ML21266A426
| ML21266A426 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/23/2021 |
| From: | Georgeson C South Texas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NOC-AE-21003841, STI:35216096 | |
| Download: ML21266A426 (58) | |
Text
Nuclear Operating Company South Texas Pm'iect Electric Generating Station P.O. Box 289 Wadsworlh. Texas 77483 September 23, 2021 NOC-AE-21003841 STI:35216096 10CFR50.55a Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)
Pursuant to 10 CFR 50.55a(g)(5)(iii), STP Nuclear Operating Company (STPNOC) hereby requests NRC approval of the following request for the third ten-year inspection interval: relief from American Society of Mechanical Engineers (ASME) Section Xl requirements for weld examination on the basis of impracticality. ASME Section Xl Tables IWB-2500-1 and IWC-2500-1 require inservice inspection of Class 1 and Class 2 component welds by nondestructive examination. 100%
examination coverage of these welds during the third ten-year inspection interval was impractical because of component configuration and geometry, and because of the limitations of the examination equipment and techniques used to perform these examinations.
The attached discussion includes a list of the affected welds for which relief is requested, the amount of coverage obtained, and the basis and justification for their acceptability. STPNOC requests NRC review and approval of this request by September 23, 2022.
There are no commitments in this letter.
If there are any questions regarding this matter, please contact Zachary Dibbern at (361) 972-4336 or me at (361) 972-7806.
///*
Christopher Georgeson General Manager, Engineering
Enclosure:
STP Electric Generating Station Units 1 and 2 ASME Section Xl 10 CFR 50.55a Request for Relief Number RR-ENG-3-25
NOC-AE-21003841 Page 2 of 2 cc:
(paper copy)
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511
NOC-AE-21003841 Enclosure Enclosure STP Electric Generating Station Units 1 and 2 ASME Section XI 10 CFR 50.55a Request for Relief Number RR-ENG-3-25
Enclosure South Texas Project Electric Generating Station Units 1 and 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number RR-ENG-3-25 In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
Page 1 of 55 I.
ASME Code Component(s) Affected The South Texas Project Electric Generating Station (STPEGS), Units 1 and 2, Class 1 and 2 welds with limited examinations that are included in this request for relief are for the Third Ten-Year Inservice Inspection Interval. The content of this request includes the insights gained from guidance provided in References 1 and 2, and the following Code Classes, Examination Categories, and Item Numbers apply.
Code Classes:
1 and 2 Examination Categories:
B-B, B-D, C-G, and R-A Item Numbers:
B2.12, B2.40, B3.110, C1.30, C6.10, R1.11. and R2.20 II.
Applicable Code Edition and Addenda
The applicable ASME Boiler and Pressure Vessel Code of Record (Code) edition and addenda was ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2004 Edition (Reference 3), and was used for the Third 10-Year Inservice Inspection (ISI) Interval at STP as modified by 10 CFR 50.55a. The Appendix VIII requirements and use of the Performance Demonstration Initiative (PDI) requirements at STP were in accordance with the 2001 Edition of Section XI, Reference 4 for the limited examinations contained in this request as conditioned by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xxiv).
The STP Third 10-Year ISI Interval ended on September 24, 2020 for Units 1 and 21; all the limited examinations contained in this request are required to be submitted to the NRC on or before 12 months after this date.
1 Unit 2 was originally scheduled to end on October 18, 2020; however the interval was reduced by 24 days to align both units ISI Fourth Interval.
Page 2 of 55 III. Applicable Code Requirements Exam Cat.
Item No.
Class 1 Weld Examination Coverage Requirements B-B B2.12 To include essentially 100% of the examination volume of one foot of one of the Pressurizer Longitudinal Head Welds per head as depicted in the applicable figure shown in Figure IWB-2500-2.
B-B B2.40 To include essentially 100% of the examination volume of the Tubesheet-To-Head Weld as depicted in applicable figure shown in Figure IWB-2500-6.
B-D B3.110 To include essentially 100% of the examination volume of the Pressurizer Nozzle-to-Vessel Welds as depicted in the applicable figure shown in Figures IWB-2500-7(a), (b), (c), or (d)
Exam Cat.
Item No.
Class 2 Weld Examination Coverage Requirements C-G C6.10 To include the surface area of the weld as depicted in Figure IWC-2500-8.
Exam Cat.
Item No.
Class 1 and 2 Piping Welds / Risk-Informed Inservice Inspection Program Coverage Requirements R-A R1.11 To include essentially 100% of the examination location potentially subject to thermal fatigue.
R-A R1.20 To include essentially 100% of the examination location not subject to a degradation mechanism.
As previously defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), now removed, and ASME Code Case N-460, Reference 5, as approved in Regulatory Guide 1.147, Revision 19, Reference 6, this Code Case was invoked for the required coverage associated with the welds in this request and states that essentially 100% equates to more than 90% of the examination volume or required surface area of each weld where the reduction in coverage is due to interference by another component or part geometry.
Limited Class 1 Welds Table IWB-2500-1, Examination Category B-B, Pressure Retaining Welds in Vessels Other Than the Reactor Vessels - Inspection Program B, Item Nos.:
B2.12 limitations applied to the Shell F Longitudinal Weld (Unit 2 PRZ-2-L6)
B2.40 limitations applied to the Channel Head-To-Tubeplate (Unit 1 RSG-1A-T1 and Unit 2 RSG-2A-T1)
Page 3 of 55 Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels -
Inspection Program B, Item No.:
B3.110 limitations applied to a pressurizer nozzle-to-vessel weld (Unit 2 PRZ-2-N3 Safety Nozzle to Head).
Limited Class 2 Welds Table IWC-2500-1, Examination Category C-G Pressure Retaining Welds in Pumps and Valves, Item No:
C6.10, limitations applied to the Containment Spray Pump 2A, weld CIAPCS-2A-PCW1.
The limitation was due to the accessibility through the concrete opening.
Limited Class 1 and 2 Piping Welds / Risk-Informed Inservice Inspection Programs Class 1 and 2 piping welds selected for examination during the third interval under the Risk-Informed Inservice Inspection (RI-ISI) Programs used for STP were examined in accordance with Relief Request RR-ENG-3-4 (Reference 7) and included the piping welds selected for examination under Examination Category R-A. The use of this relief request for STP was based on EPRI Report TR-112657 Rev. B-A Revised Risk-Informed Inservice Inspection Evaluation Procedure Reference 8.
Additional Examination Volume Requirements per EPRI Report TR-112657 - The Section Titled Examination Method (4.1 Thermal Fatigue) states In contrast to mechanical fatigue, thermal fatigue cracking usually initiates as many small cracks and then one of the cracks becomes predominant. It has been most commonly observed at or near the pipe-to-nozzle weld where the wall thickness is thinner due to a counterbore or previous grinding on the inside surface.
Figure 4-2 Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger specifies the length of the examination volume shall be enough distance [approximately 1/4 in.] to include each side of the base metal thickness transition or counterbore transition.
IV.
Reason for Request
10 CFR 50.55a(g)(5)(iii), states: ISI program update: Notification of impractical ISI Code requirements.
If the licensee has determined that conformance with a Code requirement is impractical for its facility the licensee must notify the NRC and submit, as specified in § 50.4, information to support the determinations.
Determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the Code requirements during the inservice inspection interval for which the request is being submitted. Requests for relief made in
Page 4 of 55 accordance with this section must be submitted to the NRC no later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought.
Pursuant to 10 CFR 50.55a(g)(5)(iii) above, the required submittal of this request for relief is due before September 24, 2021 because STP has determined that compliance with the code requirements of achieving essentially 100% coverage of the welds listed in this request is impractical to achieve. This request is based on actual demonstrated limitations experienced when attempting to comply with the code requirements in the performance of the examinations listed in this request.
V.
Impracticality of Compliance The construction permits for STP Unit 1 and 2 were issued on December 22, 1975 and falls under the provisions of 10 CFR 50.55a(g)(2)(ii), which were applied to components that are classified as ASME BPV Code Class 1, Class 2, and Class 3 and supports for components that are classified as ASME BPV Code Class 1, Class 2, and Class 3 must be designed and provided with the access necessary to perform the required preservice and inservice examinations set forth in editions and addenda of Section III or Section XI of the ASME BPV Code incorporated by reference in paragraph (a)(1) of this section (or the optional ASME BPV Code Cases listed in NRC Regulatory Guide 1.147, as incorporated by reference in paragraph (a)(3)(ii) of this section) applied to the construction of the particular component. Therefore, although the design of the plants has provided access for examinations to the extent practical, component design configurations with conditions resulting in examination limitations such as those from support interference, geometric configurations of welds and materials such as fittings or valve bodies made of cast stainless steel may not allow the full required examination volume or surface area coverage with the latest techniques available and thus this request for relief addresses those conditions. A typical example of such a condition is a valve-to-pipe weld where essentially 100% of the code required volume cannot be examined from the valve side of the weld and where a plant modification would be needed to provide this coverage. Details of examination restrictions and reductions in required examination coverage are provided in.
