ML24053A397
| ML24053A397 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/22/2024 |
| From: | Horton T Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 102-08732-TAH/MSC | |
| Download: ML24053A397 (1) | |
Text
10 CFR 54 A member of the STARS Alliance, LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek Todd A. Horton Senior Vice President Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel: 623.393.6418 102-08732-TAH/MSC February 22, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Renewed Operating License Number NPF-41, NPF-51, and NPF-74 License Renewal - Alloy 600 Management Program Plan As required by license renewal Commitment 23 in Table 19.5-1 of the Palo Verde Nuclear Generating Station (PVNGS) Updated Final Safety Analysis Report (UFSAR),
Arizona Public Service Company (APS) is providing the PVNGS Units 1, 2 and 3 Alloy 600 Management Program Plan for Nuclear Regulatory Commission (NRC) Staff review and approval. This is the inspection plan for reactor coolant system nickel alloy pressure boundary components described in license renewal Commitment 23, item A.4.
Specifically, Commitment 23, Item A, states:
Reactor Coolant System Nickel Alloy Pressure Boundary Components Implement applicable (1) NRC Orders, Bulletins and Generic Letters associated with nickel alloys and (2) staff-accepted industry guidelines, (3) participate in the industry initiatives, such as owners group programs and the EPRI Materials Reliability Program, for managing aging effects associated with nickel alloys, (4) upon completion of these programs, but not less than 24 months before entering the period of extended operation, APS will submit an inspection plan for reactor coolant system nickel alloy pressure boundary components to the NRC for review and approval (emphasis added)
The first PVNGS Unit that will enter the period of extended operation (PEO) is Unit 1, on June 1, 2025. This submittal was recognized as being made after the 24-month criterion for Unit 1 but before the 24-month criterion for Unit 2 (enter PEO on April 24, 2026), and Unit 3 (enter PEO on November 25, 2027). This oversight in meeting the Unit 1 submittal date has been entered into the PVNGS corrective action program.
As documented in the Purpose section of the Enclosure to this letter:
This plan details a comprehensive program management strategy including inspection programs, mitigation, repair and replacement options and planning.
The purpose of this plan is to maintain nuclear safety and plant reliability. This document identifies all Alloy 600 base material and Alloy 82/182 weld metal (with the exception of reactor internals) pressure boundary components and details the recommended inspection and/or repair activities for each location.
The steam generator and reactor internals are addressed in separate procedure/program documents.
102-08732-TAH/MSC ATTN: Document Control Desk U.S. Nuclear Regulatory Commission License Renewal - Alloy 600 Management Program Plan Page 2 The enclosed license renewal inspection plan reflects the culmination of a long history of industry, NRC staff, and APS efforts to address Alloy 600 material issues, including but not limited to,Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors, which was closed for PVNGS by NRC letter dated June 15, 2006 (ADAMS Accession Number ML061520459). Consistent with this closure letter, APS continues to meet the NRC staff expectation that plans for the inspection and repair of items discussed in Bulletin 2004-01, and other Alloy 600 issues, be updated consistent with other industry commitments and staff regulatory actions.
The enclosed license renewal inspection plan is based upon Alloy 600/82/182 locations identified based on vendor studies, reviews of plant drawings, modification design records, modification installation records, and corrective maintenance work orders. The examinations are scheduled as augmented examinations for the fourth Interval 10-year In-Service Inspection Program manuals for each PVNGS Unit. Mitigated items remain subject to visual examinations pursuant to the ASME Section XI, Pressure Test Program. Note that Code Cases N-722, N-729 and N-770, used in this license renewal inspection plan, may change pursuant to 10 CFR 50.55a rulemaking over time.
A pre-submittal meeting for this license renewal inspection plan submittal was held between APS and the NRC staff on August 31, 2023. Approval of the proposed inspection plan is requested by February 28, 2025. Once approved, the proposed plan will be implemented within 90 days. No new commitments are being made to the NRC by this letter.
Should you need further information regarding this letter, please contact Matthew S.
Cox, Licensing Department Leader, at (623) 393-5753.
Sincerely, TAH/MSC/cr
Enclosure:
Palo Verde Nuclear Generating Plant Units 1, 2 and 3 Alloy 600 Management Program Plan (4INT-INCO-06, Revision 2) cc:
J. D. Monninger NRC Region IV Regional Administrator W. T. Orders NRC NRR Project Manager for PVNGS L. N. Merker NRC Senior Resident Inspector for PVNGS B. D. Goretzki Arizona Department of Health Services - Bureau of Radiation Control Horton, Todd (Z10098)
Digitally signed by Horton, Todd (Z10098)
Date: 2024.02.22 11:42:47 -07'00'
ENCLOSURE Palo Verde Nuclear Generating Plant Units 1, 2 and 3 Alloy 600 Management Program Plan 4INT-INCO-06 Revision 2
Units 1, 2 & 3 Alloy 600 Management Program Plan 4INT-INCO-06 Rev. 002 Preparer License Renewal Review Level III Reviewer ISI Reviewer Approver Morgan, Nicholas (Z17355)
Digitally signed by Morgan, Nicholas (Z17355)
Date: 2024.01.31 10:11:42 -07'00' Boyd, William R(Z08404)
Digitally signed by Boyd, William R(Z08404)
Date: 2024.01.31 09:55:45 -07'00' Van Allen, David S(Z05052)
Digitally signed by Van Allen, David S(Z05052)
Date: 2024.01.31 10:07:50
-07'00' Toone, Spencer (Z07074)
Digitally signed by Toone, Spencer (Z07074)
Date: 2024.01.31 08:25:22
-07'00' Schrecker, Kenneth D(Z99981)
Digitally signed by Schrecker, Kenneth D(Z99981)
Date: 2024.01.31 12:55:23 -07'00'
- Couser, David I(ZP9657)
Digitally signed by Couser, David I(ZP9657)
Date: 2024.01.31 13:17:01 -07'00'
Page 2 of 59 1.0 Purpose The purpose of this document is to establish the Alloy 600 management plan used at Palo Verde Generating Station (PVGS) for maintaining the integrity and operability of each Alloy 600/82/182 component for the remaining life of the plant. This plan details a comprehensive program management strategy including inspection programs, mitigation, repair and replacement options and planning. The purpose of this plan is to maintain nuclear safety and plant reliability. This document identifies all Alloy 600 base material and Alloy 82/182 weld metal (with the exception of reactor internals) pressure boundary components and details the recommended inspection and/or repair activities for each location. The steam generator and reactor internals are addressed in separate procedure/program documents. This document will be reviewed and updated periodically to incorporate changes to the strategic plan and to document relevant industry experience.
2.0 Objective The main objectives of this Alloy 600 management plan are:
x Maintain plant safety x Minimize the impact of primary water stress corrosion cracking (PWSCC) on plant availability x Develop and execute short and long-term strategies for Alloy 600 management All aspects of this plan shall comply with industry and regulatory guidance for inspections and repairs. This management plan will determine options for the most cost-effective management specific to each category of components and its optimal course of action.
This document is a RCTS commitment and shall not be removed or changed without prior review by Regulatory Affairs IAW 93DP-0LC08. The RCTS commitments are as follows:
RCTSAI 3246893
[Sustainability Item] RCTSAI 3246893; Credited in the License Renewal Application (LRA) Boric Acid Corrosion Program and associated with the Boric Acid Corrosion study 13-LS-A104. Ensure each revision of this program manual is reviewed by the License Renewal Group (Unit 9798) for any effect on the LRA. This is an RCTS commitment and shall not be removed or changed without prior review by Regulatory Affairs per 93DP-0LC08.
Page 3 of 59 RCTSAI 3246894
[Sustainability Item] RCTSAI 3246894; Credited in the License Renewal Application (LRA) Nickel-Alloy Penetration Nozzles Welded to The Upper Reactor Closure Heads of Pressurized Water Reactors Program and associated with the Nickel-Alloy Penetration Nozzles study 13-LS-A105. Ensure each revision of this program manual is reviewed by the License Renewal Group (Unit 9798) for any effect on the LRA. This is an RCTS commitment and shall not be removed or changed without prior review by Regulatory Affairs per 93DP-0LC08.
RCTSAI 3260208
[Sustainability Item] RCTSAI 3260208; Credited in the License Renewal Application (LRA) Nickel Alloy Aging Management Program and associated with the Nickel Alloy Aging Management study 13-LS-A134. Ensure each revision of this program manual is reviewed by the License Renewal Group (Unit 9798) for any effect on the LRA. This is an RCTS commitment and shall not be removed or changed without prior review by Regulatory Affairs per 93DP-0LC08.
RCTSAI 3246929
[Sustainability Item] RCTSAI 3246929; Credited in the License Renewal Application (LRA) Nickel Alloy Aging Management Program and associated with the Nickel Alloy Aging Management study 13-LS-A134. Ensure each revision of this program manual is reviewed by the License Renewal Group (Unit 9798) for any effect on the LRA. This is an RCTS commitment and shall not be removed or changed without prior review by Regulatory Affairs per 93DP-0LC08.
Responsibilities Programs Engineering Department has the overall responsibility for the development and implementation of the Alloy 600 management plan. See applicable procedures below:
81DP-9RC03 -PVGS Integrated Materials Management Program 73TI-9RC09 -Bare Metal Visual Examination of Reactor Vessel Upper Head 73TI-9RC10 - Bare Metal Visual Examination of Reactor Vessel Lower Head 73DP-9XI03 - ASME Section XI In-service Inspection 73DP-9XI08 - Conduct of Dissimilar Metal Weld Ultrasonic Examinations
Page 4 of 59
3.0 Background
Throughout the industry, many reactor coolant system nozzles, welds and welded attachments such as instrument nozzles, nozzle safe ends, heater sleeves in pressurizer vessels, and control rod drive penetrations and bottom mounted instrumentation nozzles in reactor vessels were manufactured from Alloy 600 material.
