AEP-NRC-2021-04, Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval

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Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval
ML21067A102
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/01/2021
From: Lies Q
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2021-04
Download: ML21067A102 (282)
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Text

m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant pc,1,*.'ER One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com March 1, 2021 AEP-NRC-2021-04 10 CFR 50.55a Docket No.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Relief Request for Limited Coverage Examinations Performed In The Fourth 10-Year Inspection Interval The fourth 10-year interval for the inservice inspection program for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2 concluded on February 29, 2020. During this interval, the components identified in Enclosure 1 received less than the required examination coverage. Accordingly, pursuant to 10 CFR 50.55a(g)(5)(iii), Indiana Michigan Power Company (l&M) requests relief on the basis that the required examination coverage is impractical due to physical obstructions and limitations imposed by design, geometry, and materials of construction of the subject components. contains the relief request and the basis for this request.

There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.

Sincerely, Q.~Lies 2~A-~

Sitl Vi~~ President JMT/mll

Enclosures:

1. Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0. In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality

U. S. Nuclear Regulatory Commission AEP-NRC-2021-04 Page 2 c: R. J. Ancona - MPSC EGLE - RMD/RPS J. 8. Giessner - NRC Region Ill D. L. Hille - AEP Ft. Wayne, w/o enclosures NRC Resident Inspector R. M. Sistevaris -AEP Ft. Wayne, w/o enclosures S. P. Wall - NRC, Washington, D.C.

A J. Williamson - AEP Ft. Wayne, w/o enclosures

Enclosure 1 of AEP-NRC-2021-04 Donald C. Cook Nuclear Plant (CNP) Units 1 and 2 American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality I. ASME Code Component(s) Affected The Donald C. Cook Nuclear Plant (CNP), Units 1 and 2, Class 1 and 2 welds with limited examination coverage that are included in this request for relief are for the Fourth Ten-Year lnservice Inspection Interval. The content of this request includes the insights gained from guidance provided by the NRC to the industry in Reference 1. The following Code Classes, Examination Categories, and Item Numbers apply.

Code Classes: 1 and 2 Examination Categories: 8-A, 8-D, 8-K, C-8, R-A Item Numbers: 81.11, 81.21, 81.22, 83.110, 810.10, C2.21, R1.11, R1.11/16, R1.16, R1.20 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 lnservice Inspection of Nuclear Power Plant Components, 2004 Edition (Reference 2) and was used for the Fourth 10-Year lnservice Inspection (ISi) Interval at CNP as modified by 10CFR 50.55a. The Appendix VI 11 requirements and use of the Performance Demonstration Initiative (POI) requirements at CNP were in accordance with the 2001 Edition of Section XI (Reference 3) 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 CNP Fourth 10-Year ISi Interval ended on February 29, 2020, for Units 1 and 2. The limited coverage examinations contained in this request are required to be submitted to the NRC on or before 12 months after this date.

Ill. Applicable Code Requirements Exam Item Class 1 Weld Examination Coverage Requirements Cat. No.

To include the examination volume of the Reactor Pressure Vessel Shell 8-A 81 .11 Welds as depicted in the applicable figure shown in Fiqure IWB-2500-1 To include the examination volume of the Reactor Pressure Vessel Head 8-A 81.21 Welds as depicted in the applicable fiqure shown in Fiqure IWB-2500-3 To include the examination volume of the Reactor Pressure Vessel Head 8-A 81.22 Welds as depicted in the applicable figure shown in Figure IWB-2500-3 To include the examination volume of the Pressurizer Nozzle-to-Vessel 8-D 83.110 Welds as depicted in the applicable figure shown in Figures IWB-2500-?(a), (b), (c), or (d)

To include the surface area of the Pressurizer support skirt attachment 8-K 810.10 weld as depicted in the applicable figure shown in Figure IWB-2500-14

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality Exam Item Class 2 Weld Examination Coverage Requirements Cat. No.

C-8 C2.21 To include essentially 100% examination of the Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld as depicted in Figures IWC-2500-4(a),

(b), or (d)

Exam Item Class 1 Piping Welds / Risk-Informed lnservice Cat. No. Inspection Program Coverage Requirements R-A R1 .11 To include essentially 100% of the examination location potentially subject to thermal fatigue.

R-A R1 .11/ To include essentially 100% of the examination location potential subject 16 to thermal fati1=1ue and lnter1=1ranular Stress Corrosion CrackinQ (IGSCC)

R-A R1.16 To include essentially 100% of the examination location potentially subject to lnter1=1ranular Stress Corrosion CrackinQ (IGSCC)

R-A R1.20 To include essentially 100% of the examination location with no de1=1radation mechanism As previously defined in 10 CFR 50.55a(g)(6)(ii)(A)(2), and as stated in ASME Section XI Code Case N-460 (Reference 4) as approved in Regulatory Guide 1.147, Revision 19 (Reference 5),

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. Code Case N-460 was invoked for the required coverage associated with the welds in this request.

Limited Class 1 Welds Table IWB-2500-1, Examination Category 8-A, "Pressure Retaining Welds in Reactor Vessel,"

Item Nos. 81 .11 - limitations applied to the Lower Shell to Bottom Head Weld 2-RPV-D; 81 .21 limitations applied to the Lower Head Circumferential Weld 2-RPV-E; 81 .22 limitation applied to the seven Bottom Head Meridional Welds 2-LHM-01 @26°, 2-LHM-02 @77°, 2-LHM-03@ 129°,

2-LHM-04@ 180°, 2-LHM-05 @231°, 2-LHM-06 @283°, and 2-LHM-07@ 334°.

Table IWB-2500-1, Examination Category B-D, "Full Penetration Welded Nozzles in Vessels - Inspection Program B," Item No. 83.110 - limitations applied to six pressurizer nozzle-to-vessel welds 4"-2-RC-28 (Upper Head to Spray Nozzle), 6"-2-RC-22 (Upper Head to Relief Nozzle), 6"-2-RC-25 (Upper Head to Relief Nozzle), 6"-2-RC-26 (Upper Head to Relief Nozzle), 6"-2-RC-27 (Upper Head to Relief Nozzle) and 14"-2-RC-21 (Surge Nozzle to Lower Head). Table IWB.,2500-1, Examination Category B-K, "Welded Attachments for Vessels, Piping, Pumps, and Valves," Item No. 810.10 - limitations applied to weld 1-PRZ-26 (Pressurizer Lower Head to Support Skirt Weld).

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality Limited Class 2 Welds Table IWC-2500-1, Examination Category C-B, "Pressure Retaining Nozzle Welds in Vessels,"

Item No. C2.21 - limitations applied to one Steam Generator Nozzle-to-Shell Weld on "Steam Generator No. 21 ". The examination coverage was limited to 76.3%. This limitation was due to the non-removable insulation support ring and configuration.

Limited Class 1 Piping Welds / Risk-Informed lnservice Inspection Programs Only Class 1 piping welds were selected for examination during the fourth interval under the Risk-Informed lnservice Inspection (RI-ISi) Programs used for CNP. These were examined in accordance with Code Case N-716 (Reference 6). Use of the Code Case was based on request for an alternative ISIR-4-01 that was authorized for use per Reference 7. The examinations performed during Unit 1 Outage U1C29 and Unit 2 Outage U2C25 were performed under Code Case N-716-1 (Reference 8) which was approved in RG 1.147 Revision 18.

Additional Examination Volume Requirements for Code Case N-716 Table 1, Examination Categories "Examination Category R-A," Item No. R1 .11 - Elements Subject to Thermal Fatigue, required the use of the examination volumes depicted in the ASME Section XI, Figures IWB-2500-8(c) and IWC-2500-9, -10, and. -11 with an additional requirement that read, Note (1) The length of the examination volume shown in Fig. IWB.,2500-8(c) shall be increased by enough distance [approximately 1/2 in.] to include each side of the base metal thickness transition or counterbore transition.

Evaluation of Change in Risk due to Limited Examinations per Code Case N-716-1 Footnote 3 states "Includes essentially 100% of the examination location. When the required examination volume or area cannot be examined due to interference by another component or part geometry, limited examinations shall be evaluated for acceptability. 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.

UNIT 1 CNP has reviewed each instance of limited coverage and taken the appropriate steps (e.g., relief requests) consistent with its impact on the basis of the N-716 application. This is done using the delta risk values. N-716-1 change in risk acceptance criteria is 1E-7/1E-8 CDF/LERF at the system level and 1E-6/1 E-7 total CDF/LERF for all systems. The "With Probability of Detection (POD) Credit" column is the official result that must meet these criteria. Below is a summary of the cumulative effect of the limited examinations.

This request identifies fifteen Unit 1 piping welds with limited examination coverage of 90% or less. Welds 1-CS-96-60F, 1-RH-29-01 F, 1-RC-1-11 N, 1-RC-1-14N, 1-RC-9-03S, 1-RC-11-12S, 1-Sl-29-20S, 1-Sl-29-23S, 1-Sl-29-26F, 1-Sl-31-21S, 1-Sl-31-24S, 1-Sl-31-27F, 1-Sl-51-22F, 1-Sl-51-27F, and 1-Sl-33-26F are addressed below, by system.

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality o Chemical and Volume Control (CS) Weld 1-CS-96-60F To conservatively quantify the effect on delta risk for the CS weld, the delta risk is adjusted by not crediting the CS weld with limited examination coverage. The below table provides the delta risk with the CS weld credited and with the CS weld 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 CS weld is acceptable.

CDF Impact I LERF Impact Source of Delta Risk w/POD I w/ POD Examined Latest interval periodic update cs -3.78E-08 I -3.78E-08 required by N-716, Section 7 Not Examined Adjusted delta risk using the

-3.24E-08 I ~3.24E-08 periodic update delta risk o ECCS (RH) Weld 1-RH-29-01 F To conservatively quantify the effect on delta risk for the RH weld, the delta risk is adjusted by not crediting the RH weld with limited examination coverage. The below table provides the delta risk with the RH weld credited and with the RH weld 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 RH weld is acceptable.

CDF Impact I LERF Impact Source of Delta Risk w/POD I w/ POD Examined Latest interval periodic update RH -2.91E-10 I -2.99E-10 required by N-716, Section 7 Not Examined Adjusted delta risk using the

-1.41E-10 l-1.49E-10 periodic update delta risk o Reactor Coolant (RC) Welds 1-RC-1-11 N, 1-RC-1-14N, 1-RC-9-03S, and 1-RC-11-12S Weld 1-RC-1-14N was in Examination Category 8-J, Item No. 9.21 and only required surface examination. It is a 11/2" Branch Connection with no degradation mechanism and therefore only receives a VT-2 visual examination. This examination does not impact the delta risk calculation and therefore a limited examination does not affect total risk.

To conservatively quantify the effect on delta risk for the remaining three RC welds, the delta risk is adjusted by not crediting the three RC welds with limited examination coverage. The below table provides the delta risk with the three RC welds credited and with the three RC welds not

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality credited. 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-07 for GDF and 1E-08 for LERF. Therefore, a limited examination of the three RC welds is acceptable.

GDF Impact LERF Impact Source of Delta Risk w/POD w/POD I Examined RC -1.55E-08 -1.55E-08 Latest interval periodic update required by N-716, I Section 7 Not Examined

-9.75E-09 -9.75E-09 Adjusted delta risk using the periodic update delta I risk o Safety Injection (SI) Welds 1-Sl-29-20S, 1-Sl-29-23S, 1-Sl-29-26F, 1-Sl-31-21S, 1-Sl-31-24S, 1-Sl-31-27F, 1-Sl-51-22F, 1-Sl-51-27F, and 1-Sl-33-26F To conservatively quantify the effect on delta risk for the nine SI welds, the delta risk is adjusted by not crediting the nine SI welds with limited examination coverage. The below table provides the delta risk with the nine SI welds credited and with the nine SI welds not credited. The columns under heading "Examined" are the delta risk with the nine SI welds included, the columns under heading "Not Examined" is the adjusted delta risk after removing the nine SI welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for GDF and 1E-08 for LERF. Therefore, a limited examination of the nine SI welds is acceptable.

GDF Impact I LERF Impact Source of Delta Risk w/POD I w/ POD Examined Latest interval periodic update SI -4.20E-10 I -4.52E-10 required by N-716, Section 7 Not Examined Adjusted delta risk using the 7.39E-11 I4.20E-11 periodic update delta risk

  • Cumulative Effect to Delta Risk for One CS Weld, One RH Weld, Three RC Welds and Nine SI 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 fourteen welds included, the columns under heading "Not Examined" is the adjusted delta risk after removing the fourteen welds. As can be seen, the change is negligible and well below the acceptable limits of 1E-07 for GDF and 1E-08 for LERF. Therefore, a limited examination of the one CS Weld, one RH Weld, three RC Welds and the nine SI Welds is acceptable.

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality CDF Impact I LERF Impact Source of Delta Risk w/POD I w/ POD cs Examined RH Latest interval periodic update RC

-5.41 E-08 I -5.40E-08 required by N-716, Section 7 SI Not Examined Adjusted delta risk using the

-4.23E-08 I -4.23E-08 periodic update delta risk UNIT2 CNP has reviewed each instance of limited coverage and taken the appropriate steps (e.g., relief requests) consistent with its impact on the basis of the N-716 application. This is done using the delta risk values. N-716-1 change in risk acceptance criteria is 1E-7/1 E-8 CDF/LERF at the system level and 1E-6/1 E-7 total CDF/LERF for all systems. The "With POD Credit" column is the official result that must meet these criteria. Below is a summary of the cumulative effect of the limited examinations.

This request identifies twelve Unit 2 piping welds with limited examination coverage of 90% or less. Welds 2-CS-120-13, 2-RC-17-06N, 2-RC-17-09N, 2-RH-33-01, 2-Sl-63-17, 2-Sl-58-23, 2-Sl-59-24, 2-Sl-59-25, 2-Sl-60-31, 2-Sl-60-32, 2-Sl-61-15, and 2-Sl-62-32 are addressed below, by system.

o Chemical and Volume Control (CS) Weld 2-CS-120-13 To conservatively quantify ~he effect on delta risk for the CS weld, the delta risk is adjusted by not crediting the CS weld with limited examination coverage. The below table provides the delta risk with the CS weld credited and with the CS weld 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 CS weld is acceptable.

CDF Impact I LERF Impact Source of Delta Risk w/POD I w/ POD Examined Latest interval periodic update cs -5.40E-08 I -5.40E-08 required by N-716, Section 7 Not Examined Adjusted delta risk using the

-4.86E-08 I -4.86E-08 periodic update delta risk

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality o ECCS (RH) Weld 2-RH-33-01 To conservatively quantify the effect on delta risk for the RH weld, the delta risk is adjusted by not crediting the RH weld with limited examination coverage. The below table provides the delta risk with the RH weld credited and with the RH weld 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 RH weld is acceptable.

CDF Impact I LERF Impact w/POD I w/ POD Source of Delta Risk Examined Latest interval periodic update RH -1.44E-10 l-1.49E-10 required by N-716, Section 7 Not Examined Adjusted delta risk using the 5.60E-12 I1.10E-12 periodic update delta risk o Reactor Coolant (RC) Welds 2-RC-17-06N and 2-RC-17-09N Weld 2-RC-17-09N was in Examination Category B-J, Item No. 9.21 and only required surface examination. It is a 11/2" Branch Connection with no degradation mechanism and therefore only receives a VT-2 visual examination under N-716-1. This examination does not impact the delta risk calculation and therefore a limited examination does not affect total risk.

To conservatively quantify the effect on delta risk for the remaining RC Weld 2-RC-17-06N, the delta risk is adjusted by not crediting the RC weld with limited examination coverage. The below table provides the delta risk with the RC weld credited and with the RC weld 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 RC weld is acceptable.

CDF Impact I LERF Impact w/POD I w/ POD Source of Delta Risk Examined Latest interval periodic update RC -7.50E-09 I -7.50E-09 required by N-716, Section 7 Not Examined Adjusted delta risk using the

-2.10E-09 I -2.10E-09 periodic update delta risk

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 1 O CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality o Safety Injection (SI) Welds 2-Sl-63-17, 2-Sl-58-23, 2-Sl-59-24, 2-Sl-59-25, 2-Sl-60-31, 2-Sl-60-32, 2-Sl-61-15, and 2-Sl-62-32 To conservatively quantify the effect on delta risk for the eight SI welds, the delta risk is adjusted by not crediting the eight SI welds with limited examination coverage. The below table provides the delta risk with the eight SI welds credited and with the eight SI welds not credited. The columns under heading "Examined" are the delta risk with the eight SI welds included, the columns under heading "Not Examined" is the adjusted delta risk after removing the eight SI 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 eight welds is acceptable.