When examined, the welds listed in Attachment 1 of this request did not receive the required code volume or surface area coverage due to their component design configurations or interference by other items. These conditions resulted in scanning or surface area access limitations that prohibited obtaining essentially 100% examination coverage of the required examination volumes or surface areas, but when this situation occurred 100% of the accessible volumes or surface areas of each weld was covered.
Burden Caused by Compliance To comply with the code required examination volumes or surface areas for obtaining essentially 100% coverage for the welds listed in this request for relief, the welds and their
Page 5 of 55 associated components would have to be physically modified and/or disassembled beyond their current design. Overall, components and fittings associated with the welds listed in this request are constructed of standard design items and materials meeting typical national standards that specify required configurations and dimensions. To replace these items with items of alternate configurations or materials to enhance examination coverage would require unique redesign and fabrication. Because these items are in the Class 1 and 2 boundaries and for the Class 1 items that form a part of the reactor coolant pressure boundary, their redesign and fabrication would be an extensive effort based on the limitations that exist.
For the Class 1, Examination Category B-B, Item No. B2.12, Unit 2 Shell F Longitudinal Seam Weld PRZ-2-L6, limitation was caused due to the permanent insulation support ring.
For the Class 1, Examination Category B-B, Item No. B2.40, Unit 1 Channel Head to Tubeplate Weld and Unit 2 Channel Head to Tubeplate Weld RSG-2A-T1, limitations were caused due to ring support.
For the Class 1, Examination Category B-D, Item No. B3.110, Unit 2 Safety Nozzle to Shell Weld PRZ-2-N3, limitation was caused by the configuration of the nozzle. The examination was performed from the vessel OD and the examination could not be performed from the vessel side. To obtain the required coverage for this weld would require a design modification.
For the Class 2 Examination Category C-G, Item No.: C6.10 Containment Spray Pump 2A, Weld CIAPCS-2A-PCW1, limitation was due to the accessibility through the concrete opening For the Class 1 piping welds examined per the RI-ISI Programs, the limitations listed in this request are typically limited by their design configurations or materials. The configurations of these welds or their materials only allow UT examination coverage from one side of the weld or limited coverage from a specific area or areas of one side of the weld and thus they would also require a design modification or replacement to obtain the required examination coverage.
Overall, it is not possible to obtain UT interrogation of greater than 90% of the required code examination volume or surface areas for the welds in this request without extensive weld or component design modifications. Examinations have been performed to the maximum extent possible and radiography is impractical due to the amount of work being performed in the areas on a 24-hour basis when the welds are available for examination. Using radiography would result in numerous work-related stoppages and increased exposure due to the shutdown and startup of other work in the areas. The water may need to be drained from systems or components where radiography is performed, which increases the radiation dose rates over a much broader area than the weld being examined. There is significant impracticality associated with the performance of weld or area modifications or the use of radiography in order to increase the examination coverage.
Page 6 of 55 VI.
Proposed Alternative and Basis for Use Proposed Alternative
- 1) Periodic system pressure tests and VT-2 visual examinations will continue to be performed in accordance with ASME Section Xl, Examination Category B-P, for Class 1 pressure retaining welds and items each refueling outage and Examination Category C-H for Class 2 pressure retaining welds and items each inspection period of Table IWB-2500-1 and Table IWC-2500-1, respectively.
- 2) Conduct required PT, MT or UT examinations to the maximum extent possible as required by ASME Section XI or the RI-ISI Programs.
Basis for Use 10 CFR 50.55a(g)(4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements set forth in the ASME Code to the extent practical within the limitations of design, geometry and materials of construction of the welds and items described in Attachment 1.
When a component is found to have conditions which limit the required examination volume or surface area, STP is required to submit this information to the enforcement and regulatory authorities having jurisdiction at the plant site. This request for relief has been written to address areas where these types of conditions exist and where the required amount of coverage was reduced below the minimum acceptable. STP has performed the weld examinations listed in this request to the maximum extent possible for each of the welds identified with limitations in Attachment 1.
The Class 1 Examination Categories B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels and B-D, Full Penetration Welded Nozzles In Vessels and the Class 1 Risk-Informed Piping Welds within the scope of this request are all located inside the containment.
Even though their examination did not meet the essentially 100% code required volume coverage requirement, there is instrumentation in place to assure that early detection of any Reactor Coolant System (RCS) pressure boundary leakage is identified. This is accomplished by the leakage detection instrumentation inside the containment where the RCS leakage detection instrumentation is controlled by the units Technical Specifications. These instruments are used to quantify any unidentified leakage from the RCS and to meet the STP Technical Specifications Surveillance Requirements that have a Limiting Condition for Operation (LCO) in 3/4.4.6.
EPRI Report TR-112657 Rev. B-A Revised Risk-Informed Inservice Inspection Evaluation Procedure, Section 6.4 addresses relief requests pertaining to limited examination coverage.
The following requirements are to be met:
Page 7 of 55
- 1. An existing relief request is no longer required if the piping element is not a RI-ISI selection. Such relief requests shall be formally withdrawn by the licensee.
The welds included in this relief request do not have an existing relief request.
- 2. An existing relief request is unaffected if the piping element is a RI-ISI selection and the examination volume remains unchanged.
The welds included in the relief request do not have an existing relief request.
- 3. An existing relief request may require modification if the piping element is a RI-ISI selection and the examination volume has been expanded (e.g. thermal fatigue).
The welds included in the relief request do not have an existing relief request.
- 4. A new relief request will be generated for any RI-ISI piping element selection for which greater than 90 percent examination coverage is not achieved.
EPRI Report TR-112657 Rev. B-A states: It should be noted that is an existing ASME Section XI inspection location is partially examined and continues to be partially examined in the RI-ISI process, the amount of risk addressed by examination remains the same for that location. If a new RI-ISI inspection location is only partially examined, but was not previously required to be examined by Section XI, then the amount of risk addressed by examination of that location is still increased. It is not necessarily true that because you reduce examination totals, that a complete examination must be performed at the RI-ISI selected locations to maintain risk neutrality or improvement in the program.
The impact of partial examinations on the overall risk contribution may be assessed and included in the basis for relief.
Evaluation of RI-ISI Limited Examinations STP has reviewed each instance of limited examination coverage and taken the appropriate steps consistent with its impact on the basis of the EPRI Report TR-112657 Rev. B-A on risk.
Acceptance of limited examinations or volumes shall not invalidate the results of the change-in-risk evaluation. Areas with acceptable limited examination and their bases, shall be documented. The change in risk acceptance criteria is 1E-7/1E-8 CDF/LERF at the system level and 1E-6/1E-7 total CDF/LERF for all systems. The With POD Credit column is the official result that must meet these criteria. The values represent delta risk, the calculated difference in CDF/LERF that STP incurs due to using a risk-informed ISI versus a conventional Section XI inspection scope. Therefore, the requirement is that the delta-risk is less than the acceptance criteria, meaning a positive number is ok if it is less than 1E-7 (for example) and any negative number is ok.
Below is a summary of the cumulative effect of the limited examinations.
Page 8 of 55 UNIT 1 This Request identifies three Unit 1 piping welds with limited examination coverage (90%
or less). Welds (4-CV-1120-BB1, Weld 2, 8-RH-1106-KB2, Weld 13, and 8-RH-1107-BB2, Weld 1) are addressed below, by system.
o Chemical and Volume Control (CVC) (Weld 4-CV-1120-BB1, Weld 2)
To conservatively quantify the effect on delta risk for Weld 2, the delta risk is adjusted by not crediting this CVC weld with limited examination coverage. The below table provides the delta risk with Weld 2 credited and with Weld 2 not credited. The columns under heading Examined are the delta risk with the weld included, the columns under heading Not Examined is the adjusted delta risk after removing the weld. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of this CVC weld is acceptable.
CVC CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-8.94E-10
-8.94E-11 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined 6.00E-12 6.00E-13 Adjusted delta risk using the periodic update delta risk
Page 9 of 55 o Residual Heat Removal (RH) (Weld 8-RH-1106-KB2, Weld 13 and 8-RH-1107-BB2, Weld 1)
To conservatively quantify the effect on delta risk for the two RH welds, the delta risk is adjusted by not crediting the two RH welds with limited examination coverage. The below table provides the delta risk with the two RH welds credited and with the two RH welds not credited. The columns under heading Examined are the delta risk with the welds included, the columns under heading Not Examined is the adjusted delta risk after removing the welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of these RH welds are acceptable.