Alloy 600 and its associated weld material, Alloy 82 and 182, are susceptible to PWSCC. PWSCC has been observed in these components along with its associated j-welds and full penetration butt-welds.
For these reasons, the industry along with the EPRI Materials Reliability Program (MRP) deemed it necessary that every plant should have an overall plan for managing Alloy 600 primary water stress corrosion cracking degradation. The current practice for Alloy 600 locations is summarized in Attachment 1. This Alloy 600 management plan provides additional direction for the administering Alloy 600/82/182 inspections, preventative actions, and developing contingency repair plans.
4.0 Strategic Planning Palo Verde has proactively replaced all of the Alloy 600 pressurizer and hot leg instrument nozzles in each Unit with Alloy 690 nozzle material. In addition, all pressurizer heater sleeves (36 per Unit) have been replaced using Alloy 690 materials and welded using Alloy 52 or 52M filler materials.
Palo Verde has replaced the Reactor Vessel Heads in all three (3) units with heads having Alloy 690 nozzle material and welded using Alloy 52 filler material. The bottom mounted instrumentation nozzles bare metal examination area of interest was obstructed by Spraylat coating. This coating was cleaned using Carbon Dioxide (CO2) cleaning process co-developed by PVGS which allows a full bare metal inspection of each of the nozzles.
Weld overlays have been implemented for the more susceptible dissimilar metal (DM) welds and those with issues affecting inspection capabilities and implemented as early as the fall of 2007. The Mechanical Stress Improvement Process (MSIP) and full structural weld overlays were evaluated as mitigation options for unmitigated DM butt welds. However, the site is performing 100% inspections of unmitigated butt welds in lieu of MSIP or full structural weld overlays based on OE reviews and low probability of flaws developing in the unmitigated welds.
Page 5 of 59 5.0 Alloy 600 Locations Table 1: Alloy 600 Locations Component Number Per Unit Reference Section Reactor Pressure Vessels Bottom Mounted Instrument Nozzles (61 In-core Instrumentation Penetrations in Units 1 and 2. 60 In-core Instrument Penetrations in Unit 3),
Flange Leak off line 6.2, 6.7 Pressurizers 4 DM welds (PZR Safeties) 1 DM weld (PZR Spray) 1 DM weld (PZR Surge) 6 replacement instrumentation nozzles Unit 1*, 7 replacement instrument nozzles Unit 2* and 3*
6.3 RCS Piping 12 CL nozzles, 8 RCP instrument nozzles in Units 1 and 2 (7 in Unit 3 after RCP 2A repair with 690), DM weld (PRZ Surge), 2 DM welds Shutdown Cooling 8 HL instrumentation nozzles Unit 2*
6.4, 6.5 Steam Generators Tubesheet cladding, Nozzle Dam Retention Rings, Cladding, 4 CL instrumentation nozzles in Unit 1 and 3*
6.6
Some replacement nozzles were welded using Alloy 82 or Alloy 82/182 materials remain as part of the pressure boundary, See App. B Alloy 600/82/182 locations have been identified at Palo Vere based on vendor studies and reviews of plant drawings, modification design records, modification installation records, and corrective maintenance work orders. Reference App. B for a listing of mitigated partial penetration welds as some of the mitigated Alloy 690 nozzle locations still contain Alloy 82/182 pressure boundary materials.
5.1 Reactor Pressure Vessel (RPV) - Upper Head Penetrations The Reactor Vessel Heads in all three (3) units have been replaced with heads containing Alloy 690 nozzles at all CEDM locations/penetrations and welded using Alloy 52 filler material. Inspections will continue to be performed in accordance with ASME Code Case N-729-6 or the conditions of the latest revision to 10 CFR 50.55a.
5.2 Bottom Mounted Instrument (BMI) Nozzles The Unit 1 and Unit 2 reactor vessel bottom head includes 61 Alloy 600
Page 6 of 59 nozzles for In-core instrumentation (ICI). Each nozzle consists of a nominal 3.001-inch outside diameter (OD) welded to the inside surface of the reactor vessel with partial penetration J-welds and Alloy 182 filler material. The inside diameter (ID) of the nozzle measures 0.750 inch. The clearance (gap) of the nozzle to vessel bore is 0.002 to 0.008 inches. The nozzles were fabricated using ASME SB-166 and supplied by Teledyne Allvac for Unit 1 and Carpenter Technology for Unit 2.
The Unit 3 reactor vessel bottom head includes 61 nozzles, of which 60 nozzles of the reactor bottom head ICI nozzles are Alloy 600 material. The original 60 nozzles consist of a nominal 3.001-inch outside diameter (OD) welded to the inside surface of the reactor vessel with partial penetration J-welds and Alloy 182 filler material. The ID is 0.750 inch. The clearance (gap) of the nozzle to vessel bore is 0.002 to 0.008 inches. The penetrations were fabricated from ASME SB-166 and supplied by Teledyne Allvac for Unit 3.
On April 12th, 2003, boron deposits were discovered on two bottom mounted instrumentation (BMI) penetrations on the reactor pressure vessel (RPV) at South Texas Unit 1. As a result of this event the Nuclear Regulatory Commission issued bulletin 2003-02 strongly recommending that nuclear plants perform a bare-metal visual inspection of their bottom mounted instrumentation penetrations of their reactor pressure vessel during the next refueling.
Prior to the fall 2003 refueling outage, the Boric Acid Corrosion Prevention Program did not include the Alloy 600 ICI penetrations on the bottom of the reactor vessel as principle potential leak sites because these nozzles and nozzle welds were considered to be of low susceptibility to PWSCC.
However, when APS did access the area between the reactor vessel bottom head and the insulation package during the Unit 3 spring outage to support planning and preparation for future examinations of the bottom instrumentation nozzles. During this data gathering effort, it was discovered that nearly all the nozzles had remnants of Spraylat protective coating left from construction. In many cases, the coating created problems for a bare metal visual examination of 100% of the circumference of each nozzle penetration as it enters the RV lower head.
APS proactively cleaned the nozzle-head interface area having this condition. 100% of the nozzles in Unit 2 & 3 have been cleaned and examined bare metal. Unit 1 did not require cleaning of the BMI and 100%
bare metal examinations were performed.
On October 6th, 2013 boron deposits were discovered on bottom mounted nozzle instrumentation (BMI) penetration number 3 on the reactor pressure vessel in Unit 3. Therefore, Unit 3 includes one (1) penetration that has been repaired utilizing the half-nozzle repair technique. The
Page 7 of 59 replacement nozzle is composed of Alloy 690 material and is welded in with Alloy 52M material. The Alloy 690 nozzle inner and outer diameters are 0.75 inches and 3 inches, respectively (unchanged from existing design), and the nozzle was sized in length to extend outward from the bottom of the reactor vessel the same relative distance as the original Alloy 600 nozzle.
5.3 Pressurizer The Palo Verde pressurizers are each designed with seven instrument nozzles and 36 heaters; four steam space nozzles in the upper head, one water space nozzle in the lower shell, two water space nozzles in the lower head and 36 heater sleeves in the lower head. Since the temperature effect is considered the dominant factor for PWSCC, (temperature of 653oF) the pressurizer components have the highest susceptibility. All the instrument nozzle locations and heater sleeves have been replaced with Alloy 690 base material by either the full nozzle or half nozzle replacement techniques, respectively. Six (6) of the Unit 1 pressurizer instrument nozzles were attached to the pressurizer using Alloy 82 filler material in 1992, as the equivalent Alloy 690 filler material (Alloy 52/Alloy 152) was not commercially available at the time of the repair.
Unit 2 and 3 Alloy 690 instrument nozzle attachment welds and temper bead pads in the water space utilized Alloy 52 filler materials to attach the nozzles to the pressurizer. However, the steam space nozzles Alloy 52 filler material are welded to Alloy 82/182 materials exposed to the RCS atmosphere. The water space nozzles in Units 2 and 3 include Alloy 52 temper bead weld pads and Alloy 690 corrosion sleeves autogenously welded to the original Alloy 82/182 ID J-groove weld.
All replacement pressurizer instrument nozzles installed in the 1990s (Units 1,2,3) have stainless safe ends welded to the Alloy 690 nozzles with Alloy 82 filler material, reference App. B. All pressurizer instrument nozzles except the Unit 1 TW101 remain in the Alloy 600 program due to the pressure retaining Alloy 82 welds.
On October 9, 2023, classical boric acid leakage was identified emanating from the Alloy 82 weld that attaches the Thermal Well Nozzle, TW101 to an Alloy 82 weld pad, in Unit 1. A VE examination and isotopic analysis confirmed that the leakage was from the RCS. The Alloy 82 weld pad, Alloy 82 groove weld and part of the corrosion sleeve was removed along with the TE-101 nozzle for failure analysis. After final removal of the Alloy 82 weld pad to the pressurizer OD surface, a new Alloy 52M weld pad was installed using an ambient temperature temper bead weld process per
Page 8 of 59 Code Case N-632. An Alloy 690 nozzle was installed on the weld pad using Alloy 52M filler material. As part of the repair, the corrosion sleeve was left in place but machined back and no longer part of the TW-101 nozzle to pad weld joint provided by the 1992 mitigation configuration.