CDF Impact I LERF Impact w/ POD I w/ POD Source of Delta Risk Examined Latest interval periodic update SI -7.03E-10 I -7.28E-10 required by N-716, Section 7 Not Examined Adjusted delta risk using the 3.53E-10 I3.28E-10 periodic update delta risk

  • Cumulative Effect to Delta Risk for One CS Weld, One RH Weld, One RC Weld and Eight SI 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 eleven welds included, the columns under heading "Not Examined" is the adjusted delta risk after removing the eleven 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 CS Weld, one RH Weld, one RC Weld and the eight SI Welds is acceptable.

CDF Impact I LERF Impact w/POD I w/ POD Source of Delta Risk cs Examined RH Latest interval periodic update RC

-6.25E-08 I -6.24E-08 required by N-716, Section 7 SI Not Examined Adjusted delta risk using the

-5.05E-08 I -5.04E-08 periodic update delta risk

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality 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 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 on or before February 28, 2021 because CNP has determined that compliance with the code requirements of achieving essentially 100% coverage of the welds listed in this request is impractical to achieve. However, because February 28, 2021 falls on a Sunday, and 10 CFR 50.4(a) states that: "If a submission due date falls on a Saturday, Sunday, or Federal holiday, the next Federal working day becomes the official due date.," it is appropriate to submit the request on the next business day, March 1, 2021. 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 CNP Unit 1 and 2 were issued on March 25, 1969 and fall under the provisions of 10 CFR 50.55a(g)(1 ), which were applied to components (including supports) that must meet the requirements of paragraphs (g)(4) and (g)(5) to the extent practical. Components that are part of the reactor coolant pressure boundary and their supports must meet the requirements applicable to components that are classified as ASME Code Class 1. Components that are classified as ASME Code Class 2 and 3 must meet the requirements applicable to components that are classified as ASME Code Class 2 and or Class 3. 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 Attachment 1.

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

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision Q In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality 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 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-A, Item No. B1.11, "Lower Shell to Bottom Head Weld" 2-RPV-D limitation was caused by the six core support lugs. Item No. B1 .21 "Lower Head Circumferential Weld" 2-RPV-E limitation was caused by the proximity of the Bottom Mounted Instrumentation Tubes. Item No. B1 .22 "Bottom Head Meridional Welds" 2-LHM-01, 2-LHM-02, 2-LHM-03, 2-LHM-04, 2-LHM-05, 2:-LHM-06, and 2-LHM-07 were caused by the proximity of the Bottom Mounted Instrumentation Tubes.

For the Class 1, Examination Category B-D, Pressurizer Nozzle-to-Vessel Welds, Item No.

B3.110, 6"-2-RC-22, 6"-2-RC-25, 6"-2-RC-26, 6"-2-RC-27, 14"-2-RC-21, and 4"-2-RC-22, limitations were 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. For the four nozzle welds, all with design limitations, to obtain the required coverage for each of these welds would require a design modification.

For the Class 1, Examination Category B-K, Item No. B 10.10, Pressurizer Lower Head to Support Skirt Weld, limitations were caused by the close proximity of the Pressurizer enclosure ventilation duct. The examination was performed from the skirt OD, and the examination could not be performed from the inside due to the heater sleeves and associated cables, as well as the small space between the skirt and the Pressurizer lower head. To obtain the required coverage for this weld the ventilation duct would have to be disassembled.

For the Class 2 Examination Category C-B, Nozzle-to-Shell Welds in Vessels, Item No. C2.21, limitations on the Feedwater Nozzle-to-Shell Weld (STM-21-FWN) on Steam Generator No. 21 is due to the non-removable insulation support ring and configuration.

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

American Society of Mechanical Engineers {ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality component design modifications or plant component disassembly. 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.

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 XI, 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, CNP 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. CNP 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 Category B-A, Pressure Retaining Welds in Reactor Vessel, Examination Category B-D, Pressurizer Nozzle-to-Vessel Welds, Examination Category B-K, Pressurizer Lower Head to Support Skirt Weld, the Class 2 Examination Category C-B, Pressure Retaining Nozzle Welds in Pressure Vessels, and the Class 1 Risk-Informed piping welds within the scope of this request are all located inside 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 required to be operable. As stated in CNP TS 3.4.15 "RCS Leakage Detection Instrumentation,"

the instrumentation consists of monitoring of containment sump level in each sump, containment atmosphere particulate radioactivity, and containment atmosphere gaseous radioactivity. These instruments are used to quantify any unidentified leakage from the RCS and to meet the CNP

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) lnservice Inspection Impracticality Technical Specifications Surveillance Requirements that have a Limiting Condition for Operation (LCO) in 3.4.13 stating that RCS Operational Leakage shall be limited to:

a. No pressure boundary LEAKAGE;
b. 0.8 gpm unidentified LEAKAGE;
c. 10 gpm identified LEAKAGE; and
d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator VII. Duration of Proposed Alternative This request for relief is for the CNP, Units 1 and 2, Fourth 10-Year ISi Intervals, which began on March 1, 2010, and ended on February 29, 2020.

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) NRC Safety Evaluation Report (SER) for Palo Verde Nuclear Generating Station, Unit 3 -

Relief Request 63 for Impractical Examinations for the Third 10-Year lnservice Inspection Interval, (EPID L-2019-LLR-0002), Dated December 4, 2019 [ADAMS Accession No.:

ML19331A608].

(2) NRC Safety Evaluation Report (SER) for Grand Gulf Nuclear Station - Relief Request GG-ISl-023, Examination Coverage of Class 1 Piping and Vessel Welds, (EPID L-2018-LLR-0197), Dated October 11, 2019 [ADAMS Accession No.: ML19266A586].

(3) NRC Safety Evaluation Report (SER) for St. Lucie Plant, Unit No. 1 - Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations, (EPID L-2019-LLR-0018), Dated September 30, 2019 [ADAMS Accession No.: ML19254B533].

(4) NRC Safety Evaluation Report (SER) for River Bend Station, Unit 1 - Relief Request RBS-ISl-021 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Third 10-Year Interval Volumetric Examinations, (EPID L-2018-LLR-0388), Dated September 27, 2019

[ADAMS Accession No.: ML19261A167].

(5) NRC Safety Evaluation Report (SER) for Limerick Generating Station, Units 1 and 2 - Relief Request 13R-23, Third 10-Year lnservice Inspection Interval, Exelon Generation Company, LLC, .(EPID L-2017-LLR-0098), Dated August 7, 2018 [ADAMS Accession No.: ML18192C172].

(6) NRC Safety Evaluation Report (SER) for Cooper Nuclear Station - Request Rl-21, Revision 1 - Request for Relief concerning Examinations for the Fourth 10-Year lnservice Inspection Interval (CAC No. MF9623; EPID L-2017-LLR-0026), Dated March 22, 2018 [ADAMS Accession No.: ML18064A102].

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR-4-11, Revision 0 In Accordance with 10 CFR 50.SSa(g)(S)(iii) lnservice Inspection Impracticality (7) NRC Safety Evaluation Report (SER) for Sequoyah Nuclear Plants, Units 1 and 2 - Relief Request No. 17-ISl-1 Regarding the Requirements of the American Society of Mechanical Engineers Code (CAC NOS. MF9690 and MF9691; EPID L-2017-LLR-0025), Dated January 26, 2018 [ADAMS Accession No.: ML18008A068]

(8) NRC Safety Evaluation Report (SER) for Indian Point Nuclear Generating Unit No. 2 - Safety Evaluation Regarding Relief Requests IP2-ISI-RR-20, IP2-ISI-RR-21, and IP2-ISI-RR-22 Regarding the Fourth 10-Year Interval of lnservice Inspection Program (EPID L-2017-LLR-0052, L-2017-LLR-0050, and L-2017-LLR-0051 ), Dated January 23, 2018 [ADAMS Accession No.: ML18005A066]

(9) NRC Safety Evaluation (SER) for North Anna Power Station, Unit No. 1 - Relief Request (RR)

N1-I4-LMT-002, Limited Coverage Examinations for the Fourth Ten-Year Inspection Interval (CAC NO. MF9689, EPID L-2017-LLR-0024), Dated January 10, 2018 [ADAMS Accession No.: ML18005A109]

(10) NRC Safety Evaluation Report (SER) for Watts Bar Nuclear Plant, Unit 2 - Relief from the Requirements of the American Society of Mechanical Engineers Code (CAC NO. MF8515; EPID L-2016-LLR-0003), Dated October 28, 2017 [ADAMS Accession No.: ML17292B295]

IX References

1. NRC presentation "Coverage Relief Requests", Industry/NRG NOE Technical Information Exchange Public Meeting January 13-15, 2015, [ADAMS Accession No.: ML15013A266].
2. ASME Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, 2004 Edition.
3. ASME Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components, Appendix VIII, Performance Demonstration for Ultrasonic Examination Systems, 2001 Edition.
4. ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 WeldsSection XI, Division 1".
5. NRC Regulatory Guide 1.147, lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 19, Dated October 2019. [ADAMS Accession No.: ML19128A244].
6. ASME Code Case N-716, "Alternate Classification and Examination Requirements".
7. NRC SER Donald C. Cook Nuclear Plant, Units 1 and 2- "Evaluation of lnservice Inspection Relief Requests ISIR-4-01, -02, -03, and -04", (TAC NO. ME4495 and ME4496), Dated March 30, 2011 [ADAMS Accession No. ML11073A084].
8. ASME Code Case N-716-1, "Alternate Classification and Examination Requirements".

Attachment 1 American Electric Power (AEP)

Donald C. Cook Nuclear Plant (CNP)

American Society of Mechanical Engineers (ASME)Section XI 10 CFR 50.55a Request for Relief Number ISIR 04-11, Revision 0 In Accordance with 10 CFR 50.55a(g)(5)(iii) - lnservice 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 CNP 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 CNP approved procedures and techniques during the span of the Fourth 10-Year ISi Interval. Therefore not all the coverage calculations used are identical, but they are based on the actual NOE data reports that were provided for the examinations completed.

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Materic;tl 2 and Examination Examination Limitations Applicable Seq. Number Category Description Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 2 1 Pressurizer1 SA-508 Class SA-533 Grade 83.3% Single side exam due to Figures 1.1-1.1 / B-D Upper Head 2 Mn-Mo A (Class 2) Nozzle-to-Shell 1, 1.1-2, and 4"-2-RC-28 B3.110 Spray Nozzle- 4.0" diameter 2.5" thick Configuration 1.1-3 to-Vessel Weld Schedule 120 Unit 2 1 Pressurizer1 SA-508 Class SA-533 Grade 86.7% Single sided access due Figures 1.2**

1.2 / B-D Upper Head 2 Mn-Mo A (Class 2) to the nozzle-to-head 1, 1.2-2, 1.2-6"-2-RC-22 B3.110 Relief Nozzle- 6.0" diameter 2.4" thick configuration with an 3, and 1.2-4 to-Vessel Weld Schedule 160 existing recordable indication evaluated to be acceptable Unit 2 1 Pressurizer1 SA-508 Class SA-533 Grade 86.7% Single sided access due Figures 1.3*-

1.3 / B-D Upper Head 2 Mn-Mo A (Class 2) to the nozzle-to-head 1, 1.3-2, 1.3-6"-2-RC-25 B3.110 Relief Nozzle- 6.0" diameter 2.4" thick configuration with one 3, 1.3-4, and to-Vessel Weld Schedule 160 previously recordable 1.3-5 indication and one new indication evaluated to be acceptable Unit 2 1 Pressurizer 1 SA-508 Class SA-533 Grade 86.7% Single sided access due Figures 1.4-1.4 / B-D Upper Head 2 Mn-Mo A (Class 2) to the nozzle-to-head 1, 1.4-2, and 6"-2-RC-26 B3.110 Relief Nozzle- 6.0" diameter 2.4" thick configuration 1.4-3 to-Vessel Weld Schedule 160 Unit 2 1 Pressurizer1 SA-508 Class SA-533 Grade 86.7% Single sided access due Figures 1.5-1.5 / B-D Upper Head 2 Mn-Mo A (Class 2) to the nozzle-to-head 1, 1.5-2, and 6"-2-RC-27 B3.110 Relief Nozzle- 6.0" diameter 2.4" thick configuration 1.5-3 to-Vessel Weld Schedule 160 Unit 2 2 Steam SA-508 Class ASTM A-533 76.3% Limitation due to non- Figures 1 .6-1.6 / C-B Generator1 2 Grade A Class removable insulation 1, 1.6-2, and STM-21-FWN C2.21 Feedwater 16.0" diameter 1 support ring and 1.6-3 Nozzle-to-Shell Schedule 80 3.7" thick configuration Weld

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld I Material 1 and Material 2 and Examination Examination Limitations Applicable Seq. ~umber Category Description

  • Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 1 1 Reactor ASTM A-376 A-403 Grade 85.1% 3 Limitation due to adjacent Figures 1 .7-1.7 / R-A Coolant Pipe to Grade TP 316 WP 316 weld 1, 1.7-2, and 1-RC-9-03S R1.20 Elbow1 6.0" diameter 6.0" diameter 1.7-3 Schedule 160 Schedule 160 Unit 1 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Figures 1.8-1.8 / R-A Elbow to Grade WP 316 Grade F316 to the branch connection 1, 1.8-2, and 1-Sl-33-26F R1.20 Branch 10.0"diameter 10.0" diameter configuration 1.8-3 Connection 1 Schedule 140 Unit 1 1 Residual Heat ASTM A-182 ASTM A-376 50% 3 Single sided access due Figures 1 .9-1.9 / R-A Removal Grade F316 Grade TP 316 to the branch connection 1, 1.9-2, and 1-RH-29-01 F R1.20 Branch 14.0" diameter 14.0" diameter configuration 1.9-3 Connection to Schedule 160 Pipe 1 Unit 1 1 Chemical and ASTM A-182 ASTM A-351 50% 3 Single sided access due Table 1.10-1, 1.10 / R-A Volume Control Grade F316 Grade CF8M to the branch connection Figures 1.10-1-RC-1-11 N R1 .11 3 in. Nozzle 3.0" diameter 27.5" inside configuration 1, 1.10-2, Branch diameter 1.10-3, and Connection 1 1.10-4 Unit 1 1 Reactor ASTM A-182 ASTM A-351 50% UT Single sided access due Table 1.11-1, 1.11 / R-A Coolant 1-1/2 Grade F316 Grade CF8M Coverage, but to the branch connection Figures 1.11-1-RC-1-14N R1.20 in. Nozzle 1.5" diameter 27.5" inside only requires configuration 1, 1.11-2, Branch diameter a VT-2 per N- 1.11-3, and Connection 1 716-1 1.11-4 Unit 1 1 Reactor ASTM A-403 ASTM A-376 50% 3 Single sided access due Table 1.12-1, 1.12 / R-A Coolant Elbow Grade WP 316 Grade TP 316 to a non-removable pipe Figures 1.12-1-RC-11-12S R1.20 to Pipe 1 4.0" diameter 4.0" diameter clamp 1, 1.12-2, Schedule 120 Schedule 120 1.12-3, and 1.12-4 Unti1 1 Safety Injection ASTM A-403 ASTM A-403 61.45% 3 Limited coverage due to Table 1.13-1, 1.13 / R-A Elbow to Tee 1 Grade WP 316 Grade WP 316 configuration of tee Figures 1 .13-1-Sl-29-20S R1 .16 10.0" diameter 10.0" diameter 1, 1.13-2, Schedule 140 Schedule 140 1.13-3, and 1.13-4

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Material 2 and Examination Examination Limitations Applicable Seq. Number Category Description Product Form Product Form Co.de and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 1 1 Safety Injection ASTM A-403 ASTM A-376 50% 3 Single sided access due Table 1.14-1 ,

