ML22201A503

IP 71007 Reactor Vessel Head Replacement Inspection

ML22201A503
Person / Time
Issue date:	02/04/2025
From:	Shawn Campbell NRC/NRR/DRO/IRIB
To:
stephen.campbell@nrc.gov
Shared Package
ML22209A184	List: ML22201A503 ML22201A513
References
DC 22-017, CN 25-001
Download: ML22201A503 (1)

Text

Issue Date: 02/04/25 1

71007 NRC INSPECTION MANUAL IRIB INSPECTION PROCEDURE 71007 REACTOR VESSEL HEAD REPLACEMENT INSPECTION Effective Date: February 4, 2025 PROGRAM APPLICABILITY: IMC 2515 C 71007-01 INSPECTION OBJECTIVES 01.01 To verify that engineering evaluations and design changes associated with reactor vessel (RV) head replacement are completed in conformance with requirements in the facility license, the applicable codes and standards, licensing commitments, and the regulations.

01.02 To verify that the manufacture and fabrication of the RV head are completed in conformance with applicable codes and standards and design requirements, and that all dimensions and related tolerances for the RV head including openings in it are in accordance with design drawings.

01.03 To verify that RV head removal and replacement activities maintain adequate nuclear and radiological safety.

01.04 To verify that the RV head post-installation test program is technically adequate, in conformance with requirements, and satisfactorily implemented.

71007-02 INSPECTION REQUIREMENTS 02.01 Inspection Plan Develop a site-specific inspection plan to select and review the safety-related activities associated with the major phases of the RV head replacement project (RVHRP).

a. A typical RVHRP involves four major phases: design and planning, RV head fabrication, RV head removal and replacement, and post-installation verification and testing. In most cases, the RVHRP includes the provision of a temporary containment access opening.

b. Management for the region, with oversight of the licensee facility purchasing or obtaining a new RV head, will make the decision to proceed with any inspections at a vendor facility after consulting with the Office of Nuclear Reactor Regulation (NRR) management and the management for the other regions.

c. The inspector(s) shall contact the NRR project manager to obtain any specific technical support from NRR.

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d. During inspection preparation, review the processes for RVHRP and plans for identifying, tracking, and resolving problems related to RVHRP to ascertain that they are consistent with plant processes.

e. This procedure lists certain baseline inspection procedures (IPs) mainly in Section 03.02 and Appendix A, Applicable Inspection Procedures, of this procedure to be used to perform parts of the inspection.

02.02 Design and Planning Inspections Conduct RV head design and planning inspections in accordance with the inspection plan by performing selective inspections, consistent with the safety significance and inspection resources, of the following areas:

a. Conduct RV head replacement engineering and technical support inspections in accordance with the inspection plan by performing selective inspections that will:

1. Verify that selected design changes and modifications to systems, structures, and components (SSCs) described in the Updated Final Safety Analysis Report (UFSAR) for transporting the new and old RV heads in and out of the plant respectively are reviewed in accordance with Title 10 of the Code of Federal Regulations (10 CFR)

Section 50.59,Changes, tests and experiments, (see the table in p. 52 of NUREG-1379, Rev. 3).

2. Review key design aspects and modifications for the replacement RV head and other modifications associated with RV head replacement. Where applicable, include design reviews for the provision of a temporary containment opening. In addition, perform the following additional design reviews.

(a) Review the required documents, supplemental examinations records, analyses, and appropriate edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code documentation reconciliation to ensure that the original ASME Code N-stamp documentation remains valid, and that the replacement head will comply with the appropriate NRC rules and industry requirements.

(b) Verify there is a contract requirement to maintain part identification and traceability during processing of the replacement head.

3. Determine if the licensee has confirmed that the replacement RPV head conforms to design drawings and that there are no fabrication deviations from design.

b. Review the applicable engineering design, modification, and analyses associated with RV head lifting and rigging including: (1) crane, and rigging equipment, and full load testing (2) RV head component drop analysis, (3) safe load paths, and (4) load lay-down areas.

c. Review radiation protection program controls, planning, and preparation in the following areas:

1. as-low-as-reasonably-achievable (ALARA) planning

2. dose estimates and dose tracking

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3. exposure controls including temporary shielding

4. contamination controls

5. radioactive material management

6. radiological work plans and controls

7. airborne radioactivity effluent controls

8. radioactive waste and material handling, storage, and transportation

d. Review RVHRP activities in the following areas:

1. Security considerations associated with vital and protected area barriers that may be affected during replacement activities.

2. Where applicable at multi-unit sites, the controls and plans to minimize any adverse impact on the operating unit(s) and common systems.

02.03 RV Head Fabrication Inspections at Vendor Facility The requirements listed in Section 02.03 may be completed by any of the following three methods either individually or in combination:. (1) The Authorized Nuclear Inspector (ANI) or the NRC can perform the requirements at the vendor facility. (2) An NRC inspector can confirm that the ANI completed the requirements by a records review at either the vendor facility or at the plant site. (3) For those requirements not completed by the ANI, an NRC inspector can confirm that the requirements were met or completed by reviewing licensee surveillance reports or appropriate vendor records at the plant site.