The pressurizer heater sleeves have been replaced with Alloy 690 using a half nozzle technique and Alloy 52 and Alloy 52M weld pads with a few of the heater locations plugged. No Alloy 82/182/600 pressure retaining material remain in either Unit 1, 2 or 3.
5.4 RCS Dissimilar Metal Butt-Welds Dissimilar metal butt-welds are located throughout the reactor coolant system to connect stainless steel to carbon steel or low alloy steel.
Dissimilar metal welds are typically made using an Alloy 182 buttering layer on the carbon steel or low alloy steel nozzle end. The stainless steel pipe is then fitted up to the buttered nozzle and Alloy 82/182 was used for the filler material. Alloys 82 and 182 are similar in composition to Alloy 600 and both have been demonstrated to be susceptible to PWSCC. Two plants have identified leakage and two plants have identified cracking in dissimilar metal butt welds. Most of the identified cracking to date has been in the axial direction however, a small shallow circular crack was found at VC Summer, but had arrested when it reached the carbon steel nozzle.
The dissimilar metal butt-welds which are addressed in this program are those greater than or equal to 1 NPS in locations operating at cold leg temperature or higher, these key locations are provided in Table 2. The Alloy 600 material locations at lower than cold leg temperatures are not subject to increased augmented inspections/replacements at this time because of the lower PWSCC susceptibility at lower service temperatures.
Page 9 of 59 Table 2: Dissimilar Metal Butt Welds Component Diameter (inches)
Typical Temperature (oF)
PZR Surge (PZR Side) 12 653 PZR Surge (HL Side) 12 616 Shutdown Cooling 1 16 616 Shutdown Cooling 2 16 616 Safety Injection 1A 14 557 Safety Injection 1B 14 557 Safety Injection 2A 14 557 Safety Injection 2B 14 557 PZR Spray 1A 3
557 PZR Spray 1B 3
557 PZR Spray 4
653 PZR Safety V200 8
653 PZR Safety V201 8
653 PZR Safety 202 8
653 PZR Safety V203 8
653 Drain Line 1A 2
557 Drain Line 1B 2
557 Drain Line 2A 2
557 Letdown Line 2
557 Charging Line 2
557 5.5 RCS Piping Instrument Nozzles Each unit at PVGS was designed with 27 hot leg instrument nozzles (service temperature is 611-6160F). The hot leg nozzles consist of 18 resistance temperature differential (RTD) nozzles of which 8 are spares and 8 pressure measurement nozzles and 1 sample nozzle. Except for eight pressure instrument nozzles in Unit 2, the 10 RTD nozzles, 8 pressure measurement nozzles and the sample nozzle have been replaced with Alloy 690 using the half-nozzle repair using the Alloy 52 filler metal. The 8 spare RTD nozzles were plugged using 690 material and are no longer in service. The eight (8) pressure measurement nozzles in Unit 2 were replaced in 1991 with full nozzle replacements and external attachment weld to the outside surface using Alloy 82 filler material as Alloy 52 and Alloy 152 was not commercially available at the time of the repair.
There are three (3) RTD nozzles in each of the cold legs (A total of 12 in each unit) and 2 instrumentation taps in the suction and discharge lines of the RCP (A total of 8 in each unit). All original cold leg nozzles are Alloy 600 base material welded to the RCS piping/pump using Alloy 82/182 filler materials. The Cold Leg temperature is approximately 557oF. The temperature of the RCP instrumentation taps is at or near cold leg temperatures.
Page 10 of 59 On April 6, 2015, white residue was identified in the annulus and on the piping around the instrument tap on the suction side of RCP 2A (Line 3PRCEL075) in Unit 3. Isotopic analysis confirmed that the leakage was from the RCS. This was considered the first failure of a cold leg instrument nozzle due to PWSCC. The Unit 3 RCP 2A suction nozzle was corrected with a half nozzle repair. The replacement nozzle, manufactured by Westinghouse using Alloy 690 material and the external j-groove weld with 52M filler material to mitigate reoccurrence of a PWSCC failure.
On April 11, 2016, classical boric acid leakage was identified emanating from the annulus between the RCS Cold Leg Piping and the 2B RTD 121 Y Nozzle, in Unit 1. Isotopic analysis confirmed that the leakage was from the RCS. Based on the nozzle design, it was determined that the best course of action was to apply a Mechanical Nozzle Sealing Assembly (MNSA) to seal the annulus area. ASME Section XI Code Case N-733 allows for the installation of the MNSA without further NRC approval to start up. The MNSA is currently installed and analyzed for 40 years of operation. This 40-year duration extends past the current operating license and period of extended operation for Unit 1 that is scheduled thru June 1, 2046.
5.6 Steam Generator Each unit at PVGS has two (2) steam generators. The steam generators were replaced in 2R11, 1R12 and 3R13. Although the tubing of the replacement steam generators is manufactured from Alloy 690, the tubesheet and nozzle dam retaining rings were cladded using Alloy 82 weld material, which contains Alloy 600 material. The divider bars (which hold the floating primary side divider plate in place) are also made from Alloy 600 material in Unit 2 only. The welds that connect the divider bars to the SG bowl used Alloy 82 weld material, in all 3 units. These steam generator components are monitored by the steam generator program.
There are also four (4) instrumentation lines on the primary bowl on the cold leg side that were also welded with Alloy 82 butter in Units 1 and 3, Ref App. B and only steam generator components managed by the Alloy 600 program.
5.7 Reactor Vessel O-Ring Flange Leak-Off Line The reactor vessel O-ring flange leak-off line has an Inconel 600 pad weld.
The tube normally operates dry and is only filled with water in the event an o-ring seal develops a leak. PWSCC is not likely a concern with this
Page 11 of 59 component and excluded from the Alloy 82/182/600 examination scope of code case N-722-1.
6.0 Alloy 600 Inspection Program The examinations are schedule as augmented exams for the 4th Interval 10-year ISI Program manuals 4INT-ISI-1, 4INT-ISI-2 and 4INT-ISI-3. Mitigated items are still subject to VT-2 exams per the ASME Section XI, Pressure Test Program. Note that Code Cases N-722-x, N-729-x and N-770-x may change per updated versions of 10CFR50.55a.
6.1 Reactor Pressure Vessel (RPV) - Upper Head Penetrations The Reactor Vessel Heads in all three (3) units have been replaced and contain Alloy 690 nozzles and welded using PWSCC resistant filler materials. The reactor pressure vessel upper head are examined in accordance with ASME Code Case N-729-6 subject to the conditions specified in the latest revision of 10 CFR 50.55a. The rules and regulations of 10CFR 50.55a imposes inspection requirements for the RPVH penetrations. All three (3) PVGS Units shall be subjected to the following:
Reactor Vessel Head Bare Metal Visual Inspection (CC N729-6 every third refueling outage or 5 calendar years whichever is less)
Unit Head Replacement 1
1R15 2
2R15 3
3R15 Reactor Vessel Head Volumetric or Surface Exams (CC N729-6 extended one inspection interval nominally 20 calendar years)
Unit Head Replacement 1
1R15 2
2R15 3
3R15 NDE inspections include volumetric or surface examinations consistent with the code case and as modified by 10CFR50.55a.
Page 12 of 59 6.2 Bottom Mounted Instrumentation (BMI) Nozzles The response to Bulletin 2003-02, APS performed bare-metal visual examinations of the Reactor Pressure Vessel (RPV) lower head penetrations of Unit 2 Fall 2003, Unit 1 Spring 2004, Unit 3 Fall 2004 and subsequent outages until a complete as found bare-metal examination of all Bottom Mounted Instrument (BMI) penetrations has been performed in all three units. All the Unit 2 & 3 nozzles in have been cleaned and examined bare metal. Unit 1 did not require cleaning and 100% bare metal examinations were successfully performed.
Based on the leakage identified on Penetration number 3 during U3R17, APS performed 100% bare metal visual examination of 100% of the bottom mounted instrument nozzles every outage. This practice was utilized for 2 outages in each unit. Satisfactory results led to the relaxation of the inspection periodicity to re-align with the code requirements, every other outage. The decision to re-align the inspection periodicity can be found in Engineering Evaluation 4685204. Examinations are conducted per Code Case N-722-1 and subject to the conditions specified in paragraphs (g)(6)(ii)(E)(2) through (4) of 10 CFR 50.55a.
6.3 Pressurizer All four of the steam space instrumentation nozzles have been replaced with Alloy 690 nozzles with an internal attachment weld in all three (3) units. All steam space instrument nozzles contain Alloy 82/182 pressure retaining materials at the ID attachment welds and nozzle to safe end welds. The pressurizer steam space instrument nozzles are subject to examination each refueling outage per code case N-722-1, reference App.
B for weld details.
A water space instrument nozzle in the lower shell and two water space instrument nozzles in the lower head are replaced with Alloy 690 nozzles in all three (3) units. The two lower head replacement nozzles in Unit 1 were welded using Alloy 82 filler material for the temper bead pads, nozzle to pad attachment and nozzle to safe end welds. Unit 2 and Unit 3 were welded using Alloy 52 filler material for all three water space nozzles including the weld temper bead pads and the nozzle to pad welds. The Alloy 690 and Alloy 52 filler materials are subject to examinations per code case N-722-1, however the nozzle to safe end Alloy 82 welds are subject to inspections every refueling outage.
Page 13 of 59 TW101 water space nozzle location was replaced in 1R24 with an Alloy 690 nozzle and Alloy 52M welds and no longer subject to code case N-722-1 examinations.