1.14 / R-A Tee to Pipe 1 Grade WP 316 Grade TP 316 to configuration of tee Figures 1.14-1-Sl-29-23S R1 .16 10.0" diameter 10.0" diameter 1, 1.14-2, Schedule 140 Schedule 140 1.14-3, and 1.14-4 Unit 1 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.15-1, 1.15 / R-A Elbow to Grade WP 316 Grade F316 to branch configuration Figures 1.15-1-Sl-29-26F R1.20 Branch 10.0" diameter 10.0" diameter 1, 1.15-2, Connection 1 Schedule 140 1.15-3, and 1.15-4 Unit 1 1 Safety Injection ASTM A-403 ASTM A-403 50% 3 Single sided access due Table 1.16-'I, 1.16 / R-A Elbow to Tee 1 Grade WP 316 Grade WP 316 to configuration of tee Figures 1.16-1-Sl-31-21 S R1 .16 10.0" diameter 10.0" diameter 1, 1.16-2, Schedule 140 Schedule 140 1.16-3,and 1.16-4 Unit 1 1 Safety Injection ASTM A-403 ASTM A-376 50% 3 Single sided access due Table 1.17-*1, 1.17 / R-A Tee to Pipe 1 Grade WP 316 Grade TP 316 to configuration of tee Figures 1.17-1-Sl-31-24S R1.16 10.0" diameter 10.0" diameter 1, 1.17-2, Schedule 140 Schedule 140 *t.17-3, and 1.17-4 Unit 1 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single Sided access due Table 1.18-1, 1.18 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1 .113-1-Sl-31-27F R1.20 Branch 10.0" diameter 10.0" diameter configuration 1, 1.18-2, Connection 1 Schedule 140 1.18-3, and 1.18-4 Unit 1 1 Safety Injection ASTM A-403 ASTM A-403 50% 3 Single Sided access due Table 1.19-1, 1.19 / R-A Elbow to Tee 1 Grade WP 304 Grade WP 304 to configuration of tee Figures 1.19-1-Sl-51-22F R1.20 3.0" diameter 3.0" diameter 1, 1.19-2, Schedule 160 Schedule 160 1.19-3, and 1.19-4

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Material 2 and Examination Examination Limitations Applicable Seq. Number Category Description Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 1 1 Safety Injection ASTM A-403 ASTM A-376 50% 3 Single Sided access due Table 1.20-1, 1.20 I R-A Tee to Pipe 1 Grade WP 304 Grade TP 304 to configuration of tee Figures 1 .20-1-Sl-51-27F R1.20 3.0" diameter 3.0" diameter 1, 1.20-2, Schedule 160 Schedule 160 1.20-3, and 1.20-4 Unit 1 1 Chemical and ASTM A-403 ASTM A-182 50% 3 Single Sided access due Table 1.21-1, 1.21 / R-A Volume Control Grade WP 304 Grade F316 to branch connection Figures 1.21-1-CS-96-60F R1 .11 Elbow to 3.0" diameter 3.0" diameter configuration 1, 1.21-2, Branch Schedule 160 1.21-3, and Connection 1 1.21-4 Unit 2 1 Reactor ASTM A-182 ASTM A-351 50% 3 Single sided access due Figures 1.22-1.22 / R-A Coolant 3-IN Grade F316 Grade CF8M to branch connection 1, 1.22-2 and 2-RC-17-06N R1 .11 Nozzle Branch 3.0" diameter 27.5" inside configuration 1.22-3 Connection 1 diameter Unit 2 1 Reactor ASTM A-182 ASTM A-351 50% UT Single sided access due Figures 1.2~~-

1.23 / R-A Coolant 1-1/2- Grade F316 Grade CF8M Coverage, but to branch connection 1, 1.23-2, 2-RC-17-09N R1.20 IN Nozzle 1.5" diameter 27.5" inside only requires configuration and 1.23-3 Branch diameter a VT-2 per N-Connection 1 716-1 Unit 2 1 Safety Injection ASTM A-376 ASTM A-351 70% 3 Single sided access due Figures 1.24-1.24 / R-A Pipe to Valve 1 Grade TP 316 Grade CF8M to configuration 1, 1.24-2, 2-Sl-63-17 R1 .11/16 6.0" diameter 6.0" diameter and 1.24-3 Schedule 160 Schedule 160 Unit 2 1 Residual Heat ASTM A-182 ASTM A-376 50% 3 Single sided access due Table 1.25-1, 1.25 / R-A Removal Tee Grade F316 Grade TP 316 to configuration Figures 1.25-2-RH-33-01 R1.20 to Pipe 1 14.0" diameter 14.0" diameter 1, 1.25-2, Schedule 160 1.25-3, 1.2fi-4 and 1.25-5 Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 80.56% Limitations due to six Table 1.26-1, 1.26 / 8-A Shell to Lower Gr. B Class 1 Gr. B Class 1 Core Support Pads Figures 1 .26-2-RPV-D 81 .11 Head Thickness 5.38" thick 1, 1.26-2, tapered from 1.26-3 and 8.31" to 5.38" 1.26-4

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and .Material 2 and Examination Examination Limitations Applicable Seq. Number Category Description Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 47.61% Limitations due to Bottom Table 1.27-1, 1.27 / B-A Head Dollar Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.27-2-RPV-E B1 .21 Plate Weld 5.38" thick 5.38" thick Tubes 1, 1.27-2, 1.27-3, 1.27-4 and 1.27-!5 Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 66.30% Limitations due to Bottom Table 1.28-1, 1.28 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1 .28-2-LHM-01 B1.22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.28-2 and Weld at 26 1.28-3 Deg.

Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 83.44% Limitations due to Bottom Table 1.29-1, 1.29 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.29-2-LHM-02 B1.22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.29-2, Weld at 77 1 .29-3, 1 .29-Deg. 4 and 1.29-5 Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 73.09% Limitations due to Bottom Table 1.30-*I, 1.30 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.30-2-LHM-03 B1.22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.30-2, Weld at 129 1.30-3, 1.30-Deg. 4 and 1.30-5 Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 71.03% Limitations due to Bottom Table 1.31-*1, 1.31 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.3*1-2-LHM-04 B1 .22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.31-2 and Weld at 180 1.31-3 Deg.

Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 67.15% Limitations due to Bottom Table 1.32-1, 1.32 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.32-2-LHM-05 B1.22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.32-2 and Weld at 231 1.32-3 Deg.

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Material 2 and Examination Examination Limitations Applicablei Seq. Number Category Description Product Form Product Form Code and Results lf"ables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 83.69% Limitations due to Bottom Table 1.33-*1, 1.33 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.3:~-

2-LHM-06 B1.22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.33-2 and Weld at 283 1.33-3 Deg.

Unit 2 1 RPV Lower ASTM A-533 ASTM A-533 84.46% Limitations due to Bottom Table 1.34-1, 1.34 / B-A Head Gr. B Class 1 Gr. B Class 1 Mounted Instrument Figures 1.34-2-LHM-07 B1 .22 Meridional 5.38" thick 5.38" thick Tubes 1, 1.34-2 and Weld at 334 1.34-3 Deg.

Unit 2 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.35-1, 1.35 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1 .35-2-Sl-58-23 R1.20 Branch 10.0" diameter 10.0" diameter configuration 1, 1.35-2, Connection Schedule 140 1 .35-3, 1.35-4, 1.35-5 and 1.35-6 Unit 2 1 Safety Injection ASTM A-351 ASTM A-403 50% 3 Single sided access due Table 1.36-1, 1.36 / R-A Valve to Elbow Grade CFS Grade WP 316 to valve configuration Figures 1.36-2-Sl-59-24 R1.20 10.0" diameter 10.0" diameter 1, 1.36-2, Schedule 140 Schedule 140 1.36-3, 1.36-4, 1.36-5 and 1.36-6 Unit 2 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.37-1, 1.37 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1.37-2-Sl-59-25 R1.20 Branch 10.0" diameter 10.0" diameter configuration 1, 1.37-2, Connection Schedule 140 1.37-3, 1.37-4, 1.37-5 and 1.37-6

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Material 2 and Examination Examination Limitations Applicablei Seq. Number Category Description Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 2 1 Safety Injection ASME SA-351 ASTM A-403 50% 3 Single sided access due Table 1.38-*1, 1.38 / R-A Valve to Elbow Grade CF8M Grade WP 316 to valve configuration Figures 1.38-2-Sl-60-31 R1.20 6.0" diameter Schedule 160 1, 1.38-2, Schedule 160 6.0" diameter 1.38-3, 1.3a-4, 1.38-5 and 1.38-6 Unit 2 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.39-1, 1.39 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1.39-2-Sl-60-32 R1.20 Branch 6.0" diameter 6.0" diameter configuration 1, 1.39-2, Connection Schedule 160 1.39-3, 1.39-4, 1.39-5 and 1.39-6 Unit 2 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.40-1, 1.40 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1.40-2-Sl-61-15 R1.20 Branch 6.0" diameter 6.0" diameter configuration 1, 1.40-2, Connection Schedule 160 1.40-3, 1.40-4, 1.40-5 and 1.40-6 Unit 2 1 Safety Injection ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.41-1 ,

1.41 / R-A Elbow to Grade WP 316 Grade F316 to branch connection Figures 1.41-2-Sl-62-32 R1.20 Branch 6.0" diameter 6.0" diameter configuration 1, 1.41-2, Connection Schedule 160 1.41-3, 1.4'1-4, 1.41-5 and 1.41-6 Unit 2 1 Chemical and ASTM A-403 ASTM A-182 50% 3 Single sided access due Table 1.42-1, 1.42 / R-A Volume Control Grade WP 304 Grade F316 to branch connection Figures 1.4:2-2-CS-120-13 R1 .11 Elbow to 3.0" diameter 3.0" diameter configuration 1, 1.42-2, Branch Schedule 160 1.42-3, 1.42-Connection 4, 1.42-5, 1.42-6 and 1.42-7

TABLE 1 - CNP UNITS 1 AND 2 WELDS WITH LIMITED EXAMINATIONS Unit Class, Weld Material 1 and Materi.al 2 and Examination Examination Limitations Applicable Seq. Number Cat~gory Description Product Form Product Form Code and Results Tables and

/Weld and Item Coverage Figures Identification No. Obtained 2 Number Unit 2 1 Pressurizer1 SA-508 Class SA-533 Grade 65.2% Single sided access due Table 1.43-*1, 1.43 / B-D Lower Head 2 Mn-Mo A (Class 2) to the nozzle-to-head Figures 1.4:3-14"-2-RC-21 B3.110 Surge Nozzle- 14.0" diameter 3.0" thick configuration and 1, 1.43-2, to-Vessel Weld Schedule 160 adjacent heater sleeves 1.43-3 and 1.43-4 Unit 1 1 Pressurizer SA-216 Grade SA-516 Grade 88.2% Portion of weld Figures 1.44-1.44 / B-K Lower Head to wee 70 inaccessible due to 1, 1.44-2 and 1-PRZ-26 B10.10 Support Skirt 1.5" thick 1.5" thick adjacent duct 1.44-3 Weld NOTES: 1. Containment RCS Leakage Detection Applies

2. Ultrasonic (UT) Examination, Phased Array UT Examination (PAUT) and Surface Examination by Liquid Penetrant (PT) or Magnetic Particle (MT).
3. Acceptable limitation per Evaluation of Change in Risk for N-716-1.

1.1 Weld 4"-2-RC Pressurizer Upper Head Spray Nozzle-to-Vessel Weld Weld 4"-2-RC-28 was UT examined in Inspection Period 2 during the U2C21 refueling outage in 2013. The NOE data came from UT Report No. U2-VE-13-009. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-?(b). The corresponding CRV as shown on that Figure is A-B-C-D-E-F-G-H. The UT examination was limited by the configuration of the Nozzle-to-Shell resulting in total UT coverage of 83.3% as described in Figure 1.1-2. A photograph of weld 4"-2-RC-28 is provided in Figure 1.1-3.

No recordable indications were detected during this scan.

Section XI Appendices and Supplements used for this UT examination were Appendix I and Article 4 of ASME Section V.

Note: No laminations were reported on the Pressurizer Head that could interfere with the angle beam examinations performed on Weld 4"-2-RC-28.

1.1 Weld 4"-2-RC Pressurizer Upper Head Spray Nozzle-to-Vessel Weld

  • -2* *2
  • UL[

1*Pfi7*15 (N-~) .( *Z* -2 *NOZ2lf 2-m-21 -stl (IRS)

(I~)

  • 45' 2-PllZ* tll
  • *27*ti At 2-~z- 2,. Ct** st)

~RS) 2-wz-1J nus* tr- 2-AC* 25* Nonl.£

~- Pfi7 *12 (>>-'x)

  • 1:tl'.l" 2*PR2*17 ~ ,_ f

--0'-*VI iO Y,t:LD * /. q_ l..040 'MID (IRS)

M~Z-20 -' 2' o*"""'"ct ***r I D. C. COOK, UNIT 2 FIG . A* -4 PRCS9JRl2E Figure 1.1-1 Weld 4" RC-28 (Extracted from Reference DRAWING 2A-4)

1.1 Weld 4"-2-RC Pressurizer Upper Head Spray Nozzle-to-Vessel Weld pra 0 d Figure 1.1-2 Weld 4"-2-RC-28 Scan Coverage and Scan Summary

Figure 1.1-3 Weld 4"-2-RC-28 Component Photograph 1.2 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Weld 6"-2-RC-22 was UT examined in Inspection Period 1, during the U2C20 refueling outage in 2012. The NOE data came from UT Report No. U2-VE-12-004. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-?(b). The correspond ing CRV as shown on that Figure is A-8-C-D-E-F-G-H . The UT examination was limited by the configuration of the nozzle to head resulting in total UT coverage of 86.7% as described in Figure 1.2-3. A photograph of weld 6"-2-RC-22 is provided in Figure 1.2-4.

One previously recordable indication was identified using the 45° Shear wave 2.25 Mhz.

transducer during this examination. Follow up scans using the 45° Shear wave 5.0 Mhz.

transducer were performed . This indication was evaluated as acceptable per Table IWB-3512-1 (Figure 1.2-2).

Section XI Appendices and Supplements used for th is UT examination were Appendix I and Article 4 of ASME Section V.

Note: No laminations were reported on the Pressurizer Head that could interfere with the angle beam examinations performed on weld 6"-2-RC-22 .

1.2 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld L O 1,IUD QFrl tl ~ID P05111,::,. P()9T I (f'ROlil rf REr P-C1WT}

  • 2- me .( -~- -2 *NDZZlf 7*P"7*7S (~-~)

2-wz-21 *SEl

{IR )

(110)

  • 45' 2*PRZ* I 2* ffiZ* 1-4 4:10.15"' **2* *27*NOZAE 2-~z. 2-4 (ti-SE)

~F?S) 2* FPZ* 1.J 321. 25' tr- 2* AC* 2S*N02'2l(

'J*Pfi7*72 (W-5£)

  • 120° 2*PR2*17 *,. f Lmo

-0'-*

MID

  • ,. G. u::<<O ~ID (IRS)

-~2-11 25' Z-~Z-20 -'2' Q"

._____.,, s1.~a:

stEtlitbct e~*1 Lit< , ..-.1-Rc-11

  • I rtomc 2-P~l-?6 ('x-N)

D. C. COOK, UNIT 2 FIG. A*_. PRCS9JRl2ER Figure 1.2-1 Weld 6" RC-22 (Extracted from Reference DRAWING 2A-4)

Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld 11

  • I ll Figure 1.2-2 Weld 6"-2-RC-22 Indication #1 (Table IWB-3512-1 Calculation)

1.2 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld entwith 5'° and 00° transdurer I

\

/

ozzle

/ Head

_ _ _ _ _ ___:__,__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 0.19" Gad Limited examination:

Single sided access due to nozzle to head configuration 86.7% Code Required Volume Achieved.

11.87 ~ - in. 10.30 &J . in.

Coo quired Volwre Area canned by 45° d6 C 10.30/ ] I. 71' 100- 86. 7% Scale 2:1 F igure 1.2-3 Weld 6"-2-RC-22 Examination Location and Coverage Map

1.2 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Figure 1.2-4 Weld 6"-2-RC-22 Component Photograph

1.3 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Weld 6"-2-RC-25 was UT examined in Inspection Period 1, during the U2C20 refueling outage in 2012. The NOE data came from UT Report No. U2-VE-12-005. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

?(b ). The corresponding CRV as shown on that Figure is A-B-C-O-E-F-G-H. The UT examination was limited by the configuration of the nozzle to head resulting in total UT coverage of 86.7% as described in Figure 1.3-4. A photograph of weld 6"-2-RC-25 is provided in Figure 1.3-5.

One previously recordable indication was detected with the 45° and 60° Shear wave 2.25 Mhz.

transducers during this examination . A second indication was detected using the 60° Shear wave 2.25 Mhz. transducer. A follow up scan using a 45° and 60° 5.0 Mhz. transducers were used in the area of the indications. Both of these indications were found acceptable per Table IWB-3512-1 (Figures 1.3-2 and 1.3-3).

Section XI Appendices and Supplements used for this UT examination were Appendix I and Article 4 of Section V.

Note: No laminations were reported on the Pressurizer Head that could interfere with the angle beam examinations performed on weld 6"-2-RC-25 .