RH CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-6.52E-10
-6.52E-11 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined 2.45E-09 2.45E-10 Adjusted delta risk using the periodic update delta risk o Cumulative Effect to Delta Risk for the One CVC Weld and Two RH Welds The impact of the limited examination on the delta risk for the individual system is addressed above. The cumulative effect on the total delta risk is provided below.
The columns under heading Examined are the delta risk with the three welds included, the columns under heading Not Examined is the adjusted delta risk after removing the three welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-06 for CDF and 1E-07 for LERF. Therefore, a limited examination of the one CV Weld and two RH Welds is acceptable.
Total CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-3.08E-06
-2.28E-09 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined
-3.07E-06
-1.85E-9 Adjusted delta risk using the periodic update delta risk
Page 10 of 55 UNIT 2 This Request identifies four Unit 2 piping welds with limited examination coverage (90%
or less). Welds (4-CV-2120-BB1, Weld 2, 8-RH-2106-KB2, Weld 13, 8-RH-2107-BB2 Weld 1, and 4-RC-2422-BB1, Weld 24) are addressed below, by system.
o Chemical and Volume Control (CVC) (Weld 4-CV-2120-BB1, Weld 2)
To conservatively quantify the effect on delta risk for Weld 2, the delta risk is adjusted by not crediting this CVC weld with limited examination coverage. The below table provides the delta risk with Weld 2 credited and with Weld 2 not credited. The columns under heading Examined are the delta risk with the weld included, the columns under heading Not Examined is the adjusted delta risk after removing the weld. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of this CVC weld is acceptable.
CVC CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-8.94E-10
-8.94E-11 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined 6.00E-12 6.00E-13 Adjusted delta risk using the periodic update delta risk o Residual Heat Removal (RH) (Weld 8-RH-2106-KB2, Weld 13 and 8-RH-2107-BB2, Weld 1)
To conservatively quantify the effect on delta risk for the two RH welds, the delta risk is adjusted by not crediting the two RH welds with limited examination coverage. The below table provides the delta risk with the two RH welds credited and with the two RH welds not credited. The columns under heading Examined are the delta risk with the welds included, the columns under heading Not Examined is the adjusted delta risk after removing the welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of these RH welds are acceptable.
RH CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined 6.52E-10 6.52E-11 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined 2.45E-9 2.45E-10 Adjusted delta risk using the periodic update delta risk
Page 11 of 55 o Reactor Coolant (RC) (Weld 4-RC-2422-BB1, Weld 24)
To conservatively quantify the effect on delta risk for Weld 24, the delta risk is adjusted by not crediting this RC weld with limited examination coverage. The below table provides the delta risk with Weld 24 credited and with Weld 24 not credited. The columns under heading Examined are the delta risk with the weld included, the columns under heading Not Examined is the adjusted delta risk after removing the weld. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for CDF and 1E-08 for LERF. Therefore, a limited examination of this CVC weld is acceptable.
RC CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-3.07E-06
-1.62E-09 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined
-3.06E-06
-1.62E-09 Adjusted delta risk using the periodic update delta risk o Cumulative Effect to Delta Risk for the One CVC Weld, Two RH Welds, and One RC weld.
The impact of the limited examination on the delta risk for the individual system is addressed above. The cumulative effect on the total delta risk is provided below.
The columns under heading Examined are the delta risk with the four welds included, the columns under heading Not Examined is the adjusted delta risk after removing the four welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-06 for CDF and 1E-07 for LERF. Therefore, a limited examination of the one CVC Weld, two RH Welds and one RC Weld is acceptable.
Total CDF Impact LERF Impact Source of Delta Risk w/ POD w/ POD Examined
-3.08E-06
-2.28E-09 Latest interval periodic update required by EPRI Report 112657 Rev. B-A Not Examined
-3.06E-06
-1.85E-09 Adjusted delta risk using the periodic update delta risk VII. Duration of Proposed Alternative This request for relief is for the STP, Units 1 and 2, Third 10-Year ISI Intervals, which began on September 25, 2010 for Unit 1 and October 19, 2010 for Unit 2. Both Units Third 10-Year ISI Intervals ended on September 24, 2020.
Page 12 of 55 VIII.
Precedents Note: Industry requests for relief due to impracticality associated with limited weld examinations are common and are filed by all licensees. Some of the more recent NRC approvals of requested relief that are aligned with Reference 1 are:
(1) Millstone Power Station, Unit No. 2 - Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0024, EPID L-2020-LLR-0025, and EPID L-2020-LLR-0026) (Accession No. ML20312A001) dated December 10, 2020.
(2) Millstone Power Station, Unit No. 3 - Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-202-LLR-0027 through EPID L-202-LLR-0032) (Accession No. ML20312A002) dated December 10, 2020.
(3) Perry Nuclear Power Plant, Unit No. 1 - Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval (EPID L-2020-LLR-0067) (Accession No. Ml20252A026) dated September 18, 2020.
(4) Nine Mile Point Nuclear Station, Unit 2 - Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID-L-2019-LLR-0099) (Accession No. ML2014141L053) dated June 2, 2020 (5) Beaver Valley Power Station, Unit 2 - Relief Request 2-TYP-3-B3.110-1, 2-TYP C2.21-1, 2-TYP-3-C1.30-1, and 2-TYP-3-RA-1 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval (EPID L-2019-LLR-0082) (Accession No. ML20080J78)
(6) Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Relief Request RE:
Limited Examination Coverage During Fourth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0103) (Accession No. ML20097D644) dated April 14, 2020.
(7) Beaver Valley Power Station, Unit No. 1 - Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval (EPID L-2019-LLR-0083) (Accession No. ML20079F816) dated March 26, 2020.
IX References
- 1.
NRC presentation Coverage Relief Requests, Industry/NRC NDE Technical Information Exchange Public Meeting January 13-15, 2015, [ADAMS Accession No.: ML15013A266].
- 2.
NRC presentation Coverage Relief Request Update, 2020 Industry/NRC NDE Technical Information Exchange Public Meeting. [ADAMS Accession No.: ML20009E155)
- 3.
ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2004 Edition.
- 4.
ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems, 2001 Edition.
Page 13 of 55
- 5.
ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 WeldsSection XI, Division 1.
- 6.
NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 19, Dated October 2019. [ADAMS Accession No.:
ML19128A244]
- 7.
Relief Request RR-ENG-3-4 Request for Relief to apply an alternative to the ASME Section XI Code Requirements for Examination of Class 1 and Class 2 Piping Welds
- 8.
EPRI Report TR-112657 Rev. B-A Revised Risk-Informed Inservice Inspection Evaluation Procedure
Page 14 of 55 South Texas Project Electric Generating Station Units 1 and 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number RR-ENG-3-25 In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
Introduction This attachment contains figures and tables as applicable that are used to depict the limitations and calculations used for obtained coverage, materials and product forms, with ultrasonic examination angles and wave modes used, any limited surface examinations and the examination results for the welds associated with this request for relief, including any applicable previous examination history used. The following Table 1 for STP identifies the welds within the scope of this request and summarizes the extent of examination coverage achieved for each weld.
Many of the welds listed were examined with different STP approved procedures and techniques during the span of the Third 10-Year ISI Interval and therefore not all the coverage calculations used are identical, but they are based on the actual NDE data reports that were provided for the examinations completed.
Page 15 of 55 Table 1 - STP Units 1 and 2 Welds with Limitations, 3rd Interval Unit No./
Weld Identification Number/
Seq. Number
- Class, Category and Item No.
