 61) 3/2/1303A-8/8-8
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 55 of 61) 3/2/1303A-8/8-8 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 56 of 61) 3/2/1303B-8/8-9
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 57 of 61) 3/2/1303B-8/8-9 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 58 of 61) 3/2/3204B-18/18-1
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 59 of 61) 3/2/3204B-18/18-1 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 60 of 61) 3/2/3204B-18/18-1 (Contd)
ENCLOSURE 2 Dresden Generating Station, Unit 3 10CFR50.55a Relief Request I5R-22 (Page 61 of 61) 3/2/3204B-18/18-1 (Contd)