1.3 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld

  • 22* 22L[ ..( -~- - e.-NOZZL(

2-P~*25 (N*'x) 2-m-21 -SEl (IRS) (IRS)

-!5' 2-P~Z-19

"*2* *2H aE 2-~Z-2~ (~*SE)

~RS) 2-WZ-1.3 321. 25° e*-2-AC* S*NOTIH 1-Pfi'I -11 (IJ-'x)

{IRS)

--0' - *

  • 170' 2*P82*17
  • PR2*11 S' 2*PR2 *20 -'2° o* REEmNct PONT I D. C. COOK, UNIT 2 FIG. A* 4 PR£S9JRIZER Figure 1.3-1 Weld 6" RC-25 (Extracted from Reference DRAWING 2A-4)

1.3 Weld 6" RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld

\I Figure 1.3-2 Weld 6"-2-RC-25 Indication #1 (Table IWB-3512-1 Calculation)

Weld 6" RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld 1

I "

W l:LD INUIU\TION Weld 6' 2*RC*2S lndrcauon r,2 (Go* s.o Ml IZ)

CODC CRITCRIA ASME D&.PV; Sect*on ><I, 2004 e dition IW 0-3512 ROUN DED A I\ VALU

  • ITEM VALUE Of Uft<I) l.Uf\/1~*, -.-i *S CO:.: ;-: :=.T/WELD APPUCA0LC DIMENSIONS Thlckooss 2.11" A~ 11tc*~ *11cd bv UT Cl.iddms llf ao11lleaMe) 0.1!}* iNomlnal per drawing Thickness to use for calculations of l 2.21 *

- 2.2

  • Thlclmc~
  • Oaddlng FLAW C11MAcn: ntz/\TION Flaw minimum ck!oth fro1111 OD 1 78 fl.'lW moxlmum deolh from 00 t..86 Fl.aw throuah-Y1all deoth 11 2a or 2d 0.08 IClo~t'st distance of fl aw lo either surlMI! " s 035 O,otb U1od to dtlotm.Jn If fl Wk rf IO.lld 0.032 ~~\S subsurfilcl!

°'

ISurtace or Subsurface SubSurf.ice Ifs IS < 0.4d t h8 Raw *~ ~w-r.ice, ir ,urr ilCC, a ., :.!d + s, Calcula ted a O.O ll If Subsutfac~. a " 1/2 of 2a or 2d Flaw sta1t l1 38. 75 11.iwstoo U 39.~5 r law 1enst h = t 0.5 ASPECT RATIO & A/TW. DET£RMINATION

!Aspect RatiO, -.it. 0.08 If 'J/f,, >0,5 USI! 0.5

!:\A% lo/t* 1001 l 81'4 1.8%

Surface proximity value v (s/a) 8.7!> V> 1.0, use V 1.0 LINU.n INTERPOLATION [It nee ded)

Lesser asot>ct ratio alt. 0.05 Grcalcr Ml'l~t ratio a/'t 0.1 Lesser o/l% .3.8%

Greater a/l'6 439' Greater alt.

  • IM~1 o/e = A 005 ill&
  • le~er a/t, = 8 0 .03 Greater a/t%
  • lcsrer a/l'6 C o.s IBx C) / A
  • v,ilue to add to Lesser a/t9' 0.3 lnterPoh1ted aft" 4. 1" RESULTS Ta: ,le IWD-3 512* 1 acceinonoo limits Sutfot:* Suhtur faco IMDC<:l H-JUO = 0.08 N/A 4.1" V*1.0 I t rpol2_ted N/A NII\

,ru:lual all% N/A 1.a% llttep tul)le to Tobie IW8-3Sl2-l

eo1nnlC11ts
FJaw measurements oot31ncd w1ih6Crs.O MHl., Shear wove tr.'.tn$ducer.

Ev.iluatlon Performed By. T.G c,rraher ~{U- (-ol ,

Level: Ul Oate: 1)1../ lo'll,?.

Rcvk:wod: E. L. McClain c /. ?111(" ..:.-- Lovcl: Ill 0.1 1 : q./-.;,_/j '7

' I I Figure 1.3-3 Weld 6" RC-25 Indication #2 (Table IWB-3512-1 Calculation)

1.3 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Maximum e ent with 45° an:16J 0 transducers I

/

I Nazzle I Head I

I

- - - - - - ~ ~ - - -- - -- - - - - - -- - - -- 0.19"Oad imited examination:

Single sided access due to nozzle to head configuration 86.7% Code Require Volume Achieved.

11.87 Sl- in. 1030 &I-in.

Cooe P.equired Vol urre Area scannul by 4s-' and6 °

10. 0/ll. 7'1 0 = 86.7% Scale 2:1 Figure 1.3-4 Weld 6"-2-RC-25 Examination Location and Coverage Map

Figure 1.3-5 Weld 6"-2-RC-25 Component Photograph 1.4 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Weld 6"-2-RC-26 was UT examined in Inspection Period 1, during the U2C20 refueling outage in 2012. The NOE data came from UT Report No. U2-VE-12-006 . Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

?(b ). The corresponding CRV as shown on that Figure is A-B-C-D-E-F-G-H. The UT examination was limited by the configuration of the nozzle to head resulting in total UT coverage of 86. 7% as described in Figure 1.4-2. A photograph of weld 6"-2-RC-26 is provided in Figure 1.4-3.

There were no recordable indications identified during this examination .

Section XI Appendices and Supplements used for this UT examination were Appendix 1 and Article 4 of Section V.

Note: No laminations were reported on the Pressurizer Head that could interfere with the angle beam examinations performed on weld 6"-2-RC-26 .

1.4 Weld 6"-2-RC Pressurizer U er Head Relief Nozzle-to-Vessel Weld Lena Yi£Lt>

POSI llttf

    • 2*
  • 2* 22l[
,.p117.
;,5 (~-~) .( -~- -2 *NOZZlf 2-wz-21 *SEl (IRS)

(Un)

  • 45' 2*P11Z* 1

'*2* *27*NOW.. E 2-~Z* 2~ (t.* SE)

~RS) 2* PPZ* 1J 321. 25"

~-- 2* RC* 25-rt012l(

1*Pfl7* 2 (t.1-'x )

w

  • 120' 2*PR2*11 * ,_ f LCNO

--01-*

Ytt:LD

  • q_ LCNO ¥1tlD

{IRS)

  • PR2-11 25' Z*PR2*20 ~2' o* """"ct eoOT I D. C. COOK, UNIT 2 FIG. A- -4 PRCS9JRIZE Figure 1.4-1 Weld 6" RC-26 (Extracted from Reference DRAWING 2A-4)

1.4 Weld 6" RC Pressurizer U er Head Relief Nozzle-to-Vessel Weld Maxim.Im extent w ith

-l-- 45° and (:IJ 0 transducers I

I I

Nozzl I Head I

/ _ __ _ _ __ __ _ _ __ _ _ __ 0.19" Gad limited examination:

Single sided access due to nozzle to head configuration

86. 7% Code Required Volume Achieved.

1187 ~ . in. J0.30 sq. i n.

Oxie Requi red olwre A Clnmxl by 4 and60° 10.3 /11.8~100== 8 .7% Scale 2:1 Figure 1.4-2 Weld 6"-2-RC-26 Examination Location & Coverage Map

Figure 1.4-3 Weld 6"-2-RC-26 Component Photograph 1.5 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Weld 6"-2-RC-27 was UT examined in Inspection Period 1, during the U2C20 refueling outage in 2012. The NDE data came from UT Report No. U2-VE-12-007. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-

?(b). The corresponding CRV as shown on that Figure is A-8-C-D-E-F-G-H . The UT examination was limited by the configuration of the nozzle to head resulting in total UT coverage of 86.7% as described in Figure 1.5-2. A photograph of weld 6"-2-RC-27 is provided in Figure 1.5-3.

No recordable indications were detected during the examination .

Section XI Appendices and Supplements used for this UT examination were Appendix I and Article 4 from Section V.

Note: No laminations were reported on the Pressurizer Head that could interfere with the angle beam examinations performed on weld 6"-2-RC-27.

1.5 Weld 6"-2-RC Pressurizer U er Head Relief Nozzle-to-Vessel Weld LCNO Yt{LI>

P05111~

    • 2*
  • 22* til2ll[ .( -~- -2~*NOZ2LC
?*Pfl?*:?S (._,.~ )

2-m-21 (> -SEl (IRS)

(I~)

  • 45' 2*Pl?Z* 19
    • 2*
  • 27-tiOZ~E 2-~Z- 2' (N-SE )

~RS)

,...,. 2* Pfi'Z- 18 2- FPZ-1J m .2s* ......._ o*-2* AC* 25-Nont[

  • 2 * ~2ZLE 1*Pfl7 *:?1 (>>-'x )
  • 120' 2*PR2*17 1*Pll7* 3 (._,.~ )

(IR5}

-0'-* (IRS)

+6()* 2- l'fi'Z- 16 2*PR2 *20 -'2*

    • 8£E[R[hct Pl>NJ I D, C. COOK, UNIT 2 FIG. A*
  • PR(S9JRIZE Figure 1.5-1 Weld 6" RC-27 (Extracted from Reference DRAWING 2A-4)

1.5 Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Ma.xinum extent with

- - - - 45° and (i) 0 transducers I'

I ozzle I Head

_ _ _ _ _ __,__..__ __ _ _ __ _ _ __ __ _ _ _0.19" Gad Limited examination:

Single sided access due to nozzle to head configuration 86.7% Code Required Volume Achieved.

11.87 sq. in. I0.30 sq. in.

Ccxl ?.equired Vol une Area scanned by 45° and60° I0.30/ 11.8?-' l00-86.7% Scale 2:1 Figure 1.5-2 Weld 6" RC-27 Examination Location & Coverage Map

Weld 6"-2-RC Pressurizer Upper Head Relief Nozzle-to-Vessel Weld Figure 1.5-3 Weld 6"-2-RC-27 Component Photograph

1.6 Weld STM-21-FWN - Steam Generator Feedwater Nozzle-to-Vessel Weld Weld STM-21-FWN was UT examined in Inspection Period 2, during the U2C23 refueling outage in 2016. The NOE data came from UT Report No. U2-VE-16-013. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWC-2500-4(a). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to non-removable insulation support ring and configuration . The examination resulted in total UT coverage of 76.3% as described in Figure 1.6-2. A photograph of weld STM-21-FWN is provided in Figure 1.6-3.

No recordable indications were detected during this examination .

Section XI Appendices and Supplements used for this UT examination were Appendix I and Article 4 from Section V.

Note: No laminations were reported on the shell that could interfere with the angle beam examinations performed on weld STM-21-FWN.

1.6 Weld STM-21-FWN - Steam Generator Feedwater Nozzle-to-Vessel Weld HJ- Zl- 1 SH[ll !:c:Cfl 4MNAY I

c; IJ  :<- - -

I y

P, AN\M l 270' S Tl.i1 r,

z H LL en I

1- I-z

~

s

\.tANWAY

- 2 1-LL.

~ltJ-21-0 I 0

0 0

Figure 1.6-1 Weld STM-21-FWN (Extracted from Reference DRAWING 2B-1)

1.6 Weld STM-21-FWN - Steam Generator Feedwater Nozzle-to-Vessel Weld

'IIM ANGLE EXAM AREA 3/4COVERAGE 0 BOTH 100 45 cw 100 45 C 100 45 u 0 45 D 94.5 60 C 100 60 100 60 0 6 92 TOTAL 686.5 109,25 to I le g o Yield 686.5 I 900 = 76.3%

60 DEG COVERAGE OS SIDE~ OIREC O

  • 100.25 / 109.25
  • 92%

0 d gr  : clrc c ~ 100% i NSU T IIINO 45 a 60 deg us s de 0% ~l"'1 Figure 1.6-2 Weld STM-21-FWN Coverage Calculation

1.6 Weld STM-21-FWN - Steam Generator Feedwater Nozzle-to-Vessel Weld S FW irn' tio du to norwe ova l ins la i n up ort ring and Figure 1.6-3 Weld STM-21-FWN Component Photograph

1.7 Weld 1-RC-9-03S- Reactor Coolant Pipe to Elbow Weld 1-RC-9-03S was UT examined in Inspection Period 1, during the U1 C25 refueling outage in 2013. The NDE data came from UT Report No. U1-VE-13-007. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT exam ination was limited due to an adjacent weld . The examination resulted in total UT coverage of 85.1 % as described in with Figure 1.7-2. A photograph of weld 1-RC-9-03S is provided in Figure 1.7-3.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Request for Alternative ISIR-4-01 (Code Case N-716) as approved by the Nuclear Regulatory Commission (NRC) under the Safety Evaluation in ADAMS Accession No. ML072620553.

The exam ination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.7 Weld 1-RC-9-03S - Reactor Coolant Pipe to Elbow 1* " I I

( . r,'

s s r

  • D C. FIG Figure 1.7-1 Weld 1-RC-9-03S (Extracted from Reference DRAWING A-25)

Weld 1-RC-9-03S - Reactor Coolant Pipe to Elbow

. 19 776 .7 p

[

Figure 1.7-2 Weld 1-RC-9-03S Coverage Calculation

Weld 1-RC-9-03S - Reactor Coolant Pi e to Elbow Figure 1.7-3 Weld 1-RC-9-03S Component Photograph

1.8 Weld 1-SI-33-26F - Safety Injection Elbow to Branch Connection Weld 1-Sl-33-26F was UT examined in Inspection Period 1, during the U1 C24 refueling outage in 2011. The NOE data came from UT Report No. 1C24_UT05. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the geometric configuration of the branch connection. The examination resulted in total UT coverage of 50.0% as described in Figure 1.8-2. A photograph of weld 1-Sl-33-26F is provided in Figure 1.8-3.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Request for Alternative ISIR-4-01 (Code Case N-716) as approved by the Nuclear Regulatory Commission (NRC) under the Safety Evaluation in ADAMS Accession No. ML072620553.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.8 Weld 1-Sl-33-26F - Safety Injection Elbow to Branch Connection I r 1 ) 1

  • I Sl-10 r

Figure 1.8-1 Weld 1-Sl-33-26F (Extracted from Reference DRAWING A-55)

1.8 Weld 1-Sl-33-26F - Safety Injection Elbow to Branch Connection CODE REQUIRED COVERAGE ACI-IIEVEO: !Of,{,

limited o Ilg! Side ccess y due o Blanch Conn *on Configura * }

0. I sq. in. ( o/c AREA OF INTERROGATlON: 100%

02~.inlOo/

Not to Scale Figure 1.8-2 Weld 1-Sl-33-26F Coverage Calculation

1.8 Weld 1-Sl-33-26F - Safety Injection Elbow to Branch Connection f-S 26F Figure 1.8-3 Weld 1-Sl-33-26F Component Photograph

1.9 Weld 1-RH-29-01F - Residual Heat Removal Branch Connection to Pipe Weld 1-RH-29-01 F was UT exam ined in Inspection Period 1, during the U1 C24 refueling outage in 2011 . The NOE data came from UT Report No. 1C24_UT03. Previous ISi UT data was reviewed .