Weld Description Material 1 and Product Form Material 2 and Product Form Examination Code Coverage Obtained2 Examination Limitations and Results Normal Operating Conditions (Pressure/Temperature)
Applicable Tables and Figures Unit 1 RSG-1A-T1 1.1 1
B-B B2.40 Steam Generator Channel Head-to-Tubeplate Weld SA-508 Class 3a with SS Clad SA-508 Class 3a with SS Clad 75.3%
Limitation due to ring support 2250psi/625°F Figures 1.1-1, 1.1-2, 1.1-3, 1.1-4, 1.1-5, and 1.1-6 Unit 1 4-CV-1120-BB1 Weld 2 1.2 1
R-A R1.11 Chemical Volume and Control Pipe to Valve Weld SA-376 SA-182 Type F316 or SA-351 Gr. CF8 or CF8M 50% single sided examination Limitation due to Valve Configuration 2300psi/530°F Table 1.2-1, Figures 1.2-1, and 1.2-2 Unit 1 8-RH-1106-KB2 Weld 13 1.3 2
R-A R1.11 Residual Heat Removal Pipe to Valve Weld SA-376 SA-182 Type F316 37.5% single sided examination Limitation due to Valve Configuration 411psi/296°F Figures 1.3-1, 1.3-2, 1.3-3, 1.3-4, 1.3-5, and 1.3-6 Unit 1 8-RH-1107-BB2 Weld 1 1.4 2
R-A R1.11 Residual Heat Removal Valve to Pipe Weld SA-182 Type F316 SA-376 37.5% single sided examination Limitation due to Valve Configuration 367psi/296°F Figures 1.4-1, 1.4-2, 1.4-3, 1.4-4, 1.4-5, and 1.4-6 Unit 2 PRZ-2-N3 2.1 1
B-D B3.110 Pressurizer Relief Nozzle to Shell Weld SA-508 Class 2A SA-533 Gr. A Class 2 73.63%
Limitation due to nozzle weld configuration 2250psi/653°F Table 2.1-1, Figures 2.1-1 and 2.1-2 Unit 2 PRZ-2-L6 2.2 1
B-B B2.12 Pressurizer Shell F Longitudinal Seam Weld SA-533 Gr. A Class 2 SA-533 Gr. A Class 2 85%
Limitation due to permanent insulation support ring 2250psi/653°F Table 2.2-1, Figures 2.2-1, 2.2-2, 2.2-3, and 2.2-4 Unit 2 RSG-2A-T1 2.3 1
B-B B2.40 Steam Generator Channel Head-to-Tubeplate Weld SA-508 Class 3a with SS Clad SA-508 Class 3a with SS Clad 88%
Limitation due to ring support 2250psi/625°F Figures 2.3-1, 2.3-2, 2.3-3, 2.3-4, 2.3-5, and 2.3-6
Page 16 of 55 Table 1 - STP Units 1 and 2 Welds with Limitations, 3rd Interval Unit No./
Weld Identification Number/
Seq. Number
- Class, Category and Item No.
Weld Description Material 1 and Product Form Material 2 and Product Form Examination Code Coverage Obtained2 Examination Limitations and Results Normal Operating Conditions (Pressure/Temperature)
Applicable Tables and Figures Unit 2 4-CV-2120-BB1 Weld 2 2.4 1
R-A R1.11 Chemical Volume and Control Pipe to Valve Weld SA-376 Gr.
TP304 SA-182 Type F316 or SA-351 Gr. CF8 or CF8M 50% single sided examination Limitation due to valve configuration 2300psi/530°F Table 2.4-1, Figures 2.4-1 and 2.4-2 Unit 2 8-RH-2106-KB2 Weld 13 2.5 2
R-A R1.11 Residual Heat Removal Pipe to Valve Weld SA-376 Gr.
TP304 SA-182 Type F316 or SA-351 Gr. CF8 or CF8M 69% single sided examination Limitation due to valve configuration 411psi/296°F Table 2.5-1, Figures 2.5-1 and 2.5-2 Unit 2 8-RH-2107-BB2 Weld 1 2.6 2
R-A R1.11 Residual Heat Removal Valve to Pipe Weld SA-182 Type F316 or SA-351 Gr. CF8 or CF8M SA-376 Gr.
TP304 69.3% single sided examination Limitation due to valve configuration 367psi/296°F Table 2.6-1, Figures 2.6-1 and 2.6-2 Unit 2 4-RC-2422 Weld 24 2.7 1
R-A R1.20 Reactor Coolant Pipe to Valve Weld SA-376 Gr.
TP304 SA-182 Type F316 50% single sided examination Limitation due to valve configuration 2318psi/563°F Table 2.7-1, Figures 2.7-1 and 2.7-2 Unit 2 CIAPCS-2A-PCW1 2.8 2
C-G C6.10 Containment Spray Pump Flange to Upper Case Weld SA-182 Gr.
F304 SA-182 Gr. F304 51.2%
Limitation due to concrete opening 42psi/262°F Table 2.8-1, Figures 2.8-1, 2.8-2, and 2.8-3
1.1 Weld RSG-1A-T1, "Steam Generator Channel Head-to-Tubeplate" REPLACEMENT STEAM GENERATORS 1A & 1C RSG-1A-T1( 103-STP*)
[~---
- --~
RSG - 1 C-T1(103 - STP*l"----._
Weld Thickness
/
TUBE PLATE 6 In (Norn)
CHANNEL HEAD BOLTI NG (1-20)--------------
SAFE END EL. 37' Figure 1.1-1 RSG-1A-T1 (Extracted from Reference DWG A-RSG-1 RO)
This weld was UT examined in Inspection Period 3, during the 1 RE21 refueling outage in 2018.
The NOE data came from UT Report No.: UT-2018-095/096/097. The UT Code Required Volume (CRV) was determined based on ASME Section XI, Figure IWB-2500-6. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 60°S wave transducers. The UT examination was limited by the permanent insulation support ring resulting in total UT coverage of 75.3% as described in Figures 1.1-2, 1.1-3, 1.1-4, 1.1-5, and 1.1-6. No recordable indications were detected during this scan.
Section V. Article 4 was used for this examination.
Page 17 of 55
TUBEPLATE SEE NOTE 3 FOR UNIT AXES IDENTIFICATION GMAW. SFA-5.14 CL.
2" TYP.
R.37 TYP.
68.72 SPHERICAL RADIUS BASE METAL Note: Unit 1 CHANNEL HEAD TO TUBEPLATE weld RSG-1A-T1 Summary# 015920 Exam limitation. Total length weld inspected was 470.20" where 116" of examination area not inspected due to interference of insulation support. Support obstructed travel path on 45DEG and 60DEG transducers 354.06" /470"' x 100% = 75.3% EXAM COVERAGE Piec,e S l'inr COfflpi'aS'.Sl:Oi'I
'lilfltoclty Vl!loocll)'
Co111ve Honal Probe: UT Probe Intl ;,. Ol'fss : 376.. Mmm Sc 10 1&
o_mm Figure 1.1-2 RSG-1A-T1 Scan Coverage and Scan Summary Page 18 of 55
TUBEPLATE SEE NOTE 3 FOR UNIT AXES IOENTlflCATION 5.92 REF.
BASE METAL 25 THK.
2* YP. ~-- s* T-YP.
R.39 TY?.
68.72 SPHERICAL RADIUS BASE METAL Note. Unit 1 CHA NEL HEAD TO TUBEPLATE weld RSG-1A*T1 Summary# 015920 Exam limitation.
Total length weld inspected was 4 70.20" where 11 s* of examination area not inspected due to interference of insulation support Support obstructed travel path on 45DEG and 600EG transducers 354 06' /470 20" x 100% = 75 3% EXAM COV RAGE Figure 1.1-3 RSG-1A-T1 Examination Location and Coverage Map 19.75mm 20.00mm 4200mm Wedge:
Length Width Exit Point 42mm 20mm 13.46mm Transducer:
Shape Diameter Frequency Length Width Square 10mm 2.25Mhz 25.4mm 12.7mm Figure 1.1-4 RSG-1A-T1 Examination Location and Coverage Map Page 19 of 55
S£E NOT£ 3 fOR UNIT ms IOENTlflCATION TUBEPLATE
.09 CHAN ELH 68.72 SPHERICAL RADIUS BASE METAL Note. Unit 1 CHANNEL HEAD TO TUBEPLATE weld RSG*1A*T1 Summary# 015920 Exam hm,tation.
Total length weld inspected was 470.20' where 116' of examination area not inspected due to
,nterferenoe of insulation support. Support obstructed travel path on 45DEG and 60DEG transducers 354 06" /470 20" x 100% = 75 3% EXAM COVERAGE Figure 1.1-5 RSG-1A-T1 Examination Location and Coverage Map Conventional Probe: UT Probe Index Offset: -376.42mm Scan Offset: 0mm Beam Angle: 61.25° Shear 42.00mm Wedge:
Length Width Exit Point 42mm 20mm 16mm Transducer:
19.75mm 3
3 Shape Diameter Frequency Length Width Square 10mm 2.25Mhz 25.4mm 12.7mm 20.00mm Figure 1.1-6 RSG-1A-T1 Examination Location and Coverage Map Page 20 of 55 K. \\\\£LO DEPOSI ESS STEEL CW:
E.. HEAD 0 RIMAI
1.2 Weld 4-CV-1120-8B1, Weld 2 "Chemical Volume and Control Pipe to Valve Weld" 4 - CV - 1120- BBl XCV0004 EL, 32' 3" 4-RC-1323-BBl SEE FIG, A-RC - 11 50460 1,
OTHER FIT TING FL ANGE XCV 0005 Figure 1.2-1 4-CV-1120-B81, Weld 2 (Extracted from Reference DWG A-CV-2)
This weld was UT examined in Inspection Period 1, during the 1RE17 refueling outage in 2012.
The NOE data came from UT Report No.: UT-2012-071. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 60°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 50% as described in Table 1.2-1 combined with Figure 1.2-2. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 21 of 55
DE Record#
IJT-20 12-07 Summacy # 1 :50400 xamination ctbod/fype; UT EXAMlNATJON De cription Of Limitation: EXA UMTfA TION DU TO PIPE TO VAL VE CONFTGURA IO _
EXAM]NED FROM PIPE SIDE ONLY.