For any type of RV head fabricated by a particular vendor, only the fabrication of the prototype should be reviewed at the vendor facility, except if regional management decides otherwise, with all subsequent RV heads of the same type and model considered to be validated by that initial review. See Appendix D, Head Fabrication &

Preservice Record Review Checklist, for detailed inspection guidance to assist in reviews conducted for this section. Appendix C, Additional RV Head Fabrication Inspection Requirements, contains additional lower priority inspection requirements that the NRC inspector may choose to invoke if further assurance is necessary as to the quality of fabrication of a particular RV head.

a. Verify that material heat treatment which is used to enhance the mechanical properties of RV head material carbon, low alloy, and high alloy chromium (Series 4XX) steels is conducted in accordance with the ASME Code and approved vendor procedures or instructions and are consistent with the applicable ASME Code,Section III, Rules for Construction of Nuclear Facility Components, requirements.

b. Verify that adequate heat treatment procedures are available to assure that applicable code and/or contract requirements are met for the following:

1. Furnace atmosphere.

2. Furnace temperature distribution, calibration of measuring and recording devices.

3. Thermocouple installation on parts to be heat treated (Numbers, locations, method of attachment).

4. Heating and cooling rates.

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5. Quenching methods including quenching medium, maximum transfer time.

6. Record and documentation requirements

c. Verify that the manufacturing or process control plan includes provisions for monitoring the nondestructive examination (NDE) to ascertain that the NDE, including specific NDE method was used, is performed in accordance with applicable code, material specification, and contract requirements.

d. Verify that weld overlay welding operations to establish a layer of stainless-steel cladding on inside of RV head are done per specifications and design drawings.

e. The inspectors will select a sample of dome to flange welds and control rod drive mechanism (CRDM) flange-to-nozzles welds, and review the following:

1. certified Mill Test Reports (CMTRs) of the dome, flange, weld material rods, and CRDM nozzles

2. CMTRs for the welding material for the RPV head cladding

3. cladding weld records, weld rod material control requisitions, traceability of weld material rods, weld procedure qualification, welder qualifications, and nonconformance reports

4. CRDM nozzle cladding welding inspection records, weld rod material control requisitions, traceability of weld material rods, weld procedure qualification, welder qualifications, and non-conformance reports

5. CRDM-to-nozzle welds records-welding and weld inspections, weld rod material control requisitions, traceability of weld material rods, weld procedure qualification, welder qualifications, and non-conformance reports

6. NDE procedures, NDE records of the welds, NDE personnel qualifications, certification of the NDE solvents that they did not contain deleterious substances such as mercury, lead, and corrosive chemicals

f.

Verify that repair procedures have been established and that these procedures are consistent with applicable ASME Code, material specification, and contract requirements. Specifically, verify that:

1. repair welding is conducted in accordance with procedures qualified to Section IX of the ASME Code

2. all welders have been qualified in accordance with Section IX of the ASME Code

3. records of the repair are maintained in accordance with applicable code and contract requirements

g. Verify that requirements have been established for the preparation of certified material test reports and that the records of all required examinations and tests are traceable by travelers to procedures and revisions to which they were performed.

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h. Verify that the Design Specification is reconciled or updated, and a Design Report is prepared for the reconciliation of the replacement head.

i.

Verify that machining is carried out under a controlled system of operation (travelers, check lists) consistent with the manufacturers overall Quality Assurance (QA) program.

j.

Verify that drawing/document control system is in use during the manufacturing process and is consistent with the manufacturers QA program. Verify that the specified drawing and document revisions are available on the shop floor and are being used for fabrication, machining, and inspection.

k. Examine selected manufacturing and inspection records of finished machined RV head and verify compliance with applicable documentation requirements.

02.04 RV Head Removal and Replacement Inspections Conduct RV head removal and replacement inspections in accordance with the inspection plan by performing selective inspections, consistent with the safety significance and inspection resources, of the following areas:

a. Review activities associated with lifting and rigging: preparations and procedures for rigging and heavy lifting including any required crane and rigging inspections, testing, equipment modifications, lay-down area preparations, and training of crane and rigging personnel. Verify that the capability of the lifting equipment, including fixtures and rigging, to handle the load has been established by analysis and testing.

b. Inspect major structural modifications, if any, that are performed to facilitate RV head replacement.

c. Inspect the activities associated with containment access and, where applicable, activities associated with creation and restoration of temporary containment opening and containment leakage testing.

d. Inspect the following activities throughout the process as appropriate:

1. Establishment of operating conditions including defueling, reactor coolant system (RCS) draindown, and system isolation and safety tagging/blocking.

2. Implementation of radiation protection controls.

3. Inspect controls for excluding foreign materials in the reactor vessel.

4. Verify that reinstalled (reused) components are suitable for use.

5. Installation, use, and removal of temporary services directly related to the activities identified in this procedure.

e. Review radiological safety plans for temporary storage or disposal of the old RV head.

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71007 02.05 Post-installation Verification and Testing Inspections Conduct RV head post-installation verification and testing inspections in accordance with the inspection plan. Perform selective inspections, consistent with the safety significance and inspection resources, of the following areas:

a. Containment testing, as applicable.

b. The licensees post-installation inspections and verifications program and its implementation.

c. The conduct of RCS leakage testing and review the test results.

d. The procedures for equipment performance testing required to confirm the design and to establish baseline measurements and the conduct of testing.

e. Preservice inspection of new welds. See Appendix D for inspection guidance.

71007-03 INSPECTION GUIDANCE General Guidance Comprehensive NRC inspection of RV replacement activities involves coordination of inspections to review engineering, safety assessment, welding, NDE, quality assurance, radiation protection, security, and testing.

The RV head replacement should be accomplished under 10 CFR 50.59. Licensees should begin interacting with the regions and NRR technical branches possibly two or more years before the scheduled replacement and prior to contracting a vendor for RV head fabrication.