The UT Code Requ ired Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT exam ination was limited due to the geometric configuration of the branch connection . The examination resulted in total UT coverage of 50.0% as described in Figure 1.9-2. A photograph of weld 1-RH-29-01 F is provided in Figure 1.9-3.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Request for Alternative ISIR-4-01 (Code Case N-716) as approved by the Nuclear Regulatory Commission (NRC) under the Safety Evaluation in ADAMS Accession No. ML072620553.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.9 Weld 1-RH-29-01F - Residual Heat Removal Branch Connection to Pipe Figure 1.9-1 Weld 1-RH-29-01F (Extracted from Reference DRAWING A-81)

1.9 Weld 1-RH-29-01F - Residual Heat Removal Branch Connection to Pipe

/

D CODE REQUIRED COVERAGE ACHIEVED : 50%

(E a i ation Ii i ed to Sing Con lo

(

AREA OF INTERROGATION : 100%

I %

Figure 1.9-2 Weld 1-RH-29-01F Coverage Calculation

1.9 Weld 1-RH-29-01 F - Residual Heat Removal Branch Connection to Pipe Figure 1.9-3 Weld 1-RH-29-01 F Component Photograph

1.10 Weld 1-RC-1-11N - Chemical and Volume Control Nozzle Branch Connection Weld 1-RC-1-11 N was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-017. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-B(c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the geometric configuration of the branch connection. The examination resulted in total UT coverage of 50.0% as described in Figures 1.10-2, 1.10-3, and Table 1.10-1. A photograph of weld 1-RC-1-11 N is provided in Figure 1.10-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.10 Weld 1-RC-1-11 N - Chemical and Volume Control Nozzle Branch Connection 1- * -

1- Q- 54 ,<

1-1/r Figure 1.10-1 Weld 1-RC-1-11N (Extracted from Reference DRAWING A-9)

1.10 Weld - - - -

  • onnection p
  • I SS L 1 P1 I
  • Flow pstr am Vol m Achi v d
  • I * ,

I oop 1-' 1 m I

i

' *** ** ,. Flow Volum uir Figure 1.10-2 Weld 1-RC-1-11N Coverage Calculation

1.10 Weld 1-RC-1-11N - Chemical and Volume Control Nozzle Branch Connection I Ii

' Flow t'u~I

  • IA ,p 11 pi 10 II

' C Down tr am Volum R ulred Figure 1.10-3 Weld 1-RC-1-11 N Coverage Calculation

1.10 Weld 1-RC-1-11N - Chemical and Volume Control Nozzle Branch Connection Table 1.10-1 Weld 1-RC-1-11N Coverage Calculation Results

Figure 1.10-4 Weld 1-RC-1-11N Component Photograph 1.11 Weld 1-RC-1-14N - Reactor Coolant Nozzle Branch Connection Weld 1-RC-1-14N was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-018. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8(c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the geometric configuration of the branch connection . The examination resulted in total UT coverage of 50.0% as described in Figures 1.11-2, 1.11-3, and Table 1.11-1 . A photograph of weld 1-RC-1-14N is provided in Figure 1.11-4.

No recordable indications were detected during this examination.

The ultrasonic exam ination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.11 Weld 1-RC-1-14N - Reactor Coolant Nozzle Branch Connection

/ RfACT

/ COOlml PUPJP NO. t 1-CS-96 NlR-210

r ,<

\

TWP ElEUEtH LIN£ NO t- RC- t (C O LEG) a* 270" t.lAlERIAL 27.5' ID NO~ THt<.

5C'HE0UL£ CAL BLK LOCATIOl'I REF . DRAWINC: e 1-Rl'-I D. C. COOK, UNIT FIG. A-~ R[,.C'TO , C NfT SVSTEW FLOW OIACF?AM. 1-2-5128 Figure 1.11-1 Weld 1-RC-1-14N (Extracted from Reference DRAWING A-9)

1.11 Weld 1-RC-1-14N - Reactor Coolant Nozzle Branch Connection

~ 0 U ~ITT

.2.7 Flow C sl

  • pPi m*

OJ! In I nh 010_

0111 I.I i ti i

7 '

==--::-:z..._

Flow Up tre m Volum Requited Figure 1.11-2 Weld 1-RC-1-14N Coverage Calculation

I ,

27 Flow wn tr m V lum A hi v d 0

-=~ j 7

qui Figure 1.11-3 Weld 1-RC-1-14N Coverage Calculation L

1.11 Weld 1-RC-1-14N - Reactor Coolant Nozzle Branch Connection Table 1.11-1 Weld 1-RC-1-14N Coverage Calculation Results

t 0 Figure 1.11-4 Weld 1-RC-1-14N Component Photograph

1.12 Weld 1-RC-11-125- Reactor Coolant Elbow to Pipe Weld 1-RC-11-12S was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-020. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-S(c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to an adjacent non-removable clamp . The examination resulted in total UT coverage of 50.0% as described in Figures 1.12-2, 1.12-3, and Table 1.12-1. A photograph of weld 1-RC-11-12S is provided in Figure 1.12-4.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50 .55a(b)(2)(xv).

1.12 Weld 1-RC-11-12S- Reactor Coolant Elbow to Pipe 1-GRC- R-503 16S Nl -163 24F TE P Elf \(REF.)

1-CRC-R-S24 \.

065 t-CRC-R-500 ~

1-RC-12 07$ f'IC. A-29 Q I 115 EL. 61 I' 1 I

1-G C-R- 502

\

~-

3, 4 1-RC-501 (Bf)'\ .... .,,.... ~

REF. ~:

\

~

...._ EL.616' 1- -10 LINE NO 1-RC-1 1 FIG. -26 O1F t----- ----"(21-11r 1.0.

1-RC-3 S5 COLD LEC LOOP 3 SCHEDULE REF. DR NG: >.CP 1-RC-1 1 D. C. COOK , UNIT 1 FIG . A- RE ACl O COOI..A l S't5T[ l FLO 01 CR 1-5128 Figure 1.12-1 Weld 1-RC-11-12S (Extracted from Reference DRAWING A-28)

l_ I Pipe '

Elbow Flow Downs ream Volume Acti*eved Pipe

' l lbow Flow nstre m Volum equir d Figure 1.12-2 Weld 1-RC-11-12S Coverage Calculation

1.12 Weld 1-RC-11-12S- Reactor Coolant Elbow to Pipe Pipe J lbow Flow Up tr m Volum A IPV d Figure 1.12-3 Weld 1-RC-11-12S Coverage Calculation

1.12 Weld 1-RC-11-125 - Reactor Coolant Elbow to Pipe Table 1.12-1 Weld 1-RC-11-125 Coverage Calculation Results

1.12 Weld 1-RC-11-12S - Reactor Coolant Elbow to Pipe Compon n P oto Figure 1.12-4 Weld 1-RC-11-12S Component Photograph

1.13 Weld 1-SI-29-20S- Safety Injection Elbow to Tee Weld 1-Sl-29-20S was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-044. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the tee . The examination resulted in total UT coverage of 61 .45% as described in Figures 1.13-2, 1.13-3, and Table 1.13-1. A photograph of weld 1-Sl-29-20S is provided in Figure 1.13-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b )(2)(xv).

1.13 Weld 1-SI-29-20S - Safety Injection Elbow to Tee 1.

")..,

16S ,,, EL. 622 "

14F 15N I()"

175 135 1- Sl-29 6"

1 1-Sl-29 1-S1-68 12S EL. 608' O9S z. 34* NNULUS RESTRAINT co m s DOWN- l o* CPS- 3 I -GSI-R-550 STREAM SIDE OF .____ _. l-Sl- O3S-HL 1

/ELD 08F ~ -- -__,__ _ _ _ 29_ __ --+-I._..-+-- -----i------ ~ (1.25" )

O7S 06F 05F EL. 6 16' 3/ 4"/ . . , ....

' RESTRAINT COVERS UPSTREAM SIDE OF WELD ~ -0~2N __ 1.=-f~:~1 10*

S1-1 66-L1 OSF I - Sl- 28

~_t _ _ _5_1_ CN_l_OX_X

  • 2 I0F1 l 1-s 1-2a LINE NO. 1-S1-29 I-S1-68 1-S1-28 27-1 / 2" I.D. MATERIAL ss ss 1-RC-1 10* 0

'0.M. DIA COLD LEG LOO P 1 NOM. THK. 1.312" 0.7 18""

SCHED ULE 140 160 CAL. ELK. 33 8030 33 8028 LOCATION REF. DRAWING: 'EP 1-51-29 D. C. COOK, IT 1 FIG. - 53 FETY INJECTION SYST811 FLO If DIAGRAM: 1-5 143 Figure 1.13-1 Weld 1-SI-29-20S (Extracted from Reference DRAWING A-53)

1.13 Weld 1-SI-29-20S - Safety Injection Elbow to Tee lb I

lI I low Upstre m V lum A Elb l) low R fr Figure 1.13-2 Weld 1-SI-29-20S Coverage Calculation

1.13 Weld 1-SI-29-20S- Safety Injection Elbow to Tee T

lbow low wn tr mV tu

/

- -- - ~- -----..--/ Te Elbow low D ns V lum R ulr Figure 1.13-3 Weld 1-SI-29-20S Coverage Calculation

1.13 Weld 1-SI-29-20S- Safety Injection Elbow to Tee Table 1.13-1 Weld 1-SI-29-20S Coverage Calculation Results

1.13 Weld 1-SI-29-20S- Safety Injection Elbow to Tee 0

Figure 1.13-4 Weld 1-SI-29-20S Component Photograph

1.14 Weld 1-SI-29-23S- Safety Injection Tee to Pipe Weld 1-Sl-29-23S was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-045. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the tee . The examination resulted in total UT coverage of 50.0% as described in Figures 1.14-2, 1.14-3, and Table 1.14-1. A photograph of weld 1-Sl 23S in provided in Figure 1.14-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50 .55a(b)(2)(xv).

1.14 Weld 1-SI-29-23S- Safety Injection Tee to Pipe 16S 14F EL. 622 '

15N 10-

,o- 6" 17S 1-Sl-29 1.35 12S 1-S1-29 1-S1 - 68 EL.608' 09S AZ . .34' NNULUS RE'STRAINT COVERS DOWN-

  • CPS-3 1-GSI-R-550 STREAM SIDE OF ._________. 10 F 03S- HL

'/ELD 08 F ~ ---+--+-+--1_-_S_l-_29_ __ -+-<.__ _ -----+----- 04 7'-lri ( 1.25" )

0 06F O5F EL. 616' 03S 3/ 4"/ ..

1 RESTRAlflfT COVERS UPSTREAM SID E OF WELD ~-+--0--, 2N __l~r;~~

10*

1-1 66-L 1 OSF 1-S1-28

~ -1_ _ _~51-'C_N_l0_X_X

  • 2 lOF1 l 1-s1-2a LINE N O. 1-S1-29 1-S1-68 1-S1-28 2 -1 1 2* 1.0. MATERIAL ss ss 1-RC-1 10" 6" NOM. DIA COLD LEG LOOP 1 NOM. THK. 1..312* o. ,a**

SCHEDULE 140 160 CAL. ELK. 33 8030 33 8028 LOCATION REF. DRAWIN G: AEP 1-S1-29 D. C. COOK, IT 1 FIG. -53 AFETY INJECTION SYSTEM FLOW DIAGRAM: 1- 5143 Figure 1.14-1 Weld 1-SI-29-23S (Extracted from Reference DRAWING A-53)

1.14 Weld 1-5I-29-23S- Safet In*ection Tee to Pi e PHA ARRAY ULTR NT Pl

- - lw Up tr V tum A hi V d Pl e low Upstr m Volu R qulr d Figure 1.14-2 Weld 1-5I-29-23S Coverage Calculation

1.14 Weld 1-Sl-29-23S- Safety Injection Tee to Pipe Pi

---low V lu Ah v d ip low Down V lum R urr Figure 1.14-3 Weld 1-SI-29-23S Coverage Calculation

1.14 Weld 1-51-29-235- Safety Injection Tee to Pipe 8

Table 1.14-1 Weld 1-5I-29-23S Coverage Calculation Results

r Figure 1.14-4 Weld 1-SI-29-23S Component Photograph

1.15 Weld 1-SI-29-26F Safety Injection Elbow to Branch Connection Weld 1-Sl-29-26F was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-046. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the tee . The examination resulted in total UT coverage of 50.0% as described in Figures 1.15-2, 1.15-3, and Table 1.15-1. A photograph of weld 1-Sl 26F is provided in Figure 1.15-4.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.15 Weld 1-Sl-29-26F Safety Injection Elbow to Branch Connection 16S 14F EL. 622' 15N 1()"

17S 13S 1-Sl -29

... I _,

Hf i 6" 12S 1- S1-29 I 1-S1-68 I

I I

I EL.608 '

I 09S AZ. 34*

I NNULUS I

10" X oi RESTRAINT CO ERS DOWN-

  • CPS-3 1-GSI-R-550 RED. I 10 STREAM SIDE OF F 03S-HL

','ELD 08 F ~---+-~--1_-_S_l-_ 29_ __ _ 04

__,f--t-- -----+-----+-+-117 ( 1.25* )

21 ~ I EL. 6 16' 035 3/ 4'/_..

1 l~r~~~

RESTRAINT COVERS UPSTREAM SIDE OF WELD .----+-- 02-,N __

1 o*

S1-166-L 1 OSF 1-S1-28

$ 1

---+------10Fi 2

51CN 10 XX l 1- s 1-2a LINE N O. 1- S1 - 29 I-S1-68 1-S1-28 27-1 / 2* I.D. MATERIAL ss ss 1-RC-1 10* 6" NOM. DIA COLD LEG LOOP 1 ,VOM. THK 1.312" 0.718"

SCHEDULE 140 160 CAL. ELK. 33 8030 33 8028 LOCATION REF. DRAWIN G: '.EP 1-S1-29 D. C. COOK, FIG. -53 ~FETY INJECTION SYSTOI(

FLOW DIAGRAM: 1-5 143 Figure 1.15-1 Weld 1-Sl-29-26F (Extracted from Reference DRAWING A-53)

1.15 Weld 1-Sl-29-26F Safety Injection Elbow to Branch Connection ion w

hi v d (i anch n

Elbow I

J I

/ __ 1 Flow u ulr Figure 1.15-2 Weld 1-Sl-29-26F Coverage Calculation

1.15 Weld 1-Sl-29-26F Safety Injection Elbow to Branch Connection w

own r nch onn ction lbow

lw V tu quir d Figure 1.15-3 Weld 1-Sl-29-26F Coverage Calculation

1.15 Weld 1-Sl-29-26F Safety Injection Elbow to Branch Connection Table 1.15-1 Weld 1-Sl-29-26F Coverage Calculation Results

1.15 Weld 1-Sl-29-26F Safety Injection Elbow to Branch Connection Figure 1.15-4 Weld 1-Sl-29-26F Component Photograph

1.16 Weld 1-SI-31-21S Safety Injection Elbow to Tee Weld 1-Sl-31-21S was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NDE data came from UT Report No . U1-VE-19-051. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the tee . The examination resulted in total UT coverage of 50.0% as described in Figures 1.16-2, 1.16-3, and Table 1.16-1 . A photograph of weld 1-Sl 21 S is provided in Figure 1.16-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.16 Weld 1-SI-31-21S Safety Injection Elbow to Tee

_EL 622' 1 O'"

1-Sl-31 18S 10S

  • o F

~ 2 3F - 10"

-GSI.R 10" -Sl-31 Sl-181 - 2

\ 03S t -S1-31 8"

1-RH-27 04S FIG. 79 r-1--~ CRANEW L 27-1/2 1.0.

OBLONGFLANG 1-RC-2 21" 0 0. X 11 -314" 1.0 . X 5" THK. CO LD LEG

- - RESTRAJ T LOOP 2 U NO 1-S1-69 10"

._1_-s_I_

.3_1_ _ _- l . - o ~ s . A1N ss 10'" oar O" 6" 1-Sl -30 0 . THK. o* 0.718" J.

  • SI- 66-L2 SCHEDU LE 140 60

' 10F L_ CAL. BLK. 3378030 ULUS LOCATIO D. C. COOK, UNIT 1 FIG. A..,54 SAFETY JNJ CT ON SYSTEM REF. DRAWING AEP 1-Sl-3 FLOW DIAGRAM * -5143 Figure 1.16-1 Weld 1-SI-31-21S (Extracted from Reference DRAWING A-54)

1.16 Weld 1-SI-31-21S Safety Injection Elbow to Tee PHA D ARRAY UL T

41 Flow UpstT m Volume A ev T

Flow Down , am Volume A i ed Figure 1.16-2 Weld 1-SI-31-21S Coverage Calculation

1.16 Weld 1-SI-31-21S Safety Injection Elbow to Tee

~

T e

  • ...1 Flow qu rd Figure 1.16-3 Weld 1-SI-31-21S Coverage Calculation

1.16 Weld 1-SI-31-21S Safety Injection Elbow to Tee Table 1.16-1 Weld 1-SI-31-21S Coverage Calculation Results

1.16 Weld 1-51-31-215 Safety Injection Elbow to Tee Figure 1.16-4 Weld 1-51-31-215 Component Photograph

1.17 Weld 1-51-31-245 Safety Injection Tee to Pipe Weld 1-Sl-31-24S was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-052. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to the configuration of the tee. The examination resulted in total UT coverage of 50.0% as described in Figures 1.17-2, 1.17-3, and Table 1.17-1 . A photograph of weld 1-Sl 24S is provided in Figure 1.17-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50 .55a(b)(2)(xv).

1.17 Weld 1-5I-31-24S Safety Injection Tee to Pipe O"

-Sl-3 1 13S t0S 26F

~ 23F - 10**

10" -Sl-31 Sl-181

  • 2 1 -S I-J1 03$

8" 1-RH-27 FIG. A-79 CRAN E WALL r1----l 27-1/'Z' 1.0.