Eleam (Weld) Thickness
- .. 61 Exmn_ We14) Wj!lt__fl,;.8 8.xam (Well!l_Len * (L}
- 14.8 E* ami11_.rtion Volum.e (EV):
.23 X. 14.8 X 1.8
- 6.13 EXAM VOLUME 23 X.]4.. 8 X.9 = 3.06 AREA OF L1MITA'flON amin.ation Co e-rnge {
) :
50% COVERAG HAS BEE OBTA[NED Sec profile ATTACHED Table 1.2-1 4-CV-1120-B81, Weld 2 Scan Coverage and Scan Summary Page 22 of 55
PIFE.
.s;,,ofl. TnA5
'f'RoJE.ct C rle/1,c.-. I VoL urli:
t.f
- CV - 1/?.0 tJel~I -:f.1-J_
,u r., l
- >\\_V I
I
-FLOW t,,
~00
<\\.
,;)J >t l't. 'I' ;.,.a ::. (,,/3 To1AL \\/.L*H-t
.scAN o.i i.>~,o
,u1: 'fI*SJ..,,t:.L r,. obf,,,N 50/4 ot THI; '£tC1Vt/2eO
£XAM1HATtOf./
VOL rJ Mt. '
,;)j 'I... /'1,11 <.,'i "" ;,oe, llf El " l*~,f. t,__.._
w* RL- "'flltv.r!
rlf' EXAM HP R'iliC.1'!
J,;J.
fo Figure 1.2-2 4-CV-1120-881, Weld 2 Examination Location and Coverage Map Page 23 of 55
1.3 Weld 8-RH-1006-KB2, Weld 13 "Residual Heat Removal Pipe to Valve Weld" 1 1 11 LD EL. 8' 12LU 12 3/4" SOL1/2 /
8-RH-1106-KB 8 - RH -1 107-BB 2
8 - RH - 1112-SEE FIG. A-R Figure 1.3-1 8-RH-1006-KB2, Weld 13 (Extracted from Reference DWG B-RH-7)
This weld was UT examined in Inspection Period 3, during the 1 RE22 refueling outage in 2020.
The NOE data came from UT Report No.: UT-2020-026. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 70°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 37.5%
as described in Figures 1.3-2, 1.3-3, 1.3-4, 1.3-5 and 1.3-6. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 24 of 55
H L
W 0.320" 21.AO" 1-36" = 9.310" TOTAL VOLUME
(),J20" 21.40" o.as*
- 5.S21" AREA OF LIMITATION Piece Length 3.439" AREA EXAMINED 37.5% EXAM COVERAGE Material Shear Velocity
SUMMARY
- 611000 PIPE TO VALVE WELD #13 LINE# 8"-RH-1 106-6B2 37% OF THE REQUIRED EXAMINATION VOLUME POI EXAM, DUE TO VALVE*TO.PIPI, CON FIGURA HON, SCANNING COULD OIIIL Y BE PE:RFORM 1.0 FROM PIPE: SIP, POI PROCEDURE IS NOT QUALIFIED FOR DETECTION AND LENGTH SIZING WHEN ONLY SINGLE-SIDED ACCESS IS AVAILABLE.
70 DEGREE LONGITUDINAL T ECHNIQUE SUPPLEMENTED FOR MAXIMUM EXAMINATION VOLUME COVERAGE.
Compression Velocity 100mm Steel - Austenitic 3.09mm/µs 5.74mmlµs HAZ: 25%
HAZ Width: 5mm Conventional Probe: 45DEG Index Offset: 80.29mm Scan Offset: 0mm Beam Angle: 56.74° Shear Figure 1.3-2 8-RH-1006-KB2, Weld 13 Scan Coverage and Scan Summary H
L W
0.320" 2140" 1.36" = 9.370"T0TAL VOLUME 0 320" 21 40" 0.35" = 5.821" AREA OF LIMITATION 3 4811" AREA EXAMINED 37 5'11. EXAM COVERAGE
SUMMARY
- 611960 PIPE TO VALVE WfLD #13 LINE# 6'"-RH* 1106*882 37% OF THE REQUIRED EXAMINATION VOLUME POI EXAM DUE TO VAI.VE*TO-PIPE CONFIGURATION, SCA NING COULD ON Y 6 PERFORMED FROM PIPE SID POI PROCEDURE IS I\\IOT QUALIFIED FOR DETECTION AND LENGTH SIZING WHEN ONLY SINGLE-SIDED ACCESS IS AVAILABLE.
70 DEGREE LONGITUDINAL TECHIIIIQU SUPPLEMENTED FOR MAXIMUM EXAMINATION VOLUME COVERAGE Figure 1.3-3 8-RH-1006-KB2, Weld 13 Examination Location and Coverage Map Page 25 of 55
15.65mm co 3
3 Wedge:
Length 27.18mm Width Exit Point 27.18mm 17.78mm 14.94mm Transducer: 014LJR 3
3 Shape Diameter Frequency Length Width Round 12.7mm 2.25Mhz 10mm 10mm 17.78mm Figure 1.3-4 8-RH-1006-KB2, Weld 13 Examination Location and Coverage Map H
l W
0.320" 21 4cr 1.36"
- 9.310" TOTAl VOLUME 0 320" 21 40" 0.85" = 5.821" AREA OF LIMITATION 3 489" AREA EXAMINED 37 5% EXAM COVERAGE
SUMMARY
- 611960 PIP TOVALV WELD #13 LI N # 8"*RH*1106-6B2 37% OF THE REQUIRED EXAMJNATION VOLUME POI EXAM DUE TO VALVE-TO.PIP CO FIGURATION, SCANNING COULD ON YB PERFORMED FROM PIPE SID POI PROCEDURE IS NOT QUALIFIED FOR DETECTION AND LENGTH SIZING WHEN ONLY SINGLE-SIDED ACCESS IS AVAILABLE.
70 DEGREE LONGITUDINAL T CHNIQU SUPPLEMENTED FOR MAXIMUM EXAMINATION VOLUME COV RAGE Figure 1.3-5 8-RH-1006-KB2, Weld 13 Examination Location and Coverage Map Page 26 of 55
Conventional Probe: 45DEG Index Offset: 29.65mm Scan Offset: 0mm 15.65mm
~
27.18mm ~
Wedge:
Length Width Exit Point 27.18mm 17.78mm 14.94mm Transducer: 014LJR Shape Diameter Frequency Length Round 12.7mm 2.25Mhz 10mm w
3 3
~
Width 10mm Beam Angle: 56.74° Shear 17.78mm Figure 1.3-6 8-RH-1006-KB2, Weld 13 Examination Location and Coverage Map Page 27 of 55
1.4 Weld 8-RH-1107-882, Weld 1 "Residual Heat Removal Valve to Pipe Weld" 1
3/4" soi1/2,,,,
40S SCH. 160 312 SA-376 8 - RH-1 107 - BB 2
8-RH - 1112-SEE FIG. A-R
~
8-RH - 11 08 - 88 1 SEE FIG. A-RH - 4 Figure 1.4-1 8-RH-1007-882, Weld 1 (Extracted from Reference DWG B-RH-7)
This weld was UT examined in Inspection Period 3, during the 1 RE22 refueling outage in 2020.
The NOE data came from UT Report No.: UT-2020-027. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-O. This volume was examined with 45°S and 70°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 37.5%
as described in Figures 1.4-2, 1.4-3, 1.4-4, 1.4-5, and 1.4-6. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 28 of 55
PIPE EXAM VOLIJME CAI.C H
L W
0.320" 21.40" 1.~*
- 9.310-TOT/\\L VOLUME 0.320" 21.40" 0.115"
- 5.11'21" AREA Of LIMITATIOO Hil'!I" AREA EXAMINED Piece SllltMARY# &124611 VALVE TO PIPE WELD #1 8"-RH-1107-BB2 J7% OF TliE REOIJIRED EXAM A IOtl VOI.UME PDI EXAM. DUE TO VALVE-TO-PIPE CON FIGURA noo.
SCANNING COULD ONLY BE PERFORMED FROM PIPE SIDE.
PDI PROCEDURE IS NOT QUALIFIED FOR IJl:TECTION AtlD LENGTH SIZlltm WHEN ONl Y SINGLE-SIDED ACCESS IS AVAILABI.E. 711 DEGREE LONGITUD AL TECHtllQUE SlJPPLEMENTEO FOR MAXIMUM EXAMltlATIOtlVOLUME COVEltl\\GE.