Any engineering reviews by NRR to support inspections should be coordinated through the NRR project manager.

All inspections of RV head replacement activities should be performed per this procedure and integrated into the regional site-specific inspection plan.

The site-specific inspection plan should include the applicable inspection requirements outlined in Section 02. The emphasis on inspection activities should be based on the overall scope, the safety significance of the activities, the licensees historical performance in that area, and industry experience. Additional emphasis may be considered for those licensee activities that include new or different management controls or involve are being managed/controlled in a different manner or implemented with new techniques.

Additional guidance for specific inspections should be derived from inspection procedures relative to the area being examined. Those procedures include, but are not limited to, the procedures listed in Appendix A of this procedure.

Specific Guidance 03.01 Inspection Plan

a. The licensees design and planning phase may begin several years before replacement.

Historically, contracts for RV head fabrication have been issued three or more years

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71007 before replacement. The licensee may perform install temporary or permanent modifications to transport the old and new RV heads through the plants well in advance of the selected outage. Significant design work and outage planning may be complete a year before the outage. The inspection should focus on RVHRP activities that will ensure the proper restoration of pressure boundaries of the RCS, containment systems, exclusion of foreign materials, and plant modifications that could affect plant risk during subsequent plant operation.

b. No specific guidance

c. If the inspector performs a 50.59 or design review related to the reactor vessel head replacement activities, the review should be coordinated with the NRR Project manager for the site and given consideration as a baseline sample and initiate preparation and planning for execution of this inspection procedure. For example, if a 50.59 or design review related to an extended power uprate (EPU) is taking place, which will require a reactor vessel head replacement, the reviews should be coordinated with the Resident Inspector Office and the regional EPU point of contact. This coordination allows sufficient notice and lead time to plan and prepare to adequately inspect the reactor vessel head replacement.

d. An early review of the licensee's RVHRP scope and schedule will provide advance opportunity to identify special inspection needs and plan the design and planning phase inspections. For the modifications installed prior to the outage, inspection before the outage is recommended. About a year before the selected outage, the licensee's outage scope and schedule should be detailed enough for the NRC inspector to develop the inspection plan for review of onsite work. Historically, inspection planning has typically been performed by a region-based inspector with input from the resident inspector.

e. The scope and depth of the inspection of these parts and the inspection hours credited to the baseline inspections should be in accordance with the guidance in this procedure.

Inspection planning for the baseline inspections should consider the extended schedule for the RVHRP and the prudent management of baseline inspection hours.

03.02 Design and Planning Inspections

a. The inspection plan should integrate the required design and planning inspections.

1. 10 CFR 50.59 evaluations and screening for such evaluations for selected modifications related to RVHRP should be reviewed using applicable portions of IP 71111.21M, Comprehensive Engineering Team Inspections, as guidance.

2. Inspection samples of permanent and temporary plant modifications for the RVHRP should be selected and reviewed as a part of the baseline inspection using IP 71111.18, Plant Modifications.

The inspection should verify that (1) key RV head design aspects such as those listed below, and RV head modifications, and the designs of other related significant modifications are reviewed and approved in accordance with procedures and (2) replacement materials and components meet the appropriate design technical requirements. Those technical requirements include the applicable codes and standards, NRC requirements, and other commitments made by the licensee in the FSAR.

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71007 The inspection should review design attributes like those outlined in IP 71111.18.

The following list illustrates typical topics that may need to be reviewed:

(a) The general design process for removal and reinstallation of the RV heads and related components.

(b) If needed, the design and analysis for the creation of a temporary containment opening for RV head replacement and its restoration - design reviews should be coordinated with the Structural, Civil, and Geotechnical Engineering Branch (ESEB), NRR, via the NRR Project Manager, to confirm the restored design margin.

(c) See Appendix B of this procedure for additional information.

(d) Compliance with regulatory requirements including the incorporation of inservice inspection requirements of 10 CFR 50.55a(g).

(e) Adherence to and reconciliation of ASME Code requirements:

The ASME Code does not specifically address control of machining operations or establish special requirements in this area. It is intended, however, that the manufacturer performing machining operate under a controlled fabrication system which complies with the requirements of ASME, NCA-4000. Non-code machine shops should operate under a system which meets the requirements of 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, for their scope of activities.

If a foreign manufacturer fabricated the head in accordance with the code of its country, reconciliation of ASME, specifically IWA-4000, would have to be made with that foreign code for design, fabrication, and inspection requirements (See ML030760715 for example). If a foreign fabricator of a RV head for a licensed facility in the United States is an ASME N-stamp holder, then the NRC would require that the RV head be ordered and fabricated to ASME N-stamp requirements.

Documentation should exist to prove that the RV head meets ASME Section III, Division 1, Subsection NB-2331 requirements of at least 35 mils lateral expansion and not less than 50 ft-lbs. absorbed energy to determine if it is susceptible to brittle failure at a specified temperature.

3. No specific guidance

b. The inspection should focus on the impact of load handling activities on reactor core and spent fuel and its cooling and plant support systems for the reactor unit and common systems for the other operating unit(s) at the site.

Several heavy lifting evolutions are expected. While the radiological consequences of a heavy load drop are expected to be small with the core defueled, a dropped component could result in an unwarranted radioactive release and severe damage to equipment needed for reactor or radiological safety.

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71007 The licensee's plans and analysis for lifting and rigging of heavy loads are reviewed to verify that lifting equipment and rigging can lift and move the RPV head, and the safe load path for component removal and reinstallation is technically sound. The inspection should focus on the impact of heavy load lifting operations on spent fuel and its cooling, support systems for the reactor, and common support systems for the other operating reactor unit(s) at the site.