OBLONG FLA NGE 1-RC-2 21* 0 0 . X 11-3/4" I. D. X s* THK. COLD LEG

- - RES RAINT LOOP 2 LI NO. 1,St-69 10"

._1_._s1_.s_,___ ..,....o~s-AN 1 ss 1o- oar O" 6" 1-S t-30 o* 0.71 8" SI- 66-L2 t 10F

  • l._ SC HEDU LE 14 0 60 CAL. BLK. 3378030 3378028 AN ULUS LOCATIO D. C. COOK, UNIT 1 FIG. REF. DRAWING* AEP 1-SI*3 A-.54 SAF ETY JNJECTION SYS EM FLOW DIAGR .S143 Figure 1.17-1 Weld 1-5I-31-24S (Extracted from Reference DRAWING A-54)

1.17 Weld 1-5I-31-24S Safety Injection Tee to Pipe PH Pipe El low z;_;;..;;a=

Downstream Volume Achieved Te Pipe Flow z;.:.;=s--

Up re m Vo ume Ac lev Figure 1.17-2 Weld 1-5I-31-24S Coverage Calculation

1.17 Weld 1-SI-31-24S Safety Injection Tee to Pipe T

Flow Ups ream Volume R qulr d Figure 1.17-3 Weld 1-SI-31-24S Coverage Calculation

1.17 Weld 1-SI-31-24S Safety Injection Tee to Pipe Table 1.17-1 Weld 1-SI-31-24S Coverage Calculation Results

Figure 1.17-4 Weld 1-SI-31-24S Component Photograph 1.18 Weld 1-Sl-31-27F Safety Injection Elbow to Branch Connection Weld 1-Sl-31-27F was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-053. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8(c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the branch connection . The examination resulted in total UT coverage of 50.0% as described in Figures 1.18-2, 1.18-3, and Table 1.18-1. A photograph of weld 1-Sl-31-27F is provided in Figure 1.18-4.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.18 Weld 1-SI-31-27F Safety Injection Elbow to Branch Connection 1()"'

1-Sl-3 1 18S L 622' 14S 1

1-Sl-31 10s 26F

- 10" 10" -Sl-31 1 -Sl-31 03S 8"

1-RH-27 04S FIG. 7Q CRA N WALL 27-1/'Z' 1.0.

OB LONG FLANGE 1-RC -2 21" 0 0 . X 11 -314" 1.0 . X 5" THK. COLD LEG

- - RESTRAINT LOOP 2 3/4" 10" 1-_s1_.J_1_ __ _ o~S-AN 1 ss 10'" 06F 6

1-SJ-30 0.7 18"

,L

  • SI- 61H2 SCHEDULE 140 60 f 10F L_ CAL. BLK. 337 8030 3378028 AN ULUS LOCATION D. C. COOK, UN IT 1 FIG. REF. DRAWING* A EP 1-Sl-3 A-54 SAFETY JNJECT ON SYS EM FLOW DIAGR  : -5 143 Figure 1.18-1 Weld 1-Sl-31-27F (Extracted from Reference DRAWING A-54)

1.18 Weld 1-Sl-31-27F Safety Injection Elbow to Branch Connection co I ow Ul Flow Up r am Volum Adtl El ow u

Flow Figure 1.18-2 Weld 1-Sl-31-27F Coverage Calculation

1.18 Weld 1-SI-31-27F Safety Injection Elbow to Branch Connection Elbow low Downstream Volume Required Figure 1.18-3 Weld 1-Sl-31-27F Coverage Calculation

1.18 Weld 1-5I-31-27F Safety Injection Elbow to Branch Connection Table 1.18-1 Weld 1-5I-31-27F Coverage Calculation Results

1.18 Weld 1-Sl-31-27F Safety Injection Elbow to Branch Connection Co o Figure 1.18-4 Weld 1-Sl-31-27F Component Photograph

1.19 Weld 1-Sl-51-22F Safety Injection Elbow to Tee Weld 1-Sl-51-22F was UT examined in Inspection Period 3, during the U1C29 refueling outage in 2019. The NOE data came from UT Report No. U1-VE-19-056. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8(c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the tee . The examination resulted in total UT coverage of 50.0% as described in Figures 1.19-2, 1.19-3, and Table 1.19-1. A photograph of weld 1-Sl 22F is provided in Figure 1.19-4.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.19 Weld 1-Sl-51-22F Safety Injection Elbow to Tee

  • GSI-V-156 1-GSI-V- 156-1 (... 38j
  • OSI *157 1-0SH.-157-IA (.438")

1-SI-~ '

FIG _ ~

3*

L. 608' 1-S 1--3 1 J.-5

. A- 7 FIG.B-2SS l/HE /t'O. 1.s,.s, IIATAY/IAJ. ss

/t'OII. /JI) 4" NfJJI. rl/K. 0.438" 160 337802

0. C. COOK. UH/7' I f'!C.

11.CT {)(AC/WI: 1-5142 Figure 1.19-1 Weld 1-Sl-51-22F (Extracted from Reference DRAWING A-59)

1.19 Weld 1-Sl-51-22F Safety Injection Elbow to Tee T

low D Ah ved T

low Volu R quir d Figure 1.19-2 Weld 1-Sl-51-22F Coverage Calculation L

1.19 Weld 1-SI-51-22F Safety Injection Elbow to Tee

£ T

<--' 2*51-63 FIG. A-54 CAL. BLK. 3378028 (6-SS-160-. 71)

LOCATION RU . DRAWING: AEP 2-Sl-6)

D. C. COOK, UNIT 2 FI G. A- 56 SAITlY IN..ECTI0N SY'SlDA FLOW DIAGRAM : 2-5143 Figure 1.24-1 Weld 2-SI-63-17 (Extracted from Reference DRAWING 2A-56)

1.24 Weld 2-51-63 Safety Injection Pipe to Valve 1" 2" 3" 4" Flow

, - - -- - - - Sl 17 Valve 70° ANGLE EXAM AREA % COVERAGE 45 UPST 100 45 DNST 0 60 UPST 100 TOTAL - 700 60 DNST 0 700/1000 = 70%

70 UPST 100 70 DNST 0 45 cw 100 45 ccw 100 60 cw 100 60 ccw 100 _, ,,, __ _ A ,,,

Figure 1.24-2 2-51-63-17 Coverage Calculation

1.24 Weld 2-51-63 Safety Injection Pipe to Valve Figure 1.24-3 Weld 2-51-63-17 Component Photograph

1.25 Weld 2-RH-33 Residual Heat Removal Tee to Pipe Weld 2-RH-33-01 was UT examined in Inspection Period 3, during the U2C24 refueling outage in 2018. The NOE data came from UT Report No. U2-VE-18-029. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the geometric configuration of the tee. The examination resulted in total UT coverage of 50.0% as described in Table 1.25-1 and as shown in Figures 1.25-2, 1.25-3 and 1.25-4. A photograph of weld 2-RH-33-01 is provided in Figure 1.25-5.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Request for Alternative ISIR-4-01 (Code Case N-716) as approved by the Nuclear Regulatory Commission (NRC) under the Safety Evaluation in ADAMS Accession No. ML072620553.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.25 ~ VVeld 2-RH-33 Residual Heat Removc!I Tee to Pipe 2-GRH-V-509 05-PL-1 & 2 (1") 2-RC-18 HOT LEG LOOP 2 nc. A-10 06 2-GRH-R-507 17-PRI-PL (1 } BENO 2-RH-33 FIG. B-42 r< ',, ICM-129 \ 14" CRANE EL. 608' WALL 10 EL soa* BEND AZ 147' LINE NO 2-RH - 33 IN SULATION YES MATERIAL S5 ANNULUS NOM. DIA. 14" NOM. lHK. 1 41*

SCHEDU LE 160 CAL. BLK . 3378032 (1'1/4-SS-160-1 40}

LOCATION REF . DRAWING: AEP 2-RH-33 D. C. COOK, UNIT 2 FIG . A- 77 RESIDUAL HEAT RE MOVAL SYSTEIII FLOW DIAGRAM: 2- 51 +3 Figure 1.25-1 Weld 2-RH-33-01 (Extracted from Reference DRAWING 2A-77)

1.25 Weld 2-RH-33 Residual Heat Removal Tee to Pipe SCAN LENGTH OF VOLUME VOLUME REQUIRED PERCENTAGE OF WELD DIMENSIONS EXAMINED EXAMINATION EXAMINATION VOLUME- VOLUME COMPLETE EXAM Axial US Scan 0" to 44.5" 44.5"x0.4886 in 2 0.0 in 3 21.7427 in 3 0.0%

Axial US Scan 0" to 44.5" 44.5"x0.4886 in 2 21 .7427 in 3 21 .7427 in 3 100% "Best Effort" (from OS scan side)

Axial OS Scan 0" to 44.5" 44.5"x0.4886 in 2 21 .7427 in 3 21.7427 in 3 100%

US CW Scan 0" to 44.5" 44.5"x0.4886 in 2 0.0 in 3 21 .7427 in 3 0.0%

US CCW Scan 0" to 44.5" 44.5"x0.4886 in 2 0.0 in 3 21.7427 in 3 0.0%

OS CS Scan 0" to 44.5" 44.5"x0.4886 in 2 21.7427 in 3 21.7427 in 3 100%

OS CCW Scan 0" to 44.5" 44.5"x0.4886 in 2 21 .7427 in 3 21.7427 in 3 100%

Code Coverage Achieved (Best Effort Axial US Scan Coverage is 65.2281 in 3 130.4562 in 3 50.0%

not included)

Table 1.25-1 Weld 2-RH-33-01 Coverage Calculation Results

1.25 Weld 2-RH-33 Residual Heat Removal Tee to Pipe PHASED ARRAY ULTRASONIC EXAMINATION COVERAGE ASSESSMENT

,- - - 1.60" - - -

/

Tee Pipe l .'3 6 In C

Flow OS Coverage Achieved from O" to 44.5"

, - - - - 1.60 " ------

Tee Pipe t J.36 Ir>

---7 047 ""

"Best Effort" US Coverage area Figure 1.25-2 Weld 2-RH-33-01 Phased Array UT Examination Coverage Assessment

1.25 Weld 2-RH-33 Residual Heat Removal Tee to Pipe 0 '

G. I US nd O d R qulr d Volum Dim n Ion Figure 1.25-3 Weld 2-RH-33-01 Phased Array UT Examination Coverage Assessment

1.25 Weld 2-RH-33 Residual Heat Removal Tee to Pipe T

f o,

Axi I n Ar min du from n Pipe lll I!

am DS CW nd W Cov r Flow Achi v d from outo 44. 11 Figure 1.25-4 Weld 2-RH-33-01 Phased Array UT Examination Coverage Assessment

Weld 2-RH-33 Residual Heat Removal Tee to Pi e Figure 1.25-5 Weld 2-RH-33-01 Component Photograph

7 1.26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld Weld 2-RPV-D was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-028. Previous ISi UT data was reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-1(a). The corresponding CRVas shown on that Figure is E-F-G-H. The UT examination was limited due to six core support pads. The examination resulted in total UT coverage of 80.56%

as described in Table 1.26-1 and as shown in Figures 1.26-2, 1.26-3, and 1.26-4.

No recordable indications were detected during this examination.

Section XI Appendix VIII, Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b )(2)(xv).

Note: No laminations were reported on the RPV Head and Shell that could interfere with the angle beam examinations performed on weld 2-RPV-D.

1.26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld 27 240' 210* 1B' 00'

-f a i' 2- p - \

240*

l--'- - - - - - - - - . - - - - - - - - - - - - - ' - - - - - - - - - - - - - - - - -- 2-W -

Ell- H L 334* 1so* 129* n*

I I I

_ :?- Lti _ (2-RPV-E)

L I[ HEAD DOll R 'l TE NI T 2 Figure 1.26-1 Weld 2-RPV-D (Extracted from Reference DRAWING 2A-1)

1 26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 30.29% 14.76% 32.75% 77.8%

UP/DN 29.78% 15.58% 37.96% 83.32%

UT Coverage = 80.56% Limitations: 6 Core Support Pads Table 1.26-1 Weld 2-RPV-D Coverage Calculation Results

1.26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld I : ,_

Figure 1.26-2 Parallel scan limitation under core support pads at 0°, 60°, 180°, 240°, 300°, and 360°

1.26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld Figure 1.26-3 Parallel scan limitation to core support pads at 0°, 60°, 180°, 240°, 300°, and 360°

1.26 Weld 2-RPV-D - RPV Lower Shell to Lower Head Weld 1

r T

  • 3
  • TT Figure 1.26-4 Perpendicular scan limitation under core support pads at 0°, 60°, 180°, 240°, 300°, and 360°

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld Weld 2-RPV-E was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-029. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is A-B-C-D . The UT examination was limited due to Bottom Mounted Instrumentation Tubes . The examination resulted in total UT coverage of 47 .61 % as described in Table 1.27-1 and as shown in Figures 1.27-2 and 1.27-3.

One recordable indication was detected during this examination. The indication was acceptable per ASME Section XI , 2004 Ed ition , IWB-3510-1 as shown in Figures 1.27-4 and 1.27-5.

Section XI Appendix VIII , Supplements 4 and 6 were used for this UT examination . The examination satisfied the requirements of Appendix VIII with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b )(2)(xv) .

Note: No laminations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-RPV-E.

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld r,

D. C Figure 1.27-1 Weld 2-RPV-E (2-LHC-01) (Extracted from Reference DRAWING 2A-1)

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 18.08% 7.29% 17.34% 42.71%

UP/DN 22.23% 8.96% 21.31% 52.5%

UT Coverage= 47.61% Limitations: Bottom Mounted Instrumentation Tubes Table 1.27-1 Weld 2-RPV-E (2-LHC-01) Coverage Calculation Results

1.27 Weld 2-RPV-E (2-L - - r Head Dollar Plate Weld

}

PARA L CA

  • FULi VOi r PARA L LSCA R OS PARAL I Al - 0 S Figure 1.27-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld ICU R Figure 1.27-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld

__ ,_i;SDyn- PLA T U IT 2 INDICATIO SSESSM T ROCEDUR AL YST C.S .Wyffe LEVEL Ill 9

p II:

I 't w

~

0

( D) 0 Figure 1.27-4 2-RPV-E (2-LHC-01) Indication Assessment

1.27 Weld 2-RPV-E (2-LHC-01) - RPV Lower Head Dollar Plate Weld fW) 10-1

- o. I - =220.8 7 Figure 1.27-5 2-RPV-E (2-LHC-01) Indication Plot

1.28 Weld 2-LHM RPV Lower Head Meridional Weld at 26 Degrees Weld 2-LHM-01 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-038. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H . The UT examination was limited due to Bottom Mounted Instrumentation Tubes. The examination resulted in total UT coverage of 66.3% as described in Table 1.28-1 and as shown in Figures 1.28-2 and 1.28-3.

No recordable indications were detected during this examination.

Section XI Appendix VIII, Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Note: No laminations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-01.

1.28 Weld 2-LHM RPV Lower Head Meridional Weld at 26 Degrees Y.l 27 2 o> 210* 18. 00' 2-90' 334* 283* 1so* 129° n*

I I I

_ ~-Ltt * (2-RPV-E)

L I[ HEAD OOU. R Fl TE Figure 1.28-1 Weld 2-LHM-01 (Extracted from Reference DRAWING 2A-1)

1 28 -

W e Id 2 LHM RPV L ower Hea d Men"d"Iona I W e Id at 26 Dearees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 30.19% 12.23% 28.94% 71.37%

UP/DN 25.91% 10.49% 24.83% 61 .23%

UT Coverage = 66.3% Limitations: Bottom Mounted Instrumentation Tubes Table 1.28-1 Weld 2-LHM-01 Coverage Calculation Results

1.28 Weld 2-LHM RPV Lower Head Meridional Weld at 26 Degrees 180c:

I I

0 Figure 1.28-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.28 Weld 2-LHM RPV Lower Head Meridional Weld at 26 Degrees 77 283

- PERP S PE . E

- PEP

  • OS 20 Figure 1.28-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees Weld 2-LHM-02 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-039. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H . The UT examination was limited due to Bottom Mounted Instrumentation Tubes . The examination resulted in total UT coverage of 83.44% as described in Table 1.29-1 and as shown in Figures 1.29-2 and 1.29-3.

One recordable indication was detected during this examination. The indication was acceptable per ASME Section XI , 2004 Edition , IWB-3510-1 as shown in Figures 1.29-4 and 1.29-5.