The pressurizer heater sleeves were preemptively mitigated with Alloy 690 and Alloy 52 and Alloy 52M filler material and not subject to N-722-1 exams, Ref App B for material specifics.
6.4 RCS Dissimilar Metal Butt-Welds The current inspection requirements for dissimilar metal welds reside in ASME Section XI Code Case N-770-5 as conditioned by 10CFR50.55a.
TABLE 3: RCS Dissimilar Metal Butt Welds Component N-770-5 Inspection Item Exam Extent And Schedule (Note 3)
PZR Surge (PZR)
See Note 1 F-1 Once during the first or second refueling outage following overlay. Weld overlay examination volumes that show no indication of crack growth or new cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be added to the ISI Program and shall be examined once each inspection interval or the life of the weld overlay or as supported by design calc.
PZR Surge (HL)
See Note 2 F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
SD Cooling 1 F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
SD Cooling 2 F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
SI 1A B-2 Once per interval, not to exceed 13 years between examinations SI 1B B-2 Exam extent and schedule for Inspection Item B-2 applies as noted previously.
SI 2A B-2 Exam extent and schedule for Inspection Item B-2 applies as noted previously.
SI 2B B-2 Exam extent and schedule for Inspection Item B-2 applies as noted previously.
Page 14 of 59 Component N-770-5 Inspection Item Exam Extent And Schedule (Note 3)
PZR Spray 1A B-1 Once per interval, every second period not to exceed 7 years PZR Spray 1B B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
PZR Spray See Note 2 F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
PZR Safety F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
PZR Safety F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
PZR Safety F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
PZR Safety F-1 Exam extent and schedule for Inspection Item F-1 applies as noted previously.
Drain Line 1A B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
Drain Line 1B B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
Drain Line 2A B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
Letdown Line B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
Charging Line B-1 Exam extent and schedule for Inspection Item B-1 applies as noted previously.
Note 1: The Overlay for the Pressurizer Surge Nozzle requires a re-exam at a 3 year frequency following the initial exams, pending publication of N001- 0607-00480 with a 10 year frequency, Ref. 8.25 Note 2: The Overlay for the Pressurizer Surge Nozzle (HL) requires a re-exam at a 6 year frequency following the initial exams with a pending publication of N001- 0607-00481 with a 10 year frequency, Ref 8.26 Note 3: The requirement to prepare, maintain and execute a surface condition assessment is provided in Appendix A (applies to all dissimilar metal welds) 6.5 RCS Piping Instrument Nozzles In 1991, eight (8) instrumentation nozzles were replaced in Unit 2 with Alloy 690 full nozzle replacements and attached to the outside surface of the hot legs using Alloy 82 filler materials. These nozzle locations are subject to examination each refueling outage per code case N-722-1, reference App. B for nozzle locations.
All other hot leg RCS piping instrument nozzles have been replaced with Alloy 690 and Alloy 52 weld materials and no longer subject to examinations per code case N-722-1.
As of December 31st, 2008 APS performs bare metal examination of 100%
of the Alloy cold leg nozzles once per interval in accordance with Code Case N-722-1. The Unit 1 MNSA exam is performed each refueling outage.
Page 15 of 59 Bare metal inspections on the Alloy 600 RCP pressure instrument taps are also performed once per interval in accordance with Code Case N-722-1.
The Unit 3 RCP suction nozzle to 3PRCEL075 is no longer subject to N-722-1 exams as the instrument nozzle is Alloy 690 welded to the pump with Alloy 52 filler materials.
6.6 Steam Generators All inspections performed on the steam generators follow the guidance documents under the Steam Generator Management Program.
The instrument lines on the Primary bowl on the Cold Leg side in Units 1 and 3 are examined once per interval in accordance with Code Case N-722-1, Unit 2 is not subject to examination as the instrument lines do not contain Alloy 82/182/600 materials.
6.7 Reactor Vessel O-Ring Flange Leak-Off Line The tube normally operates dry and is only filled with water in the event an o-ring seal develops a leak. PWSCC is not likely a concern with this component. The Alloy 600/82/182 materials in the leak off lines are not subject to examinations per Code Case N-722-1.
7.0 Repair Techniques There have been five (5) repair techniques used at PVGS to mitigate leaks or preemptively replace susceptible Alloy 82/182/600 pressure retaining materials. The first repair technique, pressurizer steam space nozzles have all been replaced with Alloy 690 nozzles, installed with an internal J-groove weld in accordance with the original design. The second repair technique, pressurizer water space nozzles were repaired using a full nozzle replacement with an external temper bead pad weld. The third repair technique, eight (8) hot leg instrument nozzles in Unit 2 were replaced using a similar full nozzle repair but with an external attachment weld done directly on the outside surface of the pipe. The fourth repair technique, the remaining RCS hot leg piping instrument nozzles and pressurizer heater sleeves have been repaired with the half nozzle technique, some using temper bead pads when welded to P3 materials and no temper bead pad when welded to P1 materials. The fifth repair technique uses a Mechanical Nozzle Seal Assembly (MNSA) on emergent basis when leakage has occurred. The three repair techniques described in greater detail below include likely mitigation strategies if future leaks are discovered.
7.1 Half-Nozzle Repair Technique
Page 16 of 59 The half-nozzle repair technique has been utilized for all RCS piping instrument nozzles (except for eight instrument nozzles in Unit 2 replaced in 1991) and the pressurizer heater sleeves. In October 2013, this technique was utilized to repair BMI Nozzle number 3 in Unit 3 after leakage indications were present during the bare metal visual examinations. The technique was also utilized in April 2015 on an instrument tap on the suction RCP 2A in Unit 3 when leakage indications were present during bare metal visual inspections.
The original nozzle is cut off outside the piping or vessel and a temporary plug is installed deep in the nozzle to prevent foreign material from entering the RCS. The outer portion of the nozzle is then machined out by drilling. The inner portion of the nozzle is abandoned in place and a new Alloy 690 half nozzle is installed and welded to the piping or vessel outside diameter. This new weld meets ASME Code Section III & XI requirements and is structurally qualified for the life of the plant. In the case of the RCS piping, the weld prep for the external weld can be made directly to the outside surface of the pipe surrounding the nozzle. For the heater sleeves, a temper bead pad build up is required first, and then the weld prep is cut in the weld pad. The time and expense required to complete a half nozzle repair on the pressurizer is significantly greater than that required for the RCS piping.
There is a small gap left between the original nozzle and the new Alloy 690 half nozzle to accommodate differential thermal expansion. This gap also allows borated reactor coolant to come in direct contact with the low alloy steel parent material in the pressure vessel or carbon steel piping.
Low alloy or carbon steel in contact with borated water has the potential to corrode. The effects of boric acid corrosion were evaluated and determined to be acceptable.
7.2 Full-Nozzle Replacement The four (4) steam space nozzles on the pressurizers were repaired using a full-nozzle replacement with an internal j-weld (like for like replacement).
The pressurizer water space nozzles were attached with a temper bead pad weld. The eight instrument nozzles on the RCS piping in Unit 2 were full-nozzle replacements with an external attachment directly on the outside surface of the pipe surrounding the nozzle.
The October 2023 replacement of TW101 in Unit 1 utilized a Full-Nozzle Replacement welded to a temper bead pad.
7.3 Mechanical Nozzle Seal Assembly (MNSA)
Page 17 of 59 MNSAs are designed to provide an external seal for Alloy 600 instrument nozzles as an alternative repair option to the half nozzle design. A MNSA can be installed with water in the system; however, the RCS should be depressurized prior to installation for personnel safety. A Grafoil seal is compressed against the nozzle to vessel crevice and the assembly is retained by a bolted assembly threaded in the applicable vessel or RCS piping. The pressure boundary is essentially moved from the original attachment weld to the Grafoil seal on the outside diameter of the vessel.
Currently, there is one MNSA installed at PVGS. In April of 2016, a MNSA was installed per code case N-733 to seal leakage identified on the 2B Cold Leg RTD in Unit 1.
Page 18 of 59 8.0 References 8.1 ASME Code 2013 edition 8.2 Generic Guidance for Alloy 600 Management (MRP-126), Letter MRP 2004-053 to US PWR Chief Nuclear Officers.
8.3 Materials Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126), EPRI, Palo Alto, CA:: 1009561.
8.4 Materials Handbook for Nuclear Plant Pressure Boundary Applications, EPRI, Palo Alto, CA:, 1002792.
8.5 U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials, NUREG-1823.
8.6 Appendix A, General Design Criteria for Nuclear Power Plants, Code of Federal Regulations, Section 10 Part 50 (10CFR50).
8.7 Guideline for the Management of Material Issues, Nuclear Energy Institute, NEI 03-08.
8.8 Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors, NRC Order EA-03-009.
8.9 Needed Action for Visual Inspection of Alloy 82/182 Butt Welds and Good Practice Recommendations for Weld Joint Configurations, Letter MRP 2004-05 from Leslie Hartz to all PWR Owners.
8.10 Materials Reliability Program: Primary System Piping Butt Welds Inspection and Evaluation Guideline (MRP-139,), EPRI, Palo Alto, CA:
1015009.
8.11 Materials Reliability Program: Suitability of Emerging Technologies for Mitigation of PWSCC (MRP-118), EPRI, Palo Alto, CA:. 1009500.
8.12 Materials Reliability Program: Evaluation of the Capabilities and Limitations of Existing Technologies for Mitigation of PWSCC (MRP-122),
EPRI, Palo Alto, CA:. 1009504.