The component drop analysis, if one was performed, should be reviewed to verify, in general, that the potential offsite releases at the exclusion area boundary are within 10 CFR Part 100, Reactor site criteria, limits and equipment to maintain safe shutdown will be unaffected.

Additional information on lifting heavy loads is available in Generic Letter 81-07, Control of Heavy Loads, NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, and Regulatory Guide 1.244, Control of Heavy Loads at Nuclear Facilities." Consider reference to OpESS 2007/03 Revision 3.

c. Specific guidance for radiation protection inspections is provided in IPs 71124.01, Radiological Hazard Assessment and Exposure Controls, 71124.03, In-Plant Airborne Radioactivity Control and Mitigation, 711124.04, Occupational Dose Assessment, 711124.06 Radioactive Gaseous and Liquid Effluent Treatment, and 71124.08, Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation.

The inspection should audit the licensee's outage radiation protection program and confirm that radiological concerns are factored into RVHRP planning. Lessons learned from industry experience should be factored into work planning. Plants with a history of fuel pin leaking problems should consider and assess the potential for airborne transuranics. When applicable, review of radiological airborne effluent release controls and accountability associated with the establishment and restoration of a temporary containment opening should be included in accordance with the inspection procedures listed in the preceding paragraph, as applicable.

Training for the large RVHRP work force should be geared toward the specifics of RV head removal/replacement for both the radiation workers and radiation protection personnel. Review of planning for radioactive materials management should be considered due to the need for temporary storage of reusable equipment and the handling of the increased volumes of waste generated in a short time period. Efficient removal of materials from the work area improves housekeeping and reduces fire hazards. Emergency contingencies such as actions for a dropped component and the plans for closure of the containment (including temporary openings) in a high airborne condition should be reviewed.

d. Security boundaries may be affected during the RVHRP. Mockup training is an effective ALARA training tool for certain work evolutions. The impact of the work on the boundaries and the licensee's contingency plans should be reviewed to verify conformance with the security plan.

1. Any security inspections should be credited to the applicable standard baseline inspections procedures for security.

2. No specific guidance.

Issue Date: 02/04/25 10 71007 03.03 RV Head Fabrication Inspections at Vendor Facility Appendices C and D to this procedure provides guidance for inspection and review of vendor fabrication processes. In addition, inspections in accordance with IP43002 and IP43003 of the vendor facility constructing the RV head can be credited towards this inspection procedure.

a. No specific guidance.

b. No specific guidance.

c. No specific guidance.

d. No specific guidance.

e. No specific guidance.

f.

No specific guidance.

g. No specific guidance.

h. Both Design Specification and Report should be certified by professional engineers competent in ASME Code requirements.

i.

No specific guidance.

j.

No specific guidance.

k. No specific guidance 03.04 RV Head Removal and Replacement Inspections

a. Some cutting, machining, and welding activities may be performed during the RV head replacement outages. Several procedures are listed in Appendix A to this procedure that contain useful guidance for welding inspections.

Training and qualifications of licensee and contract quality control/assurance inspectors, and NDE examiners are reviewed to verify personnel meet site and code qualification requirements and are prepared for the site-specific tasks. In the past, mockups have been used for qualifying welding procedures and training and qualifying welders, machinists, and NDE inspectors.

For the selected welds review weld procedures and welder qualification records, confirm that the Code required essential and supplemental essential welding variables for the welding processes used were met, and verify that preservice NDE requirements were completed for the reviewed weld records. Also, review the non-conformance reports for each reactor vessel head weld to confirm that welding deficiencies were dispositioned in accordance with Code requirements.

All rigging and lifting activities should be supported by analysis especially those for abnormal and emergency conditions.

Issue Date: 02/04/25 11 71007 There should be sufficient safety margin between test loads and actual loads so that rigging and lifting equipment can conservatively be considered able to handle the actual load.

All rigging and lifting equipment including special lifting devices and any modifications to that equipment should be approved by QA for future rigging and lifting activities.

b. No specific guidance.

c. The inspection should verify that modifications to walls and other structures and removal and restoration of component supports are documented.

d. A temporary containment opening may need to be established to allow for the movement of RV head components. The inspections should verify that the procedures and methods used to enlarge and restore the containment access ensure that the design assumptions and requirements are satisfied, and that the containment is restored to at least its required strength and integrity criteria. Post restoration testing should demonstrate that the containment has been properly restored. See Appendix B of this procedure for additional information.

e. Implementation of controls for personnel access to radiologically controlled work areas, surveillance of work activities, and procedure adherence should be verified. Reviews should be made of the implementation of ALARA, radiological exposure, contamination, and airborne contamination controls (including potential for transuranics) planned for cutting, welding, and other activities including contaminated interference removal. Also, implementation of any special controls for contaminated tools and waste should be reviewed. Where applicable, controls for shielding installations should consider the effects of additional weight loads on equipment.

If a temporary containment opening is established, the method of disposal of any concrete debris may be considered. While much of this material is not expected to be contaminated, consideration should be given to any activation materials including hard to detect isotopes such as H-3, Fe-55, and other hard-to-detect radionuclides (e.g.,

transuranics).

Review licensees evaluations of adverse impact of temporary services (electrical power, structural supports, and systems) on plant equipment and systems important safety.