Section XI Appendix VIII , Supplements 4 and 6 were used for this UT examination . The examination satisfied the requirements of Appendix VIII with qualified personnel , procedures and equipment to the 2001 Edition of Append ix VIII as cond itioned by 10 CFR 50.55a(b)(2)(xv).

Note: No lam inations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-02 .

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees 27 2 o* 18 . 00'

-f 66 l°

,-.....-------~--------~------- - - - - - - - -- - ~2-RP

  • E L- H L 2- '* 'C 33.t* 283*

I

_ z- Ll1 * (2-RPV-E}

L~[ HEAD DOLL R Ft TE NIT 2 ~ " TOR PRE '3 RE Figure 1.29-1 Weld 2-LHM-02 (Extracted from Reference DRAWING 2A-1)

1 29 -

W e Id 2 LHM RPV L ower Hea d Men"d"Iona I W e Id at 77 Dearees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 45.74% 14.47% 34.26% 84.47%

UP/ON 34.87% 14.12% 33.42% 82.41%

UT Coverage = 83.44% Limitations: Bottom Mounted Instrumentation Tubes Table 1.29-1 Weld 2-LHM-02 Coverage Calculation Results

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees o=

8 E E I

E E I 0

Figure 1.29-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees 283 Figure 1.29-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees UN 2

REV.

OICA lO ------,,-,,-------------- El. II 0A

- ---9 ---

19 p E A K cw p 8 Figure 1.29-4 Weld 2-LHM-02 Indication Assessment

1.29 Weld 2-LHM RPV Lower Head Meridional Weld at 77 Degrees 100 .Y-/ ,/8 Figure 1.29-5 Weld 2-LHM-02 Indication Plot

1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees Weld 2-LHM-03 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-040. Previous ISi UT data was reviewed.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H . The UT examination was limited due to Bottom Mounted Instrumentation Tubes. The examination resulted in total UT coverage of 73.09% as described in Table 1.30-1 and as shown in Figures 1.30-2, and 1.30-3.

One recordable indication was detected during this examination. The indication was acceptable per ASME Section XI , 2004 Edition, IWB-3510-1 as shown in Figures 1.30-4 and 1.30-5.

Section XI Appendix VIII , Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Append ix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Note: No laminations were reported on the RPV Head that could interfere with the angle beam exam inations performed on weld 2-LHM-03.

1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees 3 o* 27 2 (J' 210* 18 ' 00'

-f

- IJ r c-68 1*

c- PV* \

240* 1 6 4

_ ~-Ll1 * (2-RPV-E}

L I [ HEAD OOll R Ft IT NIT 2 TOR PRE '> RE \E~ LA'/001 Figure 1.30-1 Weld 2-LHM-03 (Extracted from Reference DRAWING 2A-1)

1 30 -

W e Id 2 LHM RPV L ower Hea d Men'd',ona I W e Id at 129 DeQrees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 32.25% 13.06% 30.91% 78.23%

UP/DN 29.6% 11.99% 28.37% 69.95%

UT Coverage = 73.09% Limitations: Bottom Mounted Instrumentation Tubes Table 1.30-1 Weld 2-LHM-03 Coverage Calculation Results

1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees 7 ~

0 28 E E I

E E I 0

Figure 1.30-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees 77 33 C

- PE E E

283° Figure 1.30-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees D.C . Coo UNIT 2 OUR PDl-1S1-25 c.s.

8 10- o.

Figure 1.30-4 Weld 2-LHM-03 Indication Assessment

7 1.30 Weld 2-LHM RPV Lower Head Meridional Weld at 129 Degrees

-0 6 Figure 1.30-5 Weld 2-LHM-03 Indication Plot

1.31 Weld 2-LHM RPV Lower Head Meridional Weld at 180 Degrees Weld 2-LHM-04 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-041 . No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H. The UT examination was limited due to Bottom Mounted Instrumentation Tubes. The examination resulted in total UT coverage of 71.03% as described in Table 1.31-1 and as shown in Figures 1.31-2, and 1.31-3.

No recordable indications were detected during this examination.

Section XI Appendix VIII, Supplements 4 and 6 were used for this UT examination . The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b )(2)(xv).

Note: No laminations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-04.

1.31 Weld 2-LHM RPV Lower Head Meridional Weld at 180 Degrees 27 2 <r 2 10* 1B . 00'

-f 68 1' 2-- P .- ~

240" l---'- - - - - - - ~ - - - - - - - - - - ' - - - - - - - - - - - - - - - --- 2- RP -

2- E L- H L Tr I

2-RPV-E}

NIT 2 Figure 1.31-1 Weld 2-LHM-04 (Extracted from Reference DRAWING 2A-1)

1 31 W e Id 2 -LHM - RPV L ower Hea d Men"d"Iona I W e Id at 180 Dearees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 30.8% 12.47% 29.52% 72.79%

UP/ON 29.31% 11.87% 21.1% 69.28%

UT Coverage = 71.03% Limitations: Bottom Mounted Instrumentation Tubes Table 1.31-1 Weld 2-LHM-04 Coverage Calculation Results

1.31 Weld 2-LHM RPV Lower Head Meridional Weld at 180 Degrees 1r Figure 1.31-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.31 Weld 2-LHM RPV Lower Head Meridional Weld at 180 Degrees 0

283 270 Figure 1.31-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.32 Weld 2-LHM RPV Lower Head Meridional Weld at 231 Degrees Weld 2-LHM-05 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-042. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H. The UT examination was limited due to Bottom Mounted Instrumentation Tubes . The examination resulted in total UT coverage of 67 .15% as described in Table 1.32-1 and as shown in Figures 1.32-2, and 1.32-3.

No recordable indications were detected during this examination .

Section XI Appendix VIII , Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Note: No laminations exist on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-05.

1.32 Weld 2-LHM RPV Lower Head Meridional Weld at 231 Degrees

50* )00' 27 . 24 . 210* 1130* 150* 12 . oo* 60' 30*

~ V-A 2-RPV-VA. 2-HP - VA2 2-P.PV-\/Al FL GE- HEU.

247 113* 2r t

0 2- NI-0 2-Nl-l 0

2-NZ- 0 0

2- NJ- 0 2- NH 68 .1' JJ5' 29Y 202

  • 155* 5T RP -8 LOOP! OOP I LOOP 2 00 3 LOOP 4 HELL-SHELL 2- PY* VB2 2- RP\J- VB1 240' 170' 1 6 4' l - - ' - - - - - - - - - - r - - - - - - - - - - - ' - - - - - - - - . . . . - - - - - - - - - 2- v-c
?-RPV* VC 2- R V* V 1 SHELL- SHELL 270' go*

108 .0 '

334° I

283~

I 23 1° I

1so I

1--------,.-------1..--.-----.-------.-------.--.L..------.-------J-2-RP -0 0

129" I

77*

I l

LO~ER H(AO- SHELL L - 1 (2-RPV-E) 2- LHM- O7 2- LH~ - 0 2- LH~ - 04 2- LHN- 03 LOWER HEAD DO .il.R P ATE.

D . C. 2 FI G. A-1 REACTOR PRE S5 RE LL'i'OT Figure 1.32-1 Weld 2-LHM-05 (Extracted from Reference DRAWING 2A-1)

1 32 - - -

W e Id 2 LHM 05 RPV L ower Hea d Men"d"Iona I W e Id at 231 Dearees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 30.42% 12.32% 29.16% 71.89%

UP/DN 26.40% 10.69% 25.31% 62.41%

UT Coverage = 67 .15% Limitations: Bottom Mounted Instrumentation Tubes Table 1.32-1 Weld 2-LHM-05 Coverage Calculation Results

1.32 Weld 2-LHM RPV Lower Head Meridional Weld at 231 Degrees 0

8 =

I I

0 Figure 1.32-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.32 Weld 2-LHM RPV Lower Head Meridional Weld at 231 Degrees 77 0

283 2 0 Figure 1.32-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.33 Weld 2-LHM RPV Lower Head Meridional Weld at 283 Degrees Weld 2-LHM-06 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-043. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H. The UT examination was limited due to Bottom Mounted Instrumentation Tubes. The examination resulted in total UT coverage of 83.69% as described in Table 1.33-1 and as shown in Figures 1.33-2, and 1.33-3.

No recordable indications were detected during this examination.

Section XI Appendix VIII , Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Note: No laminations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-06 .

1.33 Weld 2-LHM RPV Lower Head Meridional Weld at 283 Degrees 30* :50D. 27. 24 . 210* 180" 150* 12. oo* 50* 30' RP -t..

2- PV-VA 2<l7 2-f.'P - VA2 11.]"

1-RPV-VA l 22" FLAN E- EU.

-t 0

2* Nl-0 2-Nl-1 0

2-N2-O 0

2-NJ-0 2- NH 681' J B" 29Y 202' 155* 5T RPV-6 LO0PI OOP I LOOP 2 00 3 LOOP 4 HE L-SHELL 2- PV* vB - RPV- VB1 240" 170" 1 6 4' l - - ' ' - - - - - - - - - - . . - - - - - - - - - - - ' - - - - - - - - - . . - - - - - - - - - 2* -C 2- F?PV-\.C 2-F? V* VC1 SHELL- SHELL

27. 90" I 8.o*

334° I

283 I

231 ° I

180° I

77*

I

~ - - - - - , . - - - - ~ - - , , - - - - - - r - - - - - - - , r - - - - - - - " T - ~ - - - - - " T - - - - - - 2*RP LO~ER

-D l HEAD-SHELL

- 1 (2-RPV-E) 2- LHM -01 2- LHP..1 -05 2- LHt,l - 04 2- LHt-l - 03 2- LHM - 2 LOWER HEAD DOLL.AR P ATE D C. 2 FIG . A-1 REAClOR PP.E SS L LJ\.'rO T Figure 1.33-1 Weld 2-LHM-06 (Extracted from Reference DRAWING 2A-1)

1 33 W e Id 2 -LHM RPV L ower H ea d M en"d"Iona I W e Id a t 283 D earees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 34.8% 14.09% 33.36% 82.26%

UP/DN 36.02% 14.59% 34.53% 85.13%

UT Coverage = 83.69% Limitations: Bottom Mounted Instrumentation Tubes Table 1.33-1 Weld 2-LHM-06 Coverage Calculation Results

1.33 Weld 2-LHM RPV Lower Head Meridional Weld at 283 Degrees o=

I I

0 Figure 1.33-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.33 Weld 2-LHM RPV Lower Head Meridional Weld at 283 Degrees 77 0

270 Figure 1.33-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.34 Weld 2-LHM RPV Lower Head Meridional Weld at 334 Degrees Weld 2-LHM-07 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-044. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

3. The corresponding CRV as shown on that Figure is E-F-G-H . The UT examination was limited due to Bottom Mounted Instrumentation Tubes. The examination resulted in total UT coverage of 84.46% as described in Table 1.34-1 and as shown in Figures 1.34-2 and 1.34-3.

No recordable indications were detected during this examination.

Section XI Appendix VIII, Supplements 4 and 6 were used for this UT examination. The examination satisfied the requirements of Appendix VIII with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

Note: No laminations were reported on the RPV Head that could interfere with the angle beam examinations performed on weld 2-LHM-07.

1.34 Weld 2-LHM RPV Lower Head Meridional Weld at 334 Degrees 330* 300* 210* 240* 210* 180" 150' 120* soo* 50* 30" R? -t..

2- PV-V~3 - 2-W -'IA2. 1-l?P -VAl FLANGE- ELL 247 11 . 22" t

0 2- Nl-0 2-Nl-l 2-~12-1 0

2-N2-0 0

2-N3-0 2-~13-1 2-NH 2-1~4- 0 6B.r 3-s*  :?93" 2~T 202

  • 153* 15* 67" 22' RP -6 LO0PI OOP I L0CP 2 LOOP 2 00? 3 LOOP 3 LOO? 4 LO P 4 SH LL- HELL

- 2- PV-V8 2 24

-RPV-V81 no* - 1 6 .4 '

Z-R'PV-270" - 2-t - - ' - - - - - - - - - r - - - - - - - - - - ' - - - - - - - - - , - - - - - - - - - - 2-~V- C SHELL-SHELL 1 Q' 334° I

283° I

231° I

- - - - ~ - - - ~ - - - - - - - - ~ - - - - - ~ - - ~ - - - - -D 180 ° 129° I

770 I

LO~ RH AO-SH LL l

L - 1 (2-RPV-E) 2-LHI.I- 2-L tJ-05 2-LHN- 04 2-L N-03 LOWER H~AO D AR PLAT D FIG. A-1 REAC10R PP.E SS RE LL'rOT Figure 1.34-1 Weld 2-LHM-07 (Extracted from Reference DRAWING 2A-1)

1 34 - - -

W e Id 2 LHM 07 RPV L ower Hea d Men"d"Iona I W e Id at 334 Dearees Beam Direction 45° Dual 45° Single 46° Shear Total Exam Volume Exam Volume Exam Volume CCW/CW 34.7% 14.05% 33.26% 82.0%

UP/DN 36.77% 14.89% 35.25% 86.92%

UT Coverage = 84.46% Limitations: Bottom Mounted Instrumentation Tubes Table 1.34-1 Weld 2-LHM-07 Coverage Calculation Results

1.34 Weld 2-LHM RPV Lower Head Meridional Weld at 334 Degrees 7-E I

Io=

Figure 1.34-2 Parallel scan limitation: Bottom Mounted Instrumentation Tubes

1.34 Weld 2-LHM RPV Lower Head Meridional Weld at 334 Degrees 283 E E E

E 270 ° Figure 1.34-3 Perpendicular scan limitation: Bottom Mounted Instrumentation Tubes

1.35 Weld 2-51-58-23 Safety Injection Elbow to Branch Connection Weld 2-Sl-58-23 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-014. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to the configuration of the branch connection. The examination resulted in total UT coverage of 50% as described in Figures 1.35-2, 1.35-3, 1.35-4, 1.35-5, and Table 1.35-1. A photograph of weld 2-Sl-58-23 is provided in Figure 1.35-6.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.35 Weld 2-SI-58-23 Safety Injection Elbow to Branch Connection Figure 1.35-1 Weld 2-SI-58-23 (Extracted from Reference DRAWING 2A-49)

1.35 Weld 2-SI-58-23 Safety Injection Elbow to Branch Connection rl Figure 1.35-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.35 Weld 2-SI-58-23 Safety Injection Elbow to Branch Connection Figure 1.35-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.35 Weld 2-SI-58-23 Safety Injection Elbow to Branch Connection Figure 1.35-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.35 Weld 2-51-58-23 Safety Injection Elbow to Branch Connection Figure 1.35-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 35 W e Id 2 SI 58 23 Saf e:v . f I0n Elb ow t 0 B ranc hC onnecIon t I niec f Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 34.0" 0.3968 in 2 0.3968 in 2 100%

Upstream Axial for 34.0" 0.3968 in 2 0.1264 in 2 31.8% (Note 1)

Downstream Volume Clockwise 34.0" 0.7936 ln 2 0.3968 in 2 50%

Counterclockwise 34.0" 0.7936 in 2 0.3968 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.35-1 Weld 2-SI-58-23 Coverage Calculation Results

1.35 Weld 2-SI-58-23 Safety Injection Elbow to Branch Connection Figure 1.35-6 Weld 2-Sl-58-23 Component Photograph

1.36 Weld 2-S1-59-24 Safety Injection Valve to Elbow Weld 2-Sl-59-24 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-015. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to the configuration of the valve . The examination resulted in total UT coverage of 50% as described in Figures 1.36-2, 1.36-3, 1.36-4, 1.36-5, and Table 1.36-1 . A photograph of weld 2-Sl-59-24 is provided in Figure 1.36-6.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Ed ition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.36 Weld 2-S1-59-24 Safety Injection Valve to Elbow C. CO Figure 1.36-1 Weld 2-S1-59-24 (Extracted from Reference DRAWING 2A-50)

1.36 Weld 2-SI-59-24 Safety Injection Valve to Elbow Figure 1.36-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.36 Weld 2-S1-59-24 Safety Injection Valve to Elbow I.

Figure 1.36-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.36 Weld 2-SI-59-24 Safety Injection Valve to Elbow I.