Length Material Shear Velocity Compression Velocity 100mm Steel - Austenitic 3.09mm/µs 5.74mm/µs Figure 1.4-2 8-RH-1007-882, Weld 1 Scan Coverage and Scan Summary PIPE EXAM VOLUME CALC H
L W
0320" 21.40" 136"=9.310"TOTALVOLUME 0 320" 21 40" 0 85"
- 5 821" AREA OF LIMITATION 3 489" AREA EXAMINED
SUMMARY
- 612460 VALVE TO PIPE WELD #1 8"-RH-1107-BB2 37% OF THE REQUIRED EXAMINATION VOLUME POI EXAM. DUE TO VALVE-TO-PIPE CONFIGURATION, SCANNING COULD ONLY BE PERFORMED FROM PIPE SID POI PROCEDURE IS NOT QUALIFIED FOR DETECTION AND LENGTH SIZING WHEN ONLY SINGLE-SIDED ACCESS IS AVAILABLE 70 DEGREE LONGITUDINAL TECHNIQU SUPPLEMENTED FOR MAXIMUM EXAMINATION VOLUME COVERAGE Figure 1.4-3 8-RH-1007-882, Weld 1 Examination Location and Coverage Map Page 29 of 55
15.65mm 3
3 17.78mm 27.18mm Wedge:
Length Width Exit Point 27.18mm 17.78mm 14.94mm Transducer: 014LJR Shape Diameter Frequency Length Width Round 12.7mm 2.25Mhz 10mm 10mm Figure 1.4-4 8-RH-1007-B82, Weld 1 Examination Location and Coverage Map PIPE EXAM VOLUME CALC H
L W
0 320" 21.40" 1.36" = 9.310" TOTAL VOLUME 0 320" 21 40" 0 85" 5 5 821" AREA OF LIMITATION 3 489" AR A EXAMINED
SUMMARY
- 612460 VALVE TO PIPE WELD #1 8"-RH-1 107-882 37% OF THE REQUIRED EXAMINATION VOLUME POI EXAM DUE TO VALVE-TO-PIPE CONFIGURATION, SCANNING COULD ONLY B PERFORM D FROM PIP SIDE PDI PROCEDURE IS NOT QUALIFIED FOR DETECTION AND LENGTH SIZING WHEN ONLY SINGLE-SIDED ACCESS IS AVAILABLE 70 DEGREE LONGITUDINAL TECHNIQU SUPPLEMENTED FOR MAXIMUM EXAMINATION VOLUME COVERAG.
Figure 1.4-5 8-RH-1007-B82, Weld 1 Examination Location and Coverage Map Page 30 of 55
Conventional Probe: 45DEG Index Offset: -55.01mm Scan Offset: 0mm Beam Angle: 56.74° Shear 15.65mm l
17.78mm 27.18mm Wedge:
Length Width Exit Point 27.18mm 17.78mm 14.94mm Transducer: 014LJR Shape Diameter Frequency Length Width Round 12.7mm 2.25Mhz 10mm 10mm Figure 1.4-6 8-RH-1007-B82, Weld 1 Examination Location and Coverage Map 2.1 Weld PRZ-2-N3 "Pressurizer Relief Nozzle to Shell Weld" MANWAY SPRAY NOZZLE N2 PRZ N2 PRZ N2 - IR SAFETY NOZZLE N3 PRZ N3 PRZ Nl3-IR Figure 2.1-1 Weld PRZ-2-N3 (Extracted from Reference DWG A-PRZ-1)
Page 31 of 55
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-014. The UT Code Required Volume (CRV) was determined based on ASME Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 0°, 45°S and 60°S wave transducers. The UT examination was limited on the nozzle side due to the nozzle configuration resulting in total UT coverage of 70.63% as described in Table 2.1-1 combined with Figure 2.1-2. No recordable indications were detected during this scan.
Section V, Article 4 was used for the examination.
oo 45" 60" 45° 60° 45 11 60° PRZ -2.-N3 Nio,ule Exam Coverage Scanning from H@aid to Nozzle vol11m tcn,11 Area, missecl Area Ad 1i l!'ll'edl 1 36.4 155.4 981 1 36.4 59 1077.. 4 1136.4 33.5 1102.9 Scann1ng from Nozz:le to Head
'Volume total Area mlue-d 1.136.4 359.4 136 1136.4 563.3 36 Scanning 45°' al"ld 60° CW/ CCW Volume tcrtal Area missed 1136.4 136 155.4 1136.4 136 155.4 Area Aclitic~ d 155.4 485.6 155.4 281.7 Achieved 86.3:3 100 94.81 100 97.0S 1'00 42.73 24.79 100 100 Areil, Afhievedl 845 845 74.36 100 74.36 100 494.42 700 Pe11centage of Exam Cove*rage 70.63 Table 2.1-1 Weld PRZ-2-N3 Scan Coverage and Scan Summary Page 32 of 55
/
/
I~ 1.ss*
WELD LENGTH CROWN 2.2" TOTAL VOLUME 3.7"
~
PRZ HEAD-N3 NOZZLE 1/2T j
1.83"
- s*
Fl l
7:
____ ___ 4.3-S" -----)r-1.5" :1 S.85"-------------,----a<
52.5" 1136.4 SCANNED OVER WELD TO OBTAIN MAXIMUM COVERAGE.
DRAWING NOTTO SCALE.
FOR REFERENCE USE ONLY.
Figure 2.1-2 Weld PRZ-2-N3 Examination Location and Coverage Map Page 33 of 55
~
Cl 0..,
VI
2.2 Weld PRZ-2-L6 "Pressurizer Relief Nozzle to Shell Weld" SHELL E PRZ C6 SHELL F PRZ-2-L5 SEAM WELD PRZ L6(
3 " MIN----
CIRCUMFERENTIAL WELD HEAD P/54-STP*)
1 Figure 2.2-1 Weld PRZ-2-L6 (Extracted from Reference DWG A-PRZ-1)
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-017. The UT Code Required Volume (CRV) was determined based on ASME Section XI, Figure IWB-2500-2. The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 0°, 45°S and 60°S wave transducers. The UT examination was limited due to the permanent insulation support ring resulting in total UT coverage of 85% as described in Table 2.1-1 combined with Figures 2.1-2, 2-1.3, and 2.1-4. No recordable indications were detected during this scan.
Section V, Article 4 was used for the examination.
NOMENCLATURE o0 DN WELD AND BASE MATERIAL 4S0 PERPENDICULAR/CW/CCW 45° PARALLEL/UP 45° PARALLEL/DOWN 60° PERPENDICULAR/CW/CCW 50° PARALLEL/UP 50° PARALLEL/DOWN TOTAL COVERAGE OBTAINED SHELL F LONGITUDINAL WELD/PRZ-2 010400 COVERAGE OBTAINED 90 90 73 90 90 98 66 597 85%
COVERAGE REQUIRED 100 100 100 100 100 100 100 700 Table 2.2-1 Weld PRZ-2-L6 Scan Coverage and Scan Summary Page 34 of 55
0° COVERAGE FOR LONG SEAM WELD 11151.JIATION S\\JPf'0RT 12*
I 4.1l~H)Xll~WfX!.3(l) H l01A~YOLUM~*471t,0 I EXAM AREA WELD LENGTH 12" WELD CROWN 3.5" TOTAL VOLUME 478.0 90% COVERAGE OBTAINED DRAWING NOT TO SCALE.
FOR REFERENCE USE ONLY.
Figure 2.2-2 Weld PRZ-2-L6 Examination Location and 0° Coverage Map 45° LIMITATIONS FOR LONG SEAM WELD INSULATICmSU~T
-l
EXAM AREA 4,&~
WELD LENGTH 12" WELD CROWN 3.5" TOTAL VOLUME 478.0 97% COVERAGE OBTAINED 1,75JIL75KU*ZS,4(2*1l.7;W:3" 74 % COVERAGE OBTAINED I A 6.SSU.Ul.3*261 I 8
4.IU.Ul.);915 I C
6.SSU.Ul.) *126 I 1'
DRAWING NOT TO SCALE.
FOR REFERENCE USE ONLY.
Figure 2.2-3 Weld PRZ-2-L6 Examination Location and 45° Coverage Map Page 35 of 55
WELD LENGTH 12" WELD CROWN 3.5" TOTAL VOLUME 478.0 60° LIMITATIONS FOR LONG SEAM WELD EXAM AREA 98% COVERAGE OBTAINED M AREA 73% COVERAGE OBTAINED DRAWING NOT TO SCALE.
FOR REFERENCE USE ONLY, Figure 2.2-4 Weld PRZ-2-L6 Examination Location and 60° Coverage Map Page 36 of 55
2.3 Weld RSG-2A-T1, "Steam Generator Channel Head-to-Tubeplate" REPLACEMENT STEAM GENERATORS 2A
~ 2C RSG-2A-T1 RSG-2C-Tl Weld Thickness 6 In (Norn)
Figure 2.3-1 RSG-2A-T1 (Extracted from Reference DWG A-RSG-1 RO)
This weld was UT examined in Inspection Period 3, during the 2RE20 refueling outage in 2019.