If the old RV head is stored on site, the storage facility should be reviewed to verify that access is properly controlled, does not create the potential for an unmonitored effluent release pathway, and the external radiation levels at the perimeter are below applicable limits (consistent with the requirements of 10 CFR Section 20.1301, Dose limits for individual members of the public) and dose rates at the perimeter are below applicable limits. For additional information, refer to Generic Letter 81-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites.

03.05 Post-installation Verification and Testing Inspections.

The inspector should review the licensees post-installation verification and testing program to verify that modifications are completed in accordance with the design; that drawings, procedures, and training have been updated as appropriate; that post-installation walkdowns and inspections are performed to ensure equipment is

Issue Date: 02/04/25 12 71007 restored and temporary services are removed; that equipment cleanliness has been verified; that pre-service inspection of welds to establish baseline data are performed; and that deficiencies are properly dispositioned. Verify that changes in performance of the RV head and in its associated parameters, such as flow rates, pressures, and temperatures are appropriately included in design documents and plant procedures. In addition to reviewing the licensee's program to verify restoration, the inspector should perform independent walkdowns to confirm equipment restoration.

If a temporary containment opening was established for RV replacement, refer to Appendix B of this procedure for additional guidance on testing following restoration.

Direct inspection of portions of the primary and secondary system leakage tests and associated visual examinations and review of the test results should be performed. The inspection should verify that system leakage testing satisfies ASME Code,Section XI, IWA-5000, and applicable regulatory requirements, that testing was conducted according to the procedure, and that results were satisfactory or properly resolved.

Section 02.04 of Inspection Procedure 93803, Safety Systems Outage Modifications Inspection, contains additional inspection guidance for testing inspections.

a. No specific guidance.

b. No specific guidance.

c. No specific guidance.

d. No specific guidance.

e. No specific guidance.

71007-04 INSPECTION RESOURCES The required number of direct inspection hours per RVHRP plant will vary significantly based on several factors such as licensee experience, contractor experience, and the variable complexities of the given RV replacement. The scope and depth of the inspections should be sufficient to provide the desired level of assurance that the licensee adequately performs activities important to safety and that the relevant codes, standards, requirements, and commitments are met. The total resources required for RVHRP inspection using IP 71007 is estimated to be 425 direct inspection hours. It is expected that portions of the inspections in this procedure can be credited towards satisfying baseline inspections.

71007-05 SPECIAL REPORTING REQUIREMENTS Findings and violations will be assessed and documented using the criteria of IMC 0612, Issue Screening. All other documentation requirements should be applicable for this inspection procedure.

71007-06 REFERENCES ASME Boiler & Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components (See 10 CFR 50.55a, Codes and standards)

ASME Boiler & Pressure Vessel Code,Section IX, Qualification Standard for Welding, Brazing, and Fusing Procedures; Welders; Brazers; and Welding, Brazing, and Fusing Operators

Issue Date: 02/04/25 13 71007 ASME Boiler & Pressure Vessel Code,Section XI, (See 10 CFR 50.55a)

Generic Letter 81-07, Control of Heavy Loads at Nuclear Power Plants Generic Letter 81-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites NUREG-0612 Control of Heavy Loads at Nuclear Power Plants (ML070250180)

Regulatory Guide (RG) 1.136, Revision 4, Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments (ML20301A167)

RG 1.244, Revision 0, Control of Heavy Loads at Nuclear Facilities (ML21006A346)

RG 1.57, Revision 2, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components (ML12325A043)

END Appendices:

A. Applicable Inspection Procedures B. Temporary Containment Opening Review Guidance C. Additional RV Head Fabrication Inspection Requirements D. Head Fabrication & Preservice Record Reviews

Attachment:

1. Revision History for IP 71007

Issue Date: 02/04/25 AppA-1 71007 Appendix A: Applicable Inspection Procedures Inspection Procedure and Manual Chapter Nos.

Document Title 71111.18 Plant Modifications 71111.21M Comprehensive Engineering Team Inspection 71124.01 Radiological Hazard Assessment and Exposure Controls 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 71124.04 Occupational Dose Assessment 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 43002 Routine Inspections of Nuclear Vendors 43003 Reactive Inspections of Nuclear Vendors 55050 Nuclear Welding General Inspection Procedure 55100 Structural Welding General Inspection Procedure 57050 Visual Testing Examination 57060 Liquid Penetrant Testing Examination 57070 Magnetic Particle Testing Examination 57080 Ultrasonic Testing Examination Procedure 57090 Nondestructive Examination Procedure Radiographic Examination Procedure Review/Work Observation/Record Review 0326 Operability Determinations Containment Inspections 70307 Containment Integrated Leak Rate Test - Procedure Review 70313 Containment Integrated Leak Rate Test 70323 Containment Leak Rate Test Results Evaluation

• • May only be applicable when the containment access has been enlarged.

Issue Date: 02/04/25 AppB-1 71007 Appendix B: Temporary Containment Opening Review Guidance A.

OBJECTIVE This appendix provides additional guidance for inspection of activities associated with establishing a temporary containment opening in the containment shell for Reactor Vessel (RV) head replacement and its subsequent restoration.

B.

BACKGROUND To replace the RV head in containments that have small equipment hatches, some licensees have chosen to replace the RV head in one piece through a temporary transfer opening cut through the containment instead of disassembling the RV head and transporting its sections and components through the equipment hatch. Based on time and radiological considerations, this approach has generally been preferable. After completion of the RV head replacement, the opening is closed, the containment structure is restored to its original configuration and integrity, and structural integrity testing is performed. Cutting the temporary opening and closing it, may be carried out without NRCs approval under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, tests and experiments, provided the process does not involve a license amendment. However, since this process involves construction activities for a significant safety related structure in a nuclear power plant, quality assurance and quality control practices should be strictly followed, and the restoration of the containment should be inspected by the NRC.