8.13 APS Letter # 102-05130-CDMSAB/RJR, APS 60-Day Response to the information Requested by NRC Bulletin 2004-01.
8.14 LTR-PCAM-06-57, Palo Verde Unit 1-PA-MCS-0233, Task 2 Primary Pressure Boundary Alloy 600/82/182 Fabrication Details.
8.15 LTR-PCAM-06-58, Palo Verde Unit 2-PA-MCS-0233, Task 2 Unit 2 Primary Pressure Boundary Alloy 600/82/182 Fabrication Details.
8.16 LTR-PCAM-06-59, Palo Verde Unit 3-PA-MCS-0233, Task 2 Unit 3 Primary Pressure Boundary Alloy 600/82/182 Fabrication Details.
8.17 PA-MCS-0233, Task 2 Unit 2 Primary Pressure Boundary Alloy 600/82/182 Fabrication Details.
Page 19 of 59 8.18 10 CFR 50.55a, Codes and Standards; Final Rule, effective date September 25, 2023.
8.19 ASME BPV Code Case N-770-5 ASME BPV Code Case N-770-5, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation ActivitiesSection XI, Division 1" per 10 CFR Part 50, Industry Codes and Standards; Amended Requirements; Final Rule.
8.20 ASME BPV Code Case N-729-6. ASME BPV Code Case N-729-6, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration WeldsSection XI, Division 1" per 10 CFR Part 50, Industry Codes and Standards; Amended Requirements; Final Rule.
8.21 ASME BPV Code Case N-722-1. ASME BPV Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials,Section XI, Division 1" (Approval Date: January 26, 2009), with the conditions in paragraph (g)(6)(ii)(E) of 10CFR50.55a.
8.22 13-LS-A104, PVGS Aging Management Program Evaluation Report -
Boric Acid Corrosion - B2.1.4, NUREG 1801 Program XI.M10 credits this document for implementing portions of this License Renewal Aging Management Program.
8.23 13-LS-A105, PVGS Aging Management Program Evaluation Report -
Nickel-Alloy Penetration Nozzles Welded To The Upper Reactor Vessel Closure Heads of Pressurized Water Reactors - B2.1.5, NUREG 1801 Program XI.M11B credits this document for implementing portions of this License Renewal Aging Management Program.
8.24 13-LS-A134, PVGS Aging Management Program Evaluation Report -
Nickel Alloy Aging Management - B2.1.34, PSNI credits this document for implementing portions of this License Renewal Aging Management Program.
8.25 N001- 0607-00480 - 2000645.316, Rev. 0. Updated Crack Growth Analysis of Pressurizer Surge Nozzle Full Structural Weld Overlays.
(Pending surge line overlay exams may be adjusted accordingly when official in SWMS) 8.26 N001-0607-00481 - 2000645-346, Rev. 0. Updated Crack Growth Analysis of Hot Leg Surge Nozzle Full Structural Overlay (Pending surge line overlay exams may be adjusted accordingly when official in SWMS)
Page 20 of 59 Table 1 - Table summary of locations, current examination methods, failure experience, Mitigation and Planed Replacement/Mitigation if leakage is detected.
Component Current Examinations Failure History Repair or Replacements Mitigation Strategy Planned Replacements/
Mitigation Reactor Pressures Vessel (RPV)
RPV Upper Head Penetrations VE, UT, ET No CEDM indications.
U2 vent line indications 2R12 U2 vent line indications repaired by machining.
Followed by removal and rewelding None RVH replacements completed in all three (3) units Bottom Mounted Instrument Nozzles (BMI)
Bare metal visual examination (VE)
Unit 3, penetration
- 3 leakage identified during U3R17 Unit 3, penetration
- 3 repaired with 1/2 nozzle technique 1/2 nozzle repair only MNSA Pressurizer Nozzles Pressurizer instrument nozzles Bare metal visuals (VE)
U1 1991 U1 2023-TW101 Alloy 82 weld leaking Replaced steam space and Water Space Nozzles in 1990s. 2023 Repair removed TW101, Alloy 82 welds installing a new Alloy 690 nozzle with Alloy 52M Filler Materials None Complete*
Pressurizer heater sleeves Bare Metal Visuals (VE) 3 leaking nozzles, 6 circ & 6 axial indications (not leaking)
Preventively replaced all PZR sleeves (All 3 units) using external pad and partial nozzle replacement.
Note: early repairs by plugging and welding with Alloy 82 was performed prior to preemptively mitigating, however these nozzles in Unit 2 are now mitigated with PWSCC resistant material (Ref. App. B, Table 2.1)
None Completed
- Root cause investigation under way for Unit 1 TW101, corrective actions to be driven by root cause investigation.
Page 21 of 59 Component Current Examinations Failure History Repair or Replacements Mitigation Strategy Planned Replacements
/Mitigation Dissimilar Metal Welds PZR Spray Bare metal
- visuals, UT,PT No Failures None Structural Weld Overlay Completed PZR Safeties Bare Metal Visuals (VE),
UT, PT No failures None Structural Weld Overlay Completed Surge Line (HL & PZR Side)
Bare metal visuals (VE),
UT No failures None Structural weld Overlay Completed PZR Spray 1A & 1B Bare metal visuals (VE),
UT No failures None Structural Weld Overlay Complete Shutdown Cooling 1 & 2 Bare metal Visuals (VE, UT No Failures None Structural Weld Overlay Completed Safety Injection lines Bare metal visuals (VE),
UT No failures None None None Drain Line 1A
& 1B Bare metal visuals (VE),
UT No failures None None None Drain Line 2A Bare metal visuals (VE),
UT No failures None None None Letdown Line Bare metal visuals (VE),
UT No failures None None None Charging Line Bare metal visuals (VE),
UT No failures None None None RCS Piping Instrument Nozzles 27 Hot Legs Bare metal visuals (VE) 5 cracked
- nozzles, suspect PWSCC Preventively replaced all 27 nozzles in 3 units using partial nozzle replacement with OD j-weld None Complete 12 Cold Legs Bare metal visuals (VE) 2B Cold Leg RTD in Unit 1 MNSA installed, Unit 1
MNSA MNSA RCP Instrument taps Bare metal visuals (VE)
Unit 3 2A Cold Leg DP XMTR failure indications during 3R18 Unit 3 RCP 2A suction half-nozzle repair with external J-groove weld 1/2 nozzle repair Half Nozzle Repair Steam Generator Instrument Nozzles 4 Cold Leg Bare Metal (VE)
No failures None None MNSA
Page 22 of 59 APPENDIX A This appendix has been maintained for historical purposes. Historical pictures of Unit 2 DM Nozzle welds prior to weld prep and full structural weld overlay where applicable.
Unmitigated welds have been prepped for examination in each unit and have been successfully examined in the previous interval(s).
Discussion This Appendix provides the methodology for the execution of a surface condition assessment for DMWs. The actions to implement successful preparation and subsequent execution for DMW examinations include, but are not limited to; Preparation, maintenance, and execution of a surface condition assessment and improvement process Walkdown inspections to measure the as-built configuration and surface condition and to estimate examination coverage Procedure qualification review - Appendix VIII qualified procedures and alternatives Performance of prejob briefs to address work scope, prerequisites, limitations, safety, sequence of tasks, roles and responsibilities, ALARA, lessons learned and site and industry operating experience and any other special requirements to ensure safe, reliable and efficient execution of the task.
Readiness to perform additional surface preparation, contingency examinations, and vendor oversight during outages Prompt review and disposition of examination results Contingency plans should be developed in conjunction with implementation of surface condition assessment process. This could include flaw evaluation to disposition flaws, weld overlay, mechanical stress improvement, etc.
Surface Condition Assessment The following shall be performed as part of each sites surface condition assessment Detailed weld history including as-built dimensional information, and previous examination data should be collected and reviewed. The collected as-built dimensional information should be used to provide a preliminary computation of achievable examination coverage.
Additionally, where encoded examinations have been performed previously, the site should also include a review of the previously collected data to ensure adequate data quality and coverage was obtained.
Page 23 of 59 DM welds that have not been examined in accordance with ASME Section XI, Appendix VIII previously, a walkdown inspection to verify the as-built configuration, assess the surface condition, and estimate examination coverage shall be implemented as part of the surface condition assessment process. Existing plant work-control processes to schedule and track the performance of DMW walkdowns should be used.
Walkdowns should be performed using the guidance provided in the attached DM Weld Walkdown Instructions.
The results of the walkdowns should be used to develop detailed characterization of the weld configuration, thicknesses, and surface condition for each weld that is scheduled for examination. An initial computation of achievable examination coverage should be completed.
A review of the walkdown and weld history information will assist in determining if additional actions may be needed and assist in scheduling and tracking the actions.
If the review of the walkdown and weld history information results in a requirement for additional actions to obtain an acceptable surface for examination or the investigation of alternative examination techniques to obtain an adequate amount of examination coverage, greater than 90%, a A condition report shall be generated within the corrective action program. The corrective measures may include:
o Development of an alternative qualified examination technique to achieve the required coverage.
o Modification of the surface condition to improve the coverage to the required level. This could include grinding, sanding, or machining of the existing surface. Surface improvements should be performed in advance, but should be prepared to perform surface improvements as needed during the outage.
o Application of a weld overlay to achieve an appropriate surface condition.
o Weld Mitigation o Development and submittal of a request for relief to the Nuclear Regulatory Commission.
During the surface conditioning process, an individual qualified to perform the UT examination shall provide final acceptance of the surface condition prior to examination.