The NOE data came from UT Report No.: UT-2019-049. The UT Code Required Volume (CRV) was determined based on ASME Section XI, Figure IWB-2500-6. The corresponding CRV as shown on that Figure is E-F-G-H. This volume was examined with 45°S and 60°S wave transducers. The UT examination was limited by the permanent insulation support ring resulting in total UT coverage of 88% as described in Figures 2.3-2, 2.3-4, 2.3-5, and 2.3-6. No recordable indications were detected during this scan.
Section V. Article 4 was used for this examination.
Page 37 of 55
TUBEPLATE SEE NOIT 3 FOR UNIT AXES IDENTIFICATION 02 2* TYP.
6' TYP.
68.72 SPHERICAL RADIUS BASE METAL Note: Unit 2 CHANNEL HEAD TO TUBEPLATE weld RSG-2A-T1 Summary# 015920 Exam limitation.
Total length weld inspected was 470.20" where 56.42" of examination area not inspected due to interference of insulation support. Support obstructed travel path on 45DEG and 60DEG transducers 413.776" /470" x 100% = 88.0374468085% EXAM COVERAGE Comp,.,,sll\\on Valoolty Colii!lentiooal Probe; Uil' Probe lnoln Of&at: fflJ84n:rn k.an Offset: On:rn l!laam A.nliJla:. ~ ~
Sbear Figure 2.3-2 RSG-2A-T1 Scan Coverage and Scan Summary Page 38 of 55
TUBEPLATE
!'E:E NOT£ 3 FOR UNIT AXES IDENTIFlCAllON 5.92 REF'.
BASE MEf,1,.L 2* T'l'P.
H--+--6' TYi'.
oB 72 SPHERICAL RAD!US 8AS£ METAL ota. Unit 2 CHANNEL f-lEAD TO TUBEPlATE weld RSG-2A-Tl Summary # 015920 Exam limitabon.
Total length weld inspected was 470.20" where 56.42" of examinalion area nol inspacted due to interference of msulabon support. Support obstructed travel path on 450 G and SODEG transducers 413 776" 14'70' x 11)0% = 88.0374468085% EXAM GOVERAG
- Figure 2.3-3 RSG-2A-T1 Examination Location and Coverage Map
/
19.75mm
/
42.00mm Wedge:
Length Width Exit Point 42mm 20mm 13.46mm Transducer:
Shape Diameter Frequency Length Square 10mm 2.25Mhz 25.4mm
~
3 I<-
Width 12.7mm 20.00mm Figure 2.3-4 RSG-2A-T1 Examination Location and Coverage Map Page 39 of 55
TUBEPLATE SEE NO E 3 FOR UNIT AXES IOE'ITTFIC.lllON BA 2* T'IP.
6' TYP.
R..39 TYP
.09 CHAN ELH 6B 72
~ERICAL RADIUS 84SE MITAL ol Unit 2 CHA NEL HEAD TO TUBEPLATE weld RSG-2A-Tl Summary/I 015920 ham l1m1tahon.
Total length we'ld inspeoted was 470,20" where 56.42" of examination area not inspeoted di,e to mter:ference of 1nsulabon support. Support obslrucled travel path on 45OEG and 60DEG transducers 413 776" /470" x 100% = 88.0374468085% EXAM COVERAG
- Figure 2.3-5 RSG-2A-T1 Examination Location and Coverage Map Conventional Probe: UT Probe Index Offset: -376.42mm Scan Offset : 0mm Beam Angle : 61.25° Shear 19.75mm
~
g g
3 3
3 3
I 20.00mm 42.00mm Wedge:
Length Width Exit Point 42mm 20mm 16mm Transducer:
Shape Diameter Frequency Length Width Square 10mm 2.25Mhz 25.4mm 12.7mm Figure 2.3-5 RSG-2A-T1 Examination Location and Coverage Map Page 40 of 55
2.4 Weld 4-CV-2120-8B1, Weld 2 "Chemical Volume and Control Pipe to Valve Weld" 4-CV-2120- BBl XCV0004 EL. 32' 3' 4-RC-2323 -BBl SEE FI G, A-RC-11 I
I
_._._._._R
- _-_. -*-------*--- *_-M-_.._._._._.2*-*.-.-0*-- *1*.-.-s*-- *E*_-_-_._._._
- 1.
OTHER MATERIA FITTI NGS FLANGES xcvooos 2
Figure 2.4-1 4-CV-2120-B81, Weld 2 (Extracted from Reference DWG A-CV-2)
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-038. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 60°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 50% as described in Table 2.4-1 combined with Figure 2.4-2. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 41 of 55
PAGE _).._ OF ~
ISi EXAMINATION COVERAGE NDE Record#
Ui-1..D\\~-03, t I Summary#
'"')Q'4l.0 xamination Method/fype:
,.r-r Description Of Limitation:
1/~L..VC Exam (Weld) Thickness (D:
~o I Exam (Weld) With (W): !>N " I Exam (Weld) Length (L): 1,.. (l,1,('
Examination Volume (EV):
X' 1'4-7~-:..
y ' 4 J~
,ofAL
,1..o)( J.'5't L..\\M\\,A1\\0I-L
~ Cl l.>./W\\i;
,L.0)(
- 11. x,~:is= 2.vH.
Examination Coverage (EC):
ID1~L covi..11.AG,i;; -:. SO'-'I b
(/;l 0 Q.L US I.'.) ~s ~G:S, E"F-F-<>12..T To "' l.1-111: IA. tw>-X '"'-'VW1 couc.ocAG.f"
% Examination Covera~):
so"'!o Table 2.4-1 4-CV-2120-B81, Weld 2 Scan Coverage and Scan Summary Examination Volume Coverage Plot/Drawing:
Scale 1/4" ~
CI~
_J,*
I" Flow Figure 2.4-2 4-CV-2120-B81, Weld 2 Examination Location and Coverage Map Page 42 of 55
2.5 Weld 8-RH-2106-8B2, Weld 13 "Residual Heat Removal Pipe to Valve Weld" 11 LD EL. 8' 3/4" SOL1/2 /
SCH. 40S SC H. 160 SA-3 12 SA-376 8-RH-21 07 - BB
~
8-RH-2108-881 SEE FIG. A-RH-4 Figure 2.5-1 8-RH-2106-B82, Weld 13 (Extracted from Reference DWG B-RH-7) 8 s:
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-039. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-O. This volume was examined with 45°S and 60°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 69.3%
as described in Table 2.5-1 combined with Figure 2.5-2. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 43 of 55
PAGE 0 1' -9.. '
I I EXAMINATJO ' COVERAGE NDE Record #
\\. ) ) -- 1-0\\ '1~ '1 Summary#
9"0 C::, \\ \\ 1__, C 11.(}j
~
Examination Method/Type: - ") \\
Description Of Limitation:
i f\\\\.~t:
Exam (Weld) Thickness ITT:, ~ ~,1 Exam (Weld) With (W): 1.5.. Exam (Weld) Length (L): '3.1 ' t.f,,
Examination Volume (EV):
\\o'"\\kL
- '!:>\\ 'I 'S."L 5 );" 3 1. '-I. ::.. '.:> l. "'-i
.._)
L \\'M,\\'"\\f.lr\\lt)l,I. r;/OUJW\\~
-~II/ l(sf.'-f-=- 'i' 7'54 Examination Coverage (EC):
\\u-C~L L Q1.lC~A:-~ G -:.. Co'). ~*/.,
C:, ()
¥2_\\....
\\.)~ G, \\> "s '<1:>< !, ),.- E. r-r--c. IL T,o /'\\ c.. ~ 1 G".,it; I""" c.... )( 1 \\;\\,\\_ vl-V\\ (.o vt.RA~~
I
~
I
% Examination y0v1,1~e (~ EC): -
(p9. ':)
Table 2.5-1 8-RH-2106-B82, Weld 13 Scan Coverage and Scan Summary Page 44 of 55
PAGE L 01' 3 ISi EXAMINATJO COV *RAGE NDE Record fl Summary#
q Examinali on Volume Coverage }>Jot/Dr-a wing:
S-~!4 -1..lo Ga. - ~ts2 - WG1-!) 1.3 L I r,,,,A"Tf OM (oui;-riA.G.G PLOT I
FL~
j I '
. j Figure 2.5-2 8-RH-2106-882, Weld 13 Examination Location and Coverage Map Page 45 of 55
2.6 Weld 8-RH-2107-882, Weld 1 "Residual Heat Removal Valve to Pipe Weld" EL.
3/4" sot1/2 /
SCH. 40S SCH. 160 SA-3 12 SA-376 8 - RH-21 07 - BB
~
8-RH-2 108-8B1 SEE FIG. A-RH-4 8-SEE Figure 2.6-1 8-RH-2107-882, Weld 1 (Extracted from Reference DWG B-RH-7)
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-040. The UT Code Required Volume (CRV) was determined based on EPRI TR-112657, Figure 4-2 "Examination Volume for Thermal Fatigue Cracking in Piping Welds NPS 4 or Larger." The corresponding CRV as shown on that Figure is A-B-C-D. This volume was examined with 45°S and 60°RL wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 69.3%
as described in Table 2.6-1 combined with Figure 2.6-2. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII,
Supplement 2.