C.

GUIDANCE GENERAL This appendix is intended to augment the existing inspection guidance in this procedure to identify regulatory concerns and licensee activities associated with cutting and closing a temporary containment opening. Some of the discussion below may overlap previous guidance and is only provided for clarity.

Nuclear Regulatory Commission inspection emphasis should be on verification that the containment is restored to its original integrity after closure of the temporary opening. Because actions related to cutting and restoring a temporary opening in a pre-stressed concrete containment encompass issues concerning reinforced concrete and steel containments, issues related to pre-stressed concrete containments are used as the basis for this appendix.

Therefore, some items discussed below may not apply to all containment designs.

Construction as used herein is an all-inclusive term that covers materials, design, fabrication, installation, examination, and testing. The licensee should prepare specifications covering all aspects of the construction of the temporary opening as discussed in the following sections.

REGULATORY CONCERNS In a pre-stressed concrete containment, the components that are cut and replaced include concrete, reinforcing bars, tendon sheathing, and the steel liner. The tendons, together with the grease in the sheathings that pass through the opening area, are removed before the opening is cut. The tendons may be reused in the restoration. The concerns are as follows:

Issue Date: 02/04/25 AppB-2 71007

1.

The steel liner plate (or metallic shell for steel containments) may be torch cut and reused. During reinstallation, the gap around the liner plate for welding may not be as uniform as it would be for new plates. The uniformity of the gap is dependent upon how skillfully the plate was initially torch cut. The strength of the replacement welds may not be the same as the uncut plate, but it should be very similar to the strength of the weld joints in the original structure. If the strength of the replacement welds will be less than the uncut plate, the reduction in weld joint strength should be evaluated as an engineering design change.

2.

The creep and shrinkage of the concrete used to close the opening, which is usually high for newly poured concrete, could result in higher compressive strain in the concrete adjacent to the repaired opening because of pre-stressing and may cause liner buckling.

3.

The creep and relaxation of reused tendons could cause the loss of pre-stress because of tensioning and de-tensioning.

4.

The leak tightness of the tendon sheathing may be compromised because of withdrawing and re-inserting the tendons, resulting in grease leakage. This leakage may reduce the strength of the concrete and leave the tendon unprotected.

5.

When containment boundary concrete replacement includes having the reinforcing bar splices lined up without staggering, confirm that an engineering-based evaluation has verified that the strength of the containment has not been compromised.

6.

After closing the opening, the containment is to be subjected to a containment pressure test and leakage test in accordance with Subsection IWL and Subsection IWE (specifically Articles IWL-5000 and IWE-5000) of the ASME Code Section XI, as incorporated by reference in 10 CFR 50.55a and subject to the applicable conditions in 10 CFR 50.55a(b)(2)(viii) and (ix). It should be noted that, when applying IWE-5000 to Class MC pressure-retaining boundary components, the condition in 10 CFR 50.55a(b)(2)(ix)(J) requires a Type A integrated leak rate test (ILRT) per 10 CFR 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors following a major containment modification or repair/replacement activity (e.g., construction openings for replacement of RV head, steam generators or pressurizers). Proposed alternative(s) to these requirements may be requested by the licensee and authorized by the NRC pursuant to 10 CFR 50.55a(z).

DESIGN REVIEWS Design reviews, if implemented, should be coordinated with the Structural, Civil and Geotechnical Engineering Branch (ESEB), the Office of Nuclear Reactor Regulation (NRR), via the Project Manager, to confirm the restored design margin of the containment structure.

Codes and Standards Acceptable options for industry codes and standards to be used for the design, construction, and restoration of the containment access are as follows:

(1) The codes and standards described in the FSAR, consistent with current regulations, as the basis of the facility operating license are to be utilized.

Issue Date: 02/04/25 AppB-3 71007 Or, and preferably, (2) To the extent practical, the latest ASME Boiler and Pressure Vessel Code (ASME Code) edition and addenda. Practical adjustments can be made in the use of the updated ASME Code provisions to accommodate the limitations of design and construction. The quality and overall margins required in the original design are to be maintained and should be included in decisions on the extent to which adjustments are made for using the updated ASME code provisions. If the licensee chooses this option, review of its acceptability should be coordinated with the ESEB via the NRR Project Manager.

Analysis The licensee should perform structural analyses for the containment, which considers the effect of the opening for the applicable loads and load combinations resulting from the containment opening.

Structural analyses of the containment structure should be performed considering both the presence of the temporary opening and conditions after its repair. This analysis should incorporate the properties of the materials of the replacement components, which may affect the behavior of the containment structure locally and globally. The analyses should demonstrate that the ASME Code allowable limits have not been exceeded in both cases. The loads and loading combinations for the restored configuration (post opening closure) of containment should be the same as those specified in the FSAR or the applicable Standard Review Plan sections. Also, consideration should be given to the conditions arising from the existence of the temporary opening, ranging from initial cutting to closing including potential construction loads.

For the interim configuration with temporary opening of containment, no design pressure (Pa )

load associated with the design basis accident will apply in the analysis.

Design Changes The materials and replacement components used to restore the containment should be like those originally used and documented in the FSAR except that the concrete used to close the opening can be adjusted to reduce the creep and shrinkage. If different materials or components are used, they should satisfy the applicable design criteria and requirements and provide an equivalent overall safety margin as provided in the originally licensed design.