Figure 1.36-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.36 Weld 2-SI-59-24 Safety Injection Valve to Elbow Figure 1.36-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 36 W e Id 2 -SI 24 5 af etv . f 10n V ave t I mec I t o Elb ow Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 34.25" 0.3774 in 2 0.3774 in 2 100%

Upstream Axial for 34.25" 0.3774 in 2 0.1231 in 2 32.6% (Note 1)

Downstream Volume Clockwise 34.25" 0.7548 ln 2 0.3774 in 2 50%

Counterclockwise 34.25" 0.7548 in 2 0.3774 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.36-1 Weld 2-51-59-24 Coverage Calculation Results

1.36 Weld 2-S1-59-24 Safety Injection Valve to Elbow Figure 1.36-6 Weld 2-S1-59-24 Component Photograph

1.37 Weld 2-51-59-25 Safety Injection Elbow to Branch Connection Weld 2-Sl-59-25 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-016. Previous ISi UT data was not documented as reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to the configuration of the branch connection . The examination resulted in total UT coverage of 50% as described in Figures 1.37-2, 1.37-3, 1.37-4, 1.37-5, and Table 1.37-1. A photograph of weld 2-Sl-59-25 is provided in Figure 1.37-6.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The exam ination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as cond itioned by 10 CFR 50.55a(b)(2)(xv).

1.37 Weld 2-S1-59-25 Safety Injection Elbow to Branch Connection I

  • Figure 1.37-1 Weld 2-S1-59-25 (Extracted from Reference DRAWING 2A-50)

1.37 Weld 2-SI-59-25 Safety Injection Elbow to Branch Connection Figure 1.37-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.37 Weld 2-S1-59-25 Safety Injection Elbow to Branch Connection Figure 1.37-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.37 Weld 2-S1-59-25 Safety Injection Elbow to Branch Connection Figure 1.37-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.37 Weld 2-51-59-25 Safety Injection Elbow to Branch Connection Figure 1.37-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 37 W e Id 2-SI 25 Saf etv . f I0n Elb ow t 0 B ranc hC onnecIon t I mec f Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 34.25" 0.3577 in 2 0.3577 in 2 100%

Upstream Axial for 34.25" 0.3577 in 2 0.1213 in 2 33.9% (Note 1)

Downstream Volume Clockwise 34.25" 0.7154 ln 2 0.3577 in 2 50%

Counterclockwise 34.25" 0.7154 in 2 0.3577 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered " Best Effort" and is not included in coverage calculation of Code required volume Table 1.37-1 Weld 2-SI-59-25 Coverage Calculation Results

1.37 Weld 2-S1-59-25 Safety Injection Elbow to Branch Connection Figure 1.37-6 Weld 2-S1-59-25 Component Photograph

1.38 Weld 2-51-60-31 Safety Injection Valve to Elbow Weld 2-Sl-60-31 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NDE data came from UT Report No. U2-VE-19-017. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the valve . The examination resulted in total UT coverage of 50% as described in Figures 1.38-2, 1.38-3, 1.38-4, 1.38-5 and Table 1.38-1 . A photograph of weld 2-Sl-60-31 is provided in Figure 1.38-6.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.38 Weld 2-51-60-31 Safety Injection Valve to Elbow 1

Figure 1.38-1 Weld 2-51-60-31 (Extracted from Reference DRAWING 2A-52)

1.38 Weld 2-SI-60-31 Safety Injection Valve to Elbow C 0 Figure 1.38-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.38 Weld 2-51-60-31 Safety Injection Valve to Elbow 2

07 Figure 1.38-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.38 Weld 2-SI-60-31 Safety Injection Valve to Elbow Figure 1.38-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.38 Weld 2-SI-60-31 Safety Injection Valve to Elbow Figure 1.38-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 38 W e Id 2 SI 60 31 Saf etv . f 10n V ave t Imec I t o Elb ow Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 21.25" 0.2272 in 2 0.2272 in 2 100%

Upstream Axial for 21.25" 0.2272 in 2 0.0896 in 2 39.4% (Note 1)

Downstream Volume Clockwise 21.25" 0.4544 ln 2 0.2272 in 2 50%

Counterclockwise 21.25" 0.4544 in 2 0.2272 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.38-1 Weld 2-51-60-31 Coverage Calculation Results

1.38 Weld 2-SI-60-31 Safety Injection Valve to Elbow Figure 1.38-6 Weld 2-SI-60-31 Component Photograph

1.39 Weld 2-SI-60-32 Safety Injection Elbow to Branch Connection Weld 2-Sl 32 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-018. Previous ISi UT data was not documented as reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-O-E-F. The UT examination was limited due to the configuration of the branch connection. The exam ination resulted in total UT coverage of 50% as described in Figures 1.39-2, 1.39-3, 1.39-4, 1.39-5, and Table 1.39-1 . A photograph of weld 2-Sl 32 is provided in Figure 1.39-6.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.39 Weld 2-SI-60-32 Safety Injection Elbow to Branch Connection 2

Figure 1.39-1 Weld 2-SI-60-32 (Extracted from Reference DRAWING 2A-52)

1.39 Weld 2-51-60-32 Safety Injection Elbow to Branch Connection Figure 1.39-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.39 Weld 2-SI-60-32 Safety Injection Elbow to Branch Connection 1.

Figure 1.39-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.39 Weld 2-SI-60-32 Safety Injection Elbow to Branch Connection L

Figure 1.39-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.39 Weld 2-SI-60-32 Safety Injection Elbow to Branch Connection Figure 1.39-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 39 - - -

W e Id 2 SI 60 32 Saf et:v I n1ec

. f 10n Elb ow t 0 B ranc hC onnec1onf Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 21.25" 0.1993 in 2 0.1993 in 2 100%

Upstream Axial for 21.25" 0.1993 in 2 0.1005 in 2 50.4% (Note 1)

Downstream Volume Clockwise 21.25" 0.1993 ln 2 0.1993 in 2 50%

Counterclockwise 21.25" 0.1993 in 2 0.1993 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.39-1 Weld 2-51-60-32 Coverage Calculation Results

Figure 1.39-6 Weld 2-SI-60-32 Component Photograph 1.40 Weld 2-51-61-15 Safety Injection Elbow to Branch Connection Weld 2-Sl-61-15 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-019. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the branch connection. The examination resulted in total UT coverage of 50% as described in Figures 1.40-2, 1.40-3, 1.40-4, 1.40-5, and Table 1.40-1. A photograph of weld 2-Sl-61-15 is provided in Figure 1.40-6.

No recordable indications were detected during this examination.

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VI II as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.40 Weld 2-51-61-15 Safety Injection Elbow to Branch Connection t 1 Figure 1.40-1 Weld 2-51-61-15 (Extracted from Reference DRAWING 2A-53)

1.40 Weld 2-51-61-15 Safety Injection Elbow to Branch Connection Figure 1.40-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.40 Weld 2-51-61-15 Safety Injection Elbow to Branch Connection Figure 1.40-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.40 Weld 2-SI-61-15 Safety Injection Elbow to Branch Connection Figure 1.40-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.40 Weld 2-SI-61-15 Safety Injection Elbow to Branch Connection 1

7 C

L Figure 1.40-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 40 W e Id 2-SI -61 15 Saf etv . f ,on Elb ow t 0 B ranc hC onnecf ,on t I mec Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 21.25" 0.2678 in 2 0.2678 in 2 100%

Upstream Axial for 21.25" 0.2678 in 2 0.0898 in 2 33.5% (Note 1)

Downstream Volume Clockwise 21.25" 0.5356 ln 2 0.2678 in 2 50%

Counterclockwise 21.25" 0.5356 in 2 0.2678 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.40-1 Weld 2-SI-61-15 Coverage Calculation Results

Figure 1.40-6 Weld 2-SI-61-15 Component Photograph 1.41 Weld 2-SI-62-32 Safety Injection Elbow to Branch Connection Weld 2-Sl-62-32 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-020. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the branch connection . The examination resulted in total UT coverage of 50% as described in Figures 1.41-2, 1.41-3, 1.41-4, 1.41-5, and Table 1.41-1. A photograph of weld 2-Sl-62-32 is provided in Figure 1.41-6.

No recordable indications were detected during this examination .

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel, procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.41 Weld 2-S1-62-32 Safety Injection Elbow to Branch Connection I

, . I I

Figure 1.41-1 Weld 2-S1-62-32 (Extracted from Reference DRAWING 2A-55)

1.41 Weld 2-SI-62-32 Safety Injection Elbow to Branch Connection Figure 1.41-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

0 L

Figure 1.41-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.41 Weld 2-S1-62-32 Safety Injection Elbow to Branch Connection 1

rl;'~* , ...._ H

'. -v, ' ~ '

I

~..ill.,..c. t. . . -~-

Figure 1.41-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.41 Weld 2-S1-62-32 Safety Injection Elbow to Branch Connection Figure 1.41-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1 41 - - -

W e Id 2 SI 62 32 Saf ettv Irnec

. f I0n Elb ow t 0 B ranc hC onnecIonf Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 21.25" 0.2678 in 2 0.2678 in 2 100%

Upstream Axial for 21 .25" 0.2678 in 2 0.0898 in 2 33.5% (Note 1)

Downstream Volume Clockwise 21.25" 0.5356 ln 2 0.2678 in 2 50%

Counterclockwise 21.25" 0.5356 in 2 0.2678 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.41-1 Weld 2-SI-62-32 Coverage Calculation Results

1.41 Weld 2-SI-62-32 Safety Injection Elbow to Branch Connection Figure 1.41-6 Weld 2-SI-62-32 Component Photograph

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection Weld 2-CS-120-13 was UT examined in Inspection Period 3, during the U2C25 refueling outage in 2019. The NOE data came from UT Report No. U2-VE-19-004. No previous ISi UT data was identified for review.

The UT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-8( c). The corresponding CRV as shown on that Figure is C-D-E-F. The UT examination was limited due to the configuration of the branch connection . The examination resulted in total UT coverage of 50% as described in Figures 1.42-2, 1.42-3, 1.42-4, 1.42-5, and Table 1.42-1 . A photograph of weld 2-CS-120-13 is provided in Figure 1.42-7.

One recordable indication was detected during this examination . The indication was determined to be metallurgical indication beam "re-direct" and found to be acceptable (see Figure 1.42-6).

The ultrasonic examination was performed in accordance with Code Case N-716-1 as approved by the Nuclear Regulatory Commission (NRC) under the Regulatory Guide 1.147 Rev. 18.

The examination satisfied the requirements of Appendix VIII and Supplement 2 with qualified personnel , procedures and equipment to the 2001 Edition of Appendix VIII as conditioned by 10 CFR 50.55a(b)(2)(xv).

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection 1

Figure 1.42-1 Weld 2-CS-120-13 (Extracted from Reference DRAWING 2A-72)

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection C

LO Figure 1.42-2 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Required

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection 0.

0 Figure 1.42-3 Phased Array Ultrasonic Examination Coverage Assessment Downstream Coverage Achieved

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection Figure 1.42-4 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Required

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection 0

Figure 1.42-5 Phased Array Ultrasonic Examination Coverage Assessment Upstream Coverage Achieved

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection Examination Performed Length of Exam Required Exam Area Achieved Exam Area Coverage Achieved Upstream Axial 11.0" 0.1194 in 2 0.1194 in 2 100%

Upstream Axial for 11.0" 0.1194 in 2 0.0661 in 2 55.3% (Note 1)

Downstream Volume Clockwise 11.0" 0.2388 ln 2 0.1194 in 2 50%

Counterclockwise 11 .0" 0.2388 in 2 0.1194 in 2 50%

Code Required Coverage Achieved 50%

Note 1: Far side volume coverage is considered "Best Effort" and is not included in coverage calculation of Code required volume Table 1.42-1 Weld 2-CS-120-13 Coverage Calculation Results

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection 2 1 0.

.2 o zl E 0 014 * '

FLO 1r ct al g I Figure 1.42-6 Weld 2-CS-120-13 Indication Plot

1.42 Weld 2-CS-120-13 Chemical and Volume Control Elbow to Branch Connection Figure 1.42-7 Weld 2-CS-120-13 Component Photograph

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Surge Nozzle-to-Vessel Weld Weld 14"-2-RC-21 was UT examined in Inspection Period 2 during the U2C21 refueling outage in 2013 . The NOE data came from UT Report No. U2-VE-13-020. Previous ISi UT data was not documented as reviewed .

The UT Code Required Volume (CRV) was determined based on Section XI, Figure IWB-2500-

?(b). The corresponding CRV as shown on that Figure is A-B-C-D-E-F-G-H . The UT examination was limited by the configuration of the Nozzle-to-Shell and adjacent heater sleeves resulting in total UT coverage of 65.2% as described in Figure 1.43-2, Figure 1.43-3 and Table 1.43-1 . A photograph of weld 14"-2-RC-21 is provided in Figure 1.43-4.

No recordable indications were detected during this scan .

Section XI Appendices and Supplements used for this UT examination were Appendix I and Article 4 of ASME Section V.

Note: No laminations were reported on the Pressurizer Lower Head that could interfere with the angle beam examinations performed on Weld 14"-2-RC-21.

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Surge Nozzle-to-Vessel Weld

-C)'--

-1 2.P -11 LD * ~ lD 2-11 Ont[

Figure 1.43-1 Weld 14"-2-RC-21 (Extracted from Reference DRAWING 2A-4)

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Surge Nozzle-to-Vessel Weld Figure 1.43-2 Weld 14"-2-RC-21 Coverage Plot

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Sur e Nozzle-to-Vessel Weld 0

q:,

Zcne 0-82.78 q. in , 1 Zcnc l - 4. 19 sq. in . 20 p Zcne 2 - 7.21 sq. in

  • 21 Za,e 3 - sq. in ** 1 are ide a .65 sq. in
16. 7 sq. in I I 13.51 sq. in JJ i
  • Area 14. sq. in Figure 1.43-3 Weld 14"-2-RC-21 Coverage Plot

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Surge Nozzle-to-Vessel Weld Side Vie Area= 16.17 sq. in. x Top View Area= 76.0" sq. In.

{16.17 X 76}

Total Volume= 1 22 8.92 cu . in.

Side View Areas Are op Vie Areas Zo Zones Exam Area Achieved/Total Area = Area x Tk x f; Areas = Ar a chieved Exa %Achi ved Exam Area Achieve cu. in.

Exam Side Areas 1e Areas 1 Areas Sq. I Achieved Area ZoneO .29 6.1 82.7S 3*

~xa c 1eved 69.8 X Exam Are c 1eved .3 = _73 _3 Zone 8.65 16.17 4 __ 9

- 20 Exam C 1e ed 53. X Exam rea Ache d 251.40 = 3~.2-!

Zone2 3.51 6. 7 7.2:l 3" 2 Exa Ac 1 ed 83.5'6 X Exam rea Achieved 23 = 379.23 Zone3 14. 6. 7 2.24 3" E a Ac , V d 90. a Area Ac eved 26. = 4.

--S.:

801.54/1228.92 = 6 5 .2% of CRV Table 1.43-1 Weld 14" RC-21 Coverage Calculation Results

1.43 Weld 14"-2-RC-21 Pressurizer Lower Head Surge Nozzle-to-Vessel Weld Figure 1.43-4 Weld 14"-2-RC-21 Component Photograph

1.44 Weld 1-PRZ-26 Pressurizer Lower Head to Support Skirt Weld Weld 1-PRZ-26 was MT examined in Inspection Period 2 during the U1C26 refueling outage in 2014. The NOE data came from MT Report No. U1-MT-14-001 . Previous ISi MT data was reviewed.

The MT Code Required Volume (CRV) was determined based on Section XI , Figure IWB-2500-

14. The corresponding CRV as shown on that Figure is A-B or C-D. The surface area examined was A-B (outside diameter of weld). The MT examination was limited by an adjacent air duct resulting in total MT coverage of 88.2% as described in Figure 1.44-2. A photograph of weld 1-PRZ-26 is provided in Figure 1.44-3.

No recordable indications were detected during this examination .

The MT examination met Section XI Paragraph IWA-2221.

1.44 Weld 1-PRZ-26 Pressurizer Lower Head to Support Skirt Weld 1* -,s 1 * 'f?Z-14 .t~.J8"

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  • 17 o* rmCM:E ea IG - PR[SSJJ 12[

Figure 1.44-1 Weld 1-PRZ-26 (Extracted from Reference DRAWING 1A-4)

1.44 Weld 1-PRZ-26 Pressurizer Lower Head to Support Skirt Weld Pressurizer 0.0. is 305.5" 36" of 1-PRZ-26 inaccessible due to ducting from 180 Deg to 270 Deg. MT Yoke would not fit between Duct and Pressurizer.

305.5" - 36" = 269.5" 269.5/305.5=.8821 88.2% Coverage Obtained Figure 1.44-2 Weld 1-PRZ-26 Coverage Calculation

1.44 Weld 1-PRZ-26 Pressurizer Lower Head to Su ort Skirt Weld Figure 1.44-3 Weld 1-PRZ-26 Component Photograph

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