Page 46 of 55
PAGE OF Q_
ISi EXAMINATION COVERAGE DE Record#
UT--z..011-oYo Summary#
(.,\\V-lt..O Examination Method/Type:
0T Description Of Limitation:
V Al'J~
Exam (Weld) Thickness (D:..-'fS "' I Exam (Weld) With (W):
IS" Exam (Weld) Length (L): '3/. Lf" Examination Volume (EV):
I.-.-
.3 1X ~.-Z..S'X~l *'-'/
'!)\\.C....f,,._,
loT/!o.L
~
L \\'W\\1T.e-1 10"'-
vowwte
- J ly f 'i ~ \\. '4 ::.
~.71~
Examination Coverage (EC):
-ro TA L, ( O ~
t; -::. l.q. Yo "0° Q.L V!:.El) C..S ~&s:1 l=Fr-til'...1 T o ACI-I IG"I/G ""lAX'lh,;,V\\.v,_ <'Dv~-<;
% Examination Cpverage (% EC):
&Cf~
Table 2.6-1 8-RH-2107-882, Weld 1 Scan Coverage and Scan Summary Page 47 of 55
PAGE.J_ OF 3_
ISi EXA IN TJON COV RAGE DERecord#
Suttu ary#
. Ll 1.A(.l:>
Examination Volume Coverage Plot/Drawing:
- -.-,. ~ - -- - -
FLDW t
I Scale i/4., -
,(
__:_a.._,__,,
l
Figure 2.6-2 8-RH-2107-882, Weld 1 Examination Location and Coverage Map Page 48 of 55
2.7 Weld 4-RC-2422-881, Weld 24 "Reactor Coolant Pipe to Valve Weld" l ' SOL
~
EL. 69'
-BBl t,,,\\J'?.i
~<::F>~ 7
- CV - 2121 - BBl EE FIG. A-CV - 3 EL. 50' 18 12 NOTES
- 1. *TH FIT 9
4-RC - 2422-BB l Figure 2.7-1 4-RC-2422-881, Weld 24 (Extracted from Reference DWG A-RC-13)
This weld was UT examined in Inspection Period 1, during the 2RE16 refueling outage in 2013.
The NOE data came from UT Report No.: UT-2013-004. The UT Code Required Volume (CRV) was determined based on ASME Section XI, Figure IWB-2500-8c as this weld does not have any potential degradation mechanism. The corresponding CRV as shown on that Figure is C-O-E-F. This volume was examined with 0°, 45°S and 70°S wave transducers. The UT examination was limited by the valve configuration resulting in total UT coverage of 50% as described in Table 2.7-1 combined with Figure 2.7-2. No recordable indications were detected during this scan.
Section XI Appendices and Supplements used for this UT examination were Appendix VIII, Supplement 2.
Page 49 of 55
PAGE -1.. OF..J_
ISi EXAMINATION COVERAGE NDE Record #
UT&EXAM&2013-004 Su1mnary # 106160 Examination Med:iodffype: ULTRASONICS UTI-PD[-UT-2 Description Of Limitation: PROXIMITY OF VALVE TO \\VELD Single-Sided Exam Exam (Weld) 111.ickness ITT: 0.530" ii Exam {We.Id) With (W): 1,48" Exam (Weld) Length (L): 14.3 '
xamination Volume (EV):
AXIAL(TOWARDS VALVE) 053 X 1.48 X 14.3' = 11.217 = 100%
AXIAL (TOWARD PIPE) 0.53 XO X 14.3".:: 0 = 0%
CJRC PLPE SIDE (COU TER CWCK WISE) 0.53 X 1.48 X. 14.3" = 1.217= 100%
CIRC PIPE SIDE {CLOCK WISE) 0.53 X 1.48 X 14.3" = 11,217 : 100%
i CIRC VAL VE SIDE (COU TER CLOCK WISE) 0.53 XO X 14,3" = 0 : 0%
CIRCV VE SIDE (CLOCK WISE) 0.53 XO X 14.3": 0 = 0%
Examination Coverage (EC):
I AXIAf...(TOW ARDS VALVE)
- Q,53 X 1.48 X 14.3" = 11.217 ~ 1()()%
AXIAL (TOW ARD PJPE) 0..53 XO X 14.J' = 0 = 0%
ClRC PIPE SIDE (COUNTER CLOCK WISE) 0.53 X 1.48 X 14.3 = 11.217 '-' 100%
cmc PlPE SIDE (CLOCK WI E) 0.53 X 1.48 14.3" = 11.217 = 100%
crn.c VALVE SIDE (COUNTER CLOCK WISE) 0.53,._ 0 X 14.3" ~ 11.217 = 0%
CIRC VAL VE SIDE (CLOCK WISE) 0.53 XO X 14.3" = 11.217 = 0%
% Examination Covera~): 50%
Table 2. 7-1 4-RC-2422-B81, Weld 24 Scan Coverage and Scan Summary Page 50 of 55
PAGE _]_ OF _]_
ISi EXAMINA TIO COVERAGE NOE Record#
lYf-EXAM-2013-004 Examination Volume Coverage Plot/Drawing:
Flow VALVE WCL Summary # 106160 PIPE Valve to Pipe Weld Risk Informed ISi Exam Volume Figure 2. 7-2 4-RC-2422-B81, Weld 24 Examination Location and Coverage Map Page 51 of 55
2.8 Weld CIAPCS-2A-PCW1 "Containment Spray Pump - Flange to Upper Case" PUMP ROOM FLOOR GRATING PCW 1 PCW2~
NEOPRENE SEAL PCW3 CSP FLANGE LOWER CASE BOTTO SEAM WELD PCW5 PUMP PIT FLOOR t
25" I
55" 12."
I Figure 2.8-1 CIAPCS-2A-PCW1 (Extracted from Reference DWG B-CSP-1)
This weld was Liquid Penetrant examined in Inspection Period 1, during the 2RE16 refueling outage in 2013. The NOE data came from PT Report No.: UT-2013-105. The Code Required Surface Area (CSA) was determined based on ASME Section XI, Figure IWC-2500-8. The corresponding CSA as shown on that Figure is A-B. This surface area was examined with Liquid Penetrant method. The surface examination was limited due to the concrete opening resulting in total CSA coverage of 51.2% as described in Table 2.8-1 combined with Figures 2.8-2 and 2.8-3. No recordable indications were detected during this scan.
Section XI, IWA-2222 which referencesSection V, Article 6.
Page 52 of 55
PAGE _I_ OF _2_
ISI XAMINATION COVERAGE LIMITATION t-,~E Rerord # (same as Fonn I RccoTd #)
Summary# 750120 CIAPCS-2A-PCWI PT-2013-105 Examination Method/Type: Liquid Peoetrant (Color Contrast Solvent Removable)
Description OfLintitatioo: See attached photos and dTawings for limitatton area's due to building struetll.Tc.
Total Examination Len~h (L): 78.375" Total Examination Width (W); 1.500" Total Limitation LenJ..rth {LL): 38.350" Exmnination Area (EA): 117.563" E:xamin.ition Coverage (EC): 60.1 88"
% Examinabon Coverage(% EC): 51.20%
I Calculations:
A B
C D
- f F
Total Total Exam Limitation E)(.<lmin.ation
- Examimrtion Examination leng~h Width Lerigth Area "(A0 8)
Coverage- {A~C}
Coverage=
~ Weld ID I
(L)
(W)
(LL)
(EA)
(EC)
(E/0}
I PCWl 78.375 1.500 3,8.2.50 117.563 60.188 51.W%
Table 2.8-1 CIAPCS-2A-PCW1, Weld 24 Area Coverage and Area Summary Page 53 of 55
General ie Looking up, comer Looking up
- W, mer.
Figure 2.8-2 CIAPCS-2A-PCW1, Weld 24 Examination Location and Coverage Map Page 54 of 55
Total Length
~*~ *
.d
~ot~-~al -Total
- j leng:th I Length l Total ASME 1 Missed Examined i Code Credit I Year "A
B" "G'
1
A / C
.___* 2_0_13_* -'--_7,8_.375 __ :3~ ~ 0-40.125 l __ 5_f~% J z
Figure 2.8-3 CIAPCS-2A-PCW1, Weld 24 Examination Location and Coverage Map Note: NOE report has typographical error. Exam coverage calculation is actually "CIA" Page 55 of 55