References:
- 1. Nuclear Regulatory Commission 10CFR Part 50a, Final rule
- 3. Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds. EPRI, Palo Alto, CA: 2009.
1018181.
- 4. Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139, Revision 1). EPRI, Palo Alto, CA:
2008. 1015009.
Page 24 of 59 APPENDIX A DM Weld Walkdown Instructions
- 1. Take pictures of general area for obstructions. If obstructions such as hangers or whip restraints, adjacent valves or components are present, determine the maximum vertical clearance and the surface distance available to mount scanners.
- 2. Take pictures of DM weld with a scale or other measuring device.
- 4. If feasible, Take UT thickness at zero degrees. Additional weld contours and thickness may be taken at 90, 180, or 270 degrees if configuration is not uniform around the circumference. Other alternate methods may be used if for complex configurations.
- 6. If weld toes are not readily visible, acid etching or eddy current surface probe may be used to identify Alloy 82/182-to-SS interface.
- 7. Take required measurements using attached example as a guideline.
- 8. Take circumference measurements on parallel surfaces for each diameter (nozzle, pipe, safe-end, elbow).
- 9. Provide comments (for example, weld crown conditions). The weld crown and scan surface must allow unimpeded access across the weld and butter. Waviness, tapers, exposed weld toes that cause the search unit to lift off the surface must be addressed. The general surface condition should either be machined or ground smooth to a 250-RMS (root mean square) finish, approximately. Long-range waviness can be measured by placing the required search units on the examination surface to assure that there are no gaps between the surface and the bottom of the probe greater than approximately 1/32 over the entire scanning surface.
- 10. Document any areas that show evidence of weld repairs.
Page 25 of 59 Palo Verde Unit 2 Surge line to PZR, 12 NPS (Configuration 1)
Field Measured Profile
Page 26 of 59 Description Dim Description Dim D1 60 degree scan path 3.0 A1 Nozzle Taper (degree) 12 D2 Butter Width
.350 A2 N/A D3 Weld Width 1.15 OD Outside Dia at weld C L 12.75 D4 Safe-end Width 2.1 D5 Pipe Weld Width
1.4 Comments
DM weld OD machined Nozzle clad.220 thick (design) One weld of this configuration D6 N/A D7 N/A T1 Pipe Thickness N/A T2 Safe-end Thickness 1.45 T3 Nozzle Thickness 1.40 Palo Verde Unit 2 PZR to Hot Leg (Configuration 2)
Page 27 of 59 Field Measured Profile Description Dim Description Dim D1 60 degree exit point 3.0 A1 Nozzle Taper (degree) 6.5 D2 Butter Width
.300 A2 N/A D3 Weld Width 1.4 OD Outside Dia at weld C L 12.75 D4 Safe-end Width 2
D5 Pipe Weld Width
1.4 Comments
DM weld OD machined Nozzle clad.220 thick (design) One weld of this configuration D6 N/A D7 N/A T1 Pipe Thickness 1.25 T2 Safe-end Thickness 1.45 T3 Nozzle Thickness 1.45
Page 28 of 59 Palo Verde Unit 2 SI Hot Leg Suction, 16 NPS (Configuration 3)
Field Measured Profile
Page 29 of 59
- Description Dim Description Dim D1 Taper Start to Butter 1.5 A1 Nozzle Taper (degree) 30 D2 Butter Width
.350 A2 N/A D3 Weld Width 1.6 OD Outside Dia at weld C L 16 D4 Safe-end Width 2.5 D5 Pipe Weld Width
1.3 Comments
DM weld OD machined Nozzle clad.220 thick (design) Two welds of this configuration D6 N/A D7 N/A T1 Pipe Thickness 1.45 T2 Safe-end Thickness 1.75 T3 Nozzle Thickness 1.65 Palo Verde Unit 2 SI to Cold Leg, 14 NPS (Configuration 4)
Page 30 of 59 Field Measured Profile Description Dim Description Dim D1 Taper to Butter 4.2 A1 Nozzle Taper (degree) 12 D2 Butter Width
.300 A2 N/A D3 Weld Width 1.5 OD Outside Dia at weld C L 14 D4 Safe-end Width 2.1 D5 Pipe Weld Width
1.5 Comments
DM weld OD machined Nozzle clad.220 thick (design) Four welds of this configuration D6 N/A D7 N/A T1 Pipe Thickness 1.55 T2 Safe-end Thickness 1.8 T3 Nozzle Thickness 1.75
Page 31 of 59 Palo Verde Unit 2 PZR Spray at Cold Leg, 3 NPS (Configuration 5)
Field Measured Profile
Page 32 of 59 Description Dim Description Dim D1 Taper to Butter 3.4 A1 Nozzle Taper (degree) 13.33 D2 Butter Width
.300 A2 N/A D3 Weld Width 1.0 OD Outside Dia at weld C L 4.8 D4 Safe-end Width 1.5 D5 Pipe Weld Width
1.0 Comments
DM weld OD hand ground Nozzle clad.220 thick (design) Two welds of this configuration D6 N/A D7 N/A T1 Safe-end Thickness
.600 T2 Safe-end Thickness
.850 T3 Nozzle Thickness 1.15 Palo Verde Unit 2 PZR Spray, 4 NPS (Configuration 6)
Page 33 of 59 Field Measured Profile Description Dim Description Dim D1 Taper to Butter 2.8 A1 Nozzle Taper (degree) 20 D2 Butter Width
.300 A2 N/A D3 Weld Width
.90 OD Outside Dia at weld C L 5.3 D4 Safe-end Width 2.2 D5 Pipe Weld Width
.80 Comments:
DM weld OD machined Nozzle clad.220 thick (design) One weld of this configuration D6 N/A D7 N/A T1 Pipe Thickness
.450 T2 Safe-end Thickness
.650 T3 Nozzle Thickness 1.10
Page 34 of 59 Palo Verde Unit 2 PZR Safeties, 6 NPS (Configuration 7)
Field Measured Profile
Page 35 of 59 Description Dim Description Dim D1 Taper to Butter @ 0 3.7 A1 Nozzle Taper (degree) 0 D1 Taper to Butter @ 90/270 3.0 A2 N/A D1 Taper to Butter @ 180 1.2 OD Outside Dia at weld C L 8.0 D2 Butter Width
.300 D3 Weld Width
1.2 Comments
DM weld OD machined and hand ground Nozzle clad.220 thick (design) Four welds of this configuration D4 Safe-end Width 3.0 N/A T1 N/A T2 Safe-end Thickness 1.45 T3 Nozzle Thickness 1.40 Palo Verde Unit 2 Drain Lines, 2 NPS (Configuration 8)
Page 36 of 59 Field Measured Profile Description Dim Description Dim D1 Taper to Butter 2.4 A1 Nozzle Taper (degree) 13.50 D2 Butter Width
.300 A2 N/A D3 Weld Width
.90 OD Outside Dia at weld C L 3.7 D4 Safe-end Width 1.5 D5 Pipe Weld Width
.60 Comments:
DM weld OD machined and hand ground Nozzle clad.220 thick (design)
Four welds of this configuration D6 N/A D7 N/A T1 Safe-end Thickness
.650 T2 Safe-end Thickness
.900 T3 Nozzle Thickness 1.20
Page 37 of 59 Palo Verde Unit 2 Charging to Cold Leg, 2 NPS (Configuration 9)
Field Measured Profile
Page 38 of 59 Description Dim Description Dim D1 Taper to Butter 3.1 A1 Nozzle Taper (degree) 20 D2 Butter Width
.400 A2 N/A D3 Weld Width 1.0 OD Outside Dia at weld C L 5.0 D4 Safe-end Width 3.0 D5 Pipe Weld Width
.60 Comments:
DM weld OD machined and hand ground Nozzle clad.220 thick (design) One weld of this configuration D6 N/A D7 N/A T1 Safe-end Thickness
.500 T2 Safe-end Thickness 1.10 T3 Nozzle Thickness 1.50
Page 39 of 59 Appendix B Mitigated Steam Generator Instrument, Pressurizer Instrument, and RCS Hot Leg Instrument Nozzles with Alloy 600/82/182 App. B has been developed the aid the Alloy 600 program owner in identifying configurations of the Steam Generator, Pressurizer and RCS Hot Leg modifications that have replaced Alloy 600 nozzles with Alloy 690 materials. These tables clarify where Alloy 82 pressure retaining welds remain as not all modifications used Alloy 52 or Alloy 52M filler materials. Note that during the modifications, many ID J-groove Alloy 82/182 welds remain in place. Some of the ID J-groove welds contain Alloy 600 nozzle that perform a Class 1 to Class 2 boundary change. With the half nozzle replacements, the original Alloy 600 nozzle comprising of the Class break no longer performs a pressure retaining function that would produce leakage detectable by a N-722-1 exam. The welds listed in the table include welds that are still performing pressure retaining functions that could result in a visual detection of RCS leakage.
Applicability of N-722-1 remains for any of the Alloy 82/182/600 materials performing a pressure retaining function that would result in a detectable pressure boundary leakage.
Also note that the program lists RTD nozzles as half nozzle replacements. Some of the RTD half nozzle replacements have been coined as 3/4-Nozzle replacements in some of the plant documents as the RTD nozzle replacements required a tight fit to carry the moment and prevent vibrations as the thermowell interacts with RCS flow. For consistency of the Alloy 600 program, configuration of the RTD nozzles, Half Nozzle has been used in the tables to stay consistent with the Alloy 600 program as this design detail is beyond the scope of the program.