TEMPORARY OPENING INSPECTIONS Based on the regulatory concerns previously described, the areas of inspection interest can be summarized as follows:

1.

Welding of the steel liner or shell since the torch cut may result in irregular edges. The welding process, use of proper materials, the skill and training of the welder, and post installation examination and testing should be considered. The replacement welds may not be the same strength as the original uncut liner, but it should provide joint strengths equivalent to the strength of the weld joints in the original structure.

2.

Proper concrete mix design and qualification and proper placement techniques should ensure that concrete in the repair area exhibits low creep and shrinkage. The certification of the concrete mix design should ensure that the design mix is like that used in original construction, and that the mix is controlled to reduce creep and shrinkage. Sufficient testing should have been done prior to placement to ensure that

Issue Date: 02/04/25 AppB-4 71007 design strength is attainable. The documentation of the certification of materials used in the concrete containment, such as aggregate, cement, water, and admixtures should be reviewed to ensure they meet specified quality requirements.

Witnessing the initial concrete placement is important to verify that the concrete is being handled and tested properly. In cases where the interior form for the concrete containment is the liner plate, additional stiffeners may be needed to prevent buckling.

3.

The tensioning force of the tendons, which may be reused, should be tensioned to a level of preload which would not cause more creep and relaxation. The pre-stressing sequence should also be carefully implemented to ensure its conformance with the original design basis.

4.

The control of grease filling should be such that the tendons are adequately covered and there is no leakage from the sheathing that can be observed on the surface of the containment.

5.

The rebar splicing around the opening and the use of the sister splices for quality control testing should be in conformance with the applicable design requirements.

Checks on the proper certification of the rebar and splice materials and worker qualifications may also be included.

6.

Witnessing of either the containment pressure test or the integrated leak rate test (ILRT) of the containment.

Fabrication, Installation, Examination, and Testing Fabrication, installation, examination, and testing with appropriate instrumentation are to be performed in accordance with the applicable ASME Code as stated above under "Codes and Standards" or the stipulations made in the FSAR. The behavior of the repaired containment structure locally and globally as obtained from the containment pressure test or the ILRT is to be assessed.

Generally, the facility technical specifications require periodic examinations of the containment integrity including inspections of the tendons. It is not expected that those examinations will be altered by the restoration of the temporary containment access. Of concern however is the potential for degradation of the containment structural integrity or leak tightness that could result from the restoration. For example, tendon degradation could occur due to moisture intrusion via a pathway created in a damaged or inadequately restored tendon duct. An assessment should be of the licensee's measures and/or planned actions (e.g., analysis, testing, examination) to verify that containment integrity is maintained following the restoration. Assistance in performing this assessment should be coordinated with the Structural, Civil and Geotechnical Engineering Branch (ESEB), NRR, via the Project Manager.

Inspection and Quality Assurance Quality assurance and independent (third party) inspection requirements for cutting and closing the temporary opening are applicable. Verification of these activities should be performed.

Issue Date: 02/04/25 AppB-5 71007 Training and Qualification The training and qualifications of craft and quality assurance personnel may be reviewed as there have been past problems with the use of inexperienced personnel.

END

Issue Date: 02/04/25 AppC-1 71007 Appendix C: Additional RV Head Fabrication Inspection Requirements

a. For castings, verify that procedures for obtaining test coupons from material are consistent with paragraph NB 2226 of ASME Section III (Reference 5).

The code paragraph references given in Section Il of this procedure are based on the 1974 edition of the ASME Code. It is recognized that other code editions may apply to in-process work being reviewed under this procedure. It is also recognized that special heat treatment requirements may be contained in the equipment specifications or procurement documents for the parts of materials under review. The inspector is responsible for determining the applicable construction standards and developing specific evaluation criteria for such situations.

b. Verify that personnel training, indoctrination and/or certification requirements have been established for heat treating, special processes, casting and forging, and for machining operations.

c. Observe heat treating operations in progress. Verify that approved procedures are available at workstations and that these procedures are followed. Specifically, review the control of process variables itemized in Step 02.03 b. Verify that heat treatment test coupons receive similar heat treatments as the components they represent.

d. Verify that procedures have been established for controlling and implementing casting and forging operations with heat traceability throughout the manufacturing process.

Heat traceability is required since it is the most practical method for assuring material identification

e. Verify that the requirements exist for identifying what manufacturing processes are used and verify functions are special processes and for qualifying the implementing procedures by determining if the processes are fully functional.

For the purposes of this procedure, special processes can be defined as metallurgical, chemical, mechanical, or other processes which may produce significant changes in the properties or characteristics of the product and where assurance of satisfactory results is largely dependent on the use of qualified procedures, personnel, and equipment. In most applications of special processes, the assurance of quality can not be obtained by direct inspection of the in-process activity or final product.

f.

Verify that a system has been established and implemented for documentation of work performance (including required verification and testing) when special processes are used in manufacturing.

g. Examine the performance of selected special processes as required. Verify that qualified procedures are being followed and that the work is performed by personnel trained and certified in accordance with the manufacturers quality assurance (QA) program requirements.

Criterion IX of Appendix B includes welding, and nondestructive testing as special processes. These activities are reviewed individually under separate procedures (IPs 55050, 55100, for welding; and 57050 to 57090 for Non Destructive Examination).

Examples of special processes are the following:

Issue Date: 02/04/25 AppC-2 71007

1. heat treating

2. chemical cleaning

3. etching, pickling, or passivating

4. vapor de-greasing

5. electroplating

6. anodizing

7. painting, coating, or surface conditioning

8. shot-peening

9. sand or shot blasting

10. special metal removal techniques (example: Elox, E.M.)

h. Verify that provisions have been established for segregation of nonconforming materials and parts.