Note: ERNiCr-3 = Alloy 82, ENiCrFe-3 = Alloy 182, ERNiCrFe-7 =Alloy 52, ERNiCrFe-7a = Alloy 52M, SB-166/167, UNS 06600 = Alloy 600, SB-166/167 UNS 06690 = Alloy 690
Page 40 of 59 Appendix B, Table 1.1 Unit 1 SG CL Instrument Alloy 690 Nozzles: Item No. B15.135 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal ID J groove ller metal Cong SDOC Other Pressure Retaining Alloy 82/182/600 Material 1PRCDV270 1PRCDL042 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCCV272 1PRCCL043 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCBV274 1PRCBL044 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCAV276 1PRCAL045 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCDV278 1PRCDL085 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCCV280 1PRCCL086 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCBV282 1PRCBL087 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer 1PRCAV284 1PRCAL088 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer Full Nozzle 01B$
ERNiCr-3 buer
- Unit 1 SGR Outage 1R12
Page 41 of 59 Appendix B, Table 1.2 Unit 1 Pressurizer Heater Alloy 690 Nozzles: Item No. B15.140 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material WO Heater Welded to Sleeve
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle Ref. DIWO No, Heater to Alloy 690 sleeve welded with ERNiCrFe-7 or 7A WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 3089399
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
Page 42 of 59
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 3082768
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&($
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
Page 43 of 59
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
05&(%
2513813 2614240 Oct.
2005 ERNiCrFe-7A ERNiCrFe-7A Half Nozzle WO 2928459
Page 44 of 59 Appendix B, Table 1.3 Unit 1 Pressurizer Alloy 690 Instrument Nozzles: Item No. B15.180 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal ID J groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material 1PRCCV204 DCP1XM-RC-173 CM 888525, WO 539042 1992 N/A N/A ERNiCr-3 Full Nozzle N001-0604-00192 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1PRCDV205 DCP1XM-RC-173 CM 888525, WO 539042 1992 N/A N/A ERNiCr-3 Full Nozzle N001-0604-00189 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1PRCAV206 DCP1XM-RC-173 CM 888525, WO 00596577 1992 N/A N/A ERNiCr-3 Full Nozzle N001-0604-00183 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1PRCBV207 DCP1XM-RC-173 CM 888525, WO 539042 1992 N/A N/A ERNiCr-3 Full Nozzle N001-0604-00191 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1PRCAV208 DCP1XM-RC-173 WO 539042 1992 ERNiCr-3 ERNiCr-3 Autogenous weld***
Pad, sleeve, Full Nozzle N001-0604-00187 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1PRCBV209 DCP1XM-RC-173 WO 539042 1992 ERNiCr-3 ERNiCr-3 Autogenous weld***
Pad, sleeve, Full Nozzle N001-0604-00186 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1JRCNTE0101 (1JRCETW0101)
DCP1XM-RC-173 WO 539042 1992 ERNiCr-3*
ERNiCr-3*
Autogenous weld***
Pad, sleeve, Full Nozzle*
N001-0604-00184 N001-0604-00148 ERNiCr-3 Bu Weld at Safe-end 1JRCNTE0101 (1JRCETW0101)
AWA-APS-2023-0052 DEC-00946 WO 4764314 T3 2023 ERNiCrFe-7**
ERNiCrFe-7**
N/A Pad, Full Nozzle**
N001-0604-00946 2023-00461 N/A
- Removed in 1R24.
- Pressure Boundary Fully Mitigated in 1R24
Page 45 of 59 Appendix B, Table 1.4 Unit 1 Hot Leg Piping Alloy 690 Instrument Connections: Item No. B15.200 EQ ID Mod DI WO Year OD J Groove ller metal ID J groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material 1PRCEV213 1PRCEL049 DMWO 2319254 DI 002346486 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCDV271 1PRCDL052 DMWO 2319254 DI 002346486 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCCV273 1PRCCL053 DMWO 2319254 DI 002346489 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCBV275 1PRCBL054 DMWO 2319254 DI 002346486 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCAV277 1PRCAL055 DMWO 2376926 DI 002455746 1999 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCDV279 1PRCDL064 DMWO 2319254 DI 00509730 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCCV281 1PRCCL065 DMWO 2319254 DI 00509730 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCBV283 1PRCBL067 DMWO 2319254 DI 00509730 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1PRCAV085 1PRCAL066 DMWO 2319254 DI 00509730 1999 ERNiCrFe-7 N/A Half Nozzle N001-0607-00329 N/A 1JRCNTE0111X**IXMITR 1JRCETW0111X**PIPEXX DMWO 2376926 DI 002455746 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCATW0112HA**PIPEXX DMWO 2376926 DI 002455746 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCBTE0112HB 1JRCBTW0112HB**PIPEXX DMWO 2376926 DI 2448544 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCCTW0112HC**PIPEXX DMWO 2376926 DI 2448544 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCDTW0112HD**PIPEXX DMWO 2376926 DI 2448544 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A
Page 46 of 59 1JRCETW0111HA**PIPEXX DMWO 2319254 DI 002346489 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0111HB**PIPEXX DMWO 2319254 DI 002346486 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0111HC**PIPEXX DMWO 2319254 DI 002346489 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0111HD**PIPEXX DMWO 2319254 DI 002346486 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0121HA**PIPEXX DMWO 2319254 DI 002346491 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0121HB**PIPEXX DMWO 2319254 DI 002346490 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A JRCETW0121HC**PIPEXX DMWO 2319254 DI 002346491 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0121HD**PIPEXX DMWO 2319254 DI 002346490 2001 ERNiCrFe-7 N/A Plug N001-0607-00392 N/A 1JRCETW0121X**PIPEXX DMWO 2376926 DI 002455748 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCATW0122HA**PIPEXX DMWO 2376926 DI 002455748 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCBTW0122HB**PIPEXX DMWO 2376926 DI 002455748 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCCTW0122HC**PIPEXX DMWO 2376926 DI 002455748 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A 1JRCDTW0122HD**PIPEXX DMWO 2376926 DI 002455748 2002 ERNiCrFe-7 N/A Half Nozzle N001-0607-00398 N/A
Page 47 of 59 Appendix B, Table 2.1 Unit 2 Pressurizer Heater Alloy 690 Nozzles: Item No. B15.140 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material WO Heater Welded to Sleeve
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle Ref. DIWO No, Heater to Alloy 690 sleeve welded with ERNiCrFe-7 WO 3564674
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&($
3OXJJHG 2327179 2327197 Oct. 2000 ERNiCrFe-7 ERNiCrFe-7 Plugged Ref. DFWO 2327179 02-N001-0604-000671 DIWO 2327197
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3333659
Page 48 of 59
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2788386
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 5614243
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&($
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
Page 49 of 59
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4812306
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2788386
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3333659
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3564674
05&(%
2513813 2614243 Nov. 2003 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614243
05&(%
3OXJJHG
2327179 2330262 Oct. 2000 ERNiCrFe-7 ERNiCrFe-7 Plugged Ref. DFWO 2327179 02-N001-0604-000671 DIWO 2330262
Page 50 of 59 Appendix B, Table 2.2 Unit 2 Pressurizer Alloy 690 Instrument Nozzles: Item No.B15.180 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal ID J groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material 2PRCCV204 2PM-RC-179 CM 888525, WO 00596577 1993 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 2PRCDV205 2PM-RC-179 CM 888525, WO 00596577 1993 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 2PRCAV206 2PM-RC-179 CM 888525, WO 00596577 1993 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 2PRCBV207 2PM-RC-179 CM 888525, WO 00596577 1993 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 2PRCAV208 2PM-RC-182 WO 00694487 1995 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld Pad, sleeve, Full Nozzle N001-0604-00009 N001-0604-00246 ERNiCr-3 Bu Weld at Safe-end 2PRCBV209 2PM-RC-182 WO 00694487 1995 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld Pad, sleeve, Full Nozzle N001-0604-00009 N001-0604-00246 ERNiCr-3 Bu Weld at Safe-end 2JRCNTE0101 (2JRCETW0101) 2PM-RC-182 WO 00694487 1995 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld Pad, sleeve, Full Nozzle N001-0604-00009 N001-0604-00245 ERNiCr-3 Bu Weld at Safe-end
Page 51 of 59 Appendix B, Table 2.3 Unit 2 Hot Leg Piping Alloy 690 Instrument Connections: Item No. B15.200 EQ ID Mod DI WO Year OD J Groove ller metal ID J groove ller metal Cong (Full Nozz. w/
Corrosion Sleeve)
DWG Other Pressure Retaining Alloy 82/182/600 Material 2PRCEV213 2PRCEL049 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCDV271 2PRCDL052 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCCV273 2PRCCL053 DMWO 219026 DI 233220 2000 ERNiCrFe-7 Autogenous weld Half Nozzle N001-0607-00329 N/A 2PRCBV275 2PRCBL054 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCAV277 2PRCAL055 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCDV279 2PRCDL064 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCCV281 2PRCCL065 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCBV283 2PRCBL067 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2PRCAV085 2PRCAL066 2PM-RC-167 DI 00509730 1991 ERNiCr-3 Autogenous weld Full Nozzle N001-0607-00329 N/A 2JRCNTE0111X**IXMITR 2JRCETW0111X**PIPEXX DMWO 2376926 DI 2448544 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCATW0112HA**PIPEXX DMWO 2376926 DI 2448544 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCBTE0112HB 2JRCBTW0112HB**PIPEXX DMWO 2376926 DI 2448544 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCCTW0112HC**PIPEXX DMWO 2376926 DI 2448544 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A
Page 52 of 59 2JRCDTW0112HD**PIPEXX DMWO 2376926 DI 2448544 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCETW0111HA**PIPEXX DMWO 219026 DI 233220 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0111HB**PIPEXX DMWO 219026 DI 233221 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0111HC**PIPEXX DMWO 219026 DI 233220 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0111HD**PIPEXX DMWO 219026 DI 233221 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0121HA**PIPEXX DMWO 219026 DI 233222 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0121HB**PIPEXX DMWO 219026 DI 233223 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0121HC**PIPEXX DMWO 219026 DI 233222 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0121HD**PIPEXX DMWO 219026 DI 233223 2000 ERNiCrFe-7 Original Alloy 82/182 Plug N001-0607-00392 N/A 2JRCETW0121X**PIPEXX DMWO 2376926 DI 2448549 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCATW0122HA**PIPEXX DMWO 2376926 DI 2448549 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCBTW0122HB**PIPEXX DMWO 2376926 DI 2448549 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCCTW0122HC**PIPEXX DMWO 2376926 DI 2448549 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A 2JRCDTW0122HD**PIPEXX DMWO 2376926 DI 2448549 2005 ERNiCrFe-7 Original Alloy 82/182 Half Nozzle N001-0607-00398 N/A
Page 53 of 59 Appendix B, Table 3.1 Unit 3 SG CL Instrument Alloy 690 Nozzles: Item No. B15.135 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal ID J groove ller metal Cong SDOC Other Pressure Retaining Alloy 82/182/600 Material 3PRCDV270 3PRCDL042 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCCV272 3PRCCL043 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCBV274 3PRCBL044 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCAV276 3PRCAL045 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCDV278 3PRCDL085 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCCV280 3PRCCL086 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCBV282 3PRCBL087 N/A, Ref SDOC N/A, Ref SDOC 2007*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer 3PRCAV284 3PRCAL088 N/A, Ref SDOC N/A, Ref SDOC 2005*
N/A N/A ERNiCrFe-7 w/ERNiCr-3 buer ID Mounted Full Nozzle 01B$
ERNiCr-3 buer
- Unit 3 SGR Outage 3R13
Page 54 of 59 Appendix B, Table 3.2 Unit 3 Pressurizer Heater Alloy 690 Nozzles: Item No. B15.140 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material WO Heater Welded to Sleeve
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle Ref. DIWO No, Heater to Alloy 690 sleeve welded with ERNiCrFe-7 or 7A WO 3404031
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3404031
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3404031
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3200038
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
Page 55 of 59
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3404031
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&($
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3404031
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 3228723
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 5423854
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
Page 56 of 59
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 2797822
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle WO 4296964
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
05&(%
2513813 2614238 Sep. 2004 ERNiCrFe-7 ERNiCrFe-7 Half Nozzle DIWO 2614238
Page 57 of 59 Appendix B, Table 3.3 Unit 3 Pressurizer Alloy 690 Instrument Nozzles: Item No. B15.180 EQ ID Mod DI WO Year Pad weld ller metal OD J Groove ller metal ID J groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material 3PRCCV204 3PM-RC-179 WO 00645696 1994 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 3PRCDV205 3PM-RC-179 WO 00645696 1994 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 3PRCAV206 3PM-RC-179 WO 00645696 1994 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 3PRCBV207 3PM-RC-179 WO 00645696 1994 N/A none ERNiCrFe-7 welded to Alloy 82/182 Full Nozzle N001-0604-00223 ERNiCr-3 Bu Weld at Safe-end 3PRCAV208 3PM-RC-182 WO 00645697 1994 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld sleeve Pad, sleeve, Full Nozzle N001-0604-00246 ERNiCr-3 Bu Weld at Safe-end 3PRCBV209 3PM-RC-182 WO 00645697 1994 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld sleeve Pad, sleeve, Full Nozzle N001-0604-00246 ERNiCr-3 Bu Weld at Safe-end 3JRCNTE0101 3PM-RC-182 WO 00645697 1994 ERNiCrFe-7 ERNiCrFe-7 Autogenous weld sleeve Pad, sleeve, Full Nozzle N001-0604-00245 ERNiCr-3 Bu Weld at Safe-end
Page 58 of 59 Appendix B, Table 3.4 Unit 3 Hot Leg Piping Alloy 690 Instrument Connections: Item No. B15.200 EQ ID Mod DI WO Year OD J Groove ller metal ID J groove ller metal Cong DWG Other Pressure Retaining Alloy 82/182/600 Material 3PRCEV213 3PRCEL049 DMWO 00911855 DI 2390208 2001 ERNiCrFe-7 N/A Half Nozzle N001-607-00278, N001-607-00398 N/A 3PRCDV271 3PRCDL052 DMWO 00911855 CM 226397, DI 00913082 2000 ERNiCrFe-7 N/A Half Nozzle N001-607-00203 N/A 3PRCCV273 3PRCEL032 DMWO 2390196 DI 2390209 2001 ERNiCrFe-7 N/A Half Nozzle N001-607-00392, N001-607-00278 N/A 3PRCBV275 3PRCBL054 DMWO 00911855 DI 226396, DI 00913081 2000 ERNiCrFe-7 N/A Half Nozzle N001-607-00278, N001-607-00203 N/A 3PRCAV277 3PRCAL155 DMWO 2390196 DI 2390209 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00367 N/A 3PRCDV279 3PRCDL064 DMWO 00911855 DI 226402, DI 00913087 2000 ERNiCrFe-7 N/A Half Nozzle N001-607-00278, N001-607-00201 N/A 3PRCCV281 3PRCCL065 DMWO 2390196 DI 2390215 2001 ERNiCrFe-7 N/A Half Nozzle N001-607-00201, N001-607-00278, N001-607-00392 N/A 3PRCBV283 3PRCBL067 DMWO 00911855 DI 226401, DI 00913086 2000 ERNiCrFe-7 N/A Half Nozzle N001-607-00278, N001-607-00201, 13-P-ZCG-103 N/A 3PRCAV285 3PRCEL063 DMWO 2390196 DI 2390215 2001 ERNiCrFe-7 N/A Half Nozzle N001-0607-00367 N/A 3JRCNTE0111X**IXMITR 3JRCETW0111X**PIPEXX DMWO 2376926 DI 2455749 2003 ERNiCrFe-7 N/A RTD N001-607-00398 N/A 3JRCATW0112HA**PIPEXX DMWO 2376926 DI 2455749 2003 ERNiCrFe-7 N/A RTD N001-607-00398 N/A 3JRCBTE0112HB 3JRCBTW0112HB**PIPEXX DMWO 2376926 DI 2455749 2003 ERNiCrFe-7 N/A RTD N001-607-00398 N/A 3JRCCTW0112HC**PIPEXX DMWO 2376926 DI 2455749 2003 ERNiCrFe-7 N/A RTD N001-607-00398 N/A
Page 59 of 59 3JRCDTW0112HD**PIPEXX DMWO 2376926 DI 2455749 2003 ERNiCrFe-7 N/A RTD N001-607-00398 N/A 3JRCETW0111HA**PIPEXX DMWO 2390196 DI 2390209 2001 ERNiCrFe-7 N/A Plug N001-607-00203, N001-607-00278, N/A 3JRCETW0111HB**PIPEXX DMWO 2390196 DI 2390208 2001 ERNiCrFe-7 N/A Plug N001-607-00203, N001-607-00278, N001-607-00392 N/A 3JRCETW0111HC**PIPEXX DMWO 2390196 DI 2390209 2001 ERNiCrFe-7 N/A Plug N001-607-00203, N001-607-00278, N001-607-00392 N/A 3JRCETW0111HD**PIPEXX DMWO 2390196 DI 2390208 2001 ERNiCrFe-7 N/A Plug N001-607-00203, N001-607-00278, N001-607-00392 N/A 3JRCETW0121HA**PIPEXX DMWO 2390196 DI 2390215 2001 ERNiCrFe-7 N/A Plug N001-607-00201, N001-607-00278, N001-607-00392 N/A 3JRCETW0121HB**PIPEXX DMWO 2390196 DI 2390212 2001 ERNiCrFe-7 N/A Plug N001-607-00201, N001-607-00278, N001-607-00392 N/A 3JRCETW0121HC**PIPEXX DMWO 2390196 DI 2390215 2001 ERNiCrFe-7 N/A Plug N001-607-00201, N001-607-00278, N001-607-00392 N/A 3JRCETW0121HD**PIPEXX DMWO 2390196 DI 2390212 2001 ERNiCrFe-7 N/A Plug N001-607-00201, N001-607-00278, N001-607-00392 N/A 3JRCETW0121X**PIPEXX DMWO 2376926 DI 2455750 2003 ERNiCrFe-7 N/A Half Nozzle N001-607-00398 N/A 3JRCATW0122HA**PIPEXX DMWO 2376926 DI 2455750 2003 ERNiCrFe-7 N/A Half Nozzle N001-607-00398 N/A 3JRCBTW0122HB**PIPEXX DMWO 2376926 DI 2455750 2003 ERNiCrFe-7 N/A Half Nozzle N001-607-00398 N/A 3JRCCTW0122HC**PIPEXX DMWO 2376926 DI 2455750 2003 ERNiCrFe-7 N/A Half Nozzle N001-607-00398 N/A 3JRCDTW0122HD**PIPEXX DMWO 2376926 DI 2455750 2003 ERNiCrFe-7 N/A Half Nozzle N001-607-00398 N/A