The inspector is expected to perform a thorough review of applicable material or equipment specifications, procurement documents, and the manufacturers process qualification data to form additional bases for his evaluation.

i.

Visually inspect the RV head and verify proper identification and conformance to specification requirements within the limits of visual examination (VT). Emphasis shall be given to surface condition and geometry such as body contour, weld ends, and fillets end weld appearance at intersection of pressure boundary surfaces. If applicable, verify that minimum wall thickness has been determined and meets equipment specification requirements.

j.

Verify that in-process changes at the shop floor level are being handled in accordance with established and approved procedures consistent with the manufacturers QA program.

k. Verify that in-process and final inspections are conducted in accordance with production plan requirements, that acceptance/rejection criteria have been established and personnel responsible for inspection have been identified.

l.

Verify that provisions have been established to identify rejected items and removal of these items from the process flow.

m. Verify that procedures have been established for resolving nonconforming items and that these procedures are being implemented on the shop floor in the manufacturing process.

n. Verify that procedures for repair and acceptance standards for rejected items have been established.

o. Verify that gages and measuring devices on the shop floor which are used for determining acceptability of the product are under control of an established gage calibration system meeting Criterion XII of Appendix B.

p. Verify that adequate procedures are available and are being followed for protection of finish-machined surfaces and for prevention of damage to finished parts and components during handling and transfer.

Issue Date: 02/04/25 AppC-3 71007

q. If applicable, verify that new or and unique processes for metal removal such as electrical discharge machining or chemical milling are evaluated and qualified before using them in production.

It is emphasized that poor machining practices can have a significant effect on performance and life expectancy of parts and components. Improper machining techniques, such as the use of excessive feed rates or improper or dull tooling for example can significantly degrade surface integrity and cause accelerated fatigue failure or stress corrosion attack.

r. Verify that use of cutting fluids is controlled and that precautions are taken to minimize contamination of austenitic stainless steels and high nickel alloys with halogen or sulfur-containing oils.

Similarly, inadequate radii or sharp corners can cause high stress concentrations resulting in premature failures.

s. Verify that approved cleaning and de-greasing procedures are available and are being followed.

The inspector is expected to perform a review of applicable material and equipment specifications, procurement documents and the manufacturers process qualification data, as applicable to form additional bases for his evaluation.

t.

Observe selected machining operations. Verify that required tooling and cutting speed and feed rates are specified and followed.

u. Examine representative sampling of finish-machined parts of RV head. Verify proper identification and conformance to specification and drawing requirements within limits of visual inspection. Verify that step changes in diameters of shafts and other section transitions are blended to specified radii and that the specified surface finish is achieved on critical areas such as sealing surfaces. If questionable, ask for measurement.

Issue Date: 02/04/25 AppD-1 71007 Appendix D: Head Fabrication & Preservice Record Review Checklist

1. Record Background Information, Review Material Specifications and ASTM Standards

Response

Construction Code Edition (e.g.,Section III, 95 Edition 96 Addenda)

Preservice Code Edition Section (e.g.,Section XI, 89 Edition No Addenda)

General Source and Sequence of Component Fabrication (e.g., Head Forging

- JSW, Nozzles - Valinox, Cladding/Buttering & Final Welded Assembly -

AREVA)

Head Forging Material (e.g., SA-508 Grade 3, Class 1, SA-788, ASTM E208-91, ASTM A-275)

VHP Nozzle Material (e.g., SB 167 UNS N06690)

CRDM/CEDM Housing Material (e.g., SA -312, SA-376 or SA-182)

Date of Post-Weld Heat Treatment (PWHT)

Date of Hydro Test

Issue Date: 02/04/25 AppD-2 71007

2. Detailed Review Checklist - Suggested Items for Review (based on design and construction for a typical PWR vessel head). The information below in the Attributes to Verify/Acceptance Criteria and ASME Code Section III Requirement columns should verified by comparing them to the ASME Construction Code Edition and Addenda for the component being inspected.

Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments Head Forging -

Heat Treatment &

PWHT NB 4622 NB 4623 ASME Code Section II SA-508/SA-508M and SA-788 SA-508 Gr 3, Class 1 -

Heat treatment (1540- 1640 F) water quench. Temper (1200 F or 1175 F minimum - depending on S13 and grade) for min 1/2hr per inch per SA spec.

PWHT (after cladding and J-groove weld butter) 1100-1250 F for 2hrs +

15 minutes/inch over 2 inches (Table NB 4622.1-2). Note - PWHT time for single piece head forging controlled by nominal weld thickness attaching the lifting lugs.

Verify minimum 1/4-inch butter on J-groove weld prep before PWHT (NB-4622.8 (a) 1).

Confirm licensee/QA/ANI audits of furnace atmosphere, temperature, TC placement and calibration. Also, of vender quenching practices including, quenching media and max transfer time.

CMTR, purchase spec, vendor heat treat strip charts.

Fabrication Process Control Sheets.

QA audits of furnace atmosphere, temperature, TC placement and calibration and quenching practices.

Issue Date: 02/04/25 AppD-3 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments Head Forging -

Material &

Tolerances NB 2120 NB 4222 ASME Code Section II SA-508/SA-508M and A-788 Material Spec used in accordance with (i.a.w.) Table I-1.0 of Section II (e.g., typically SA 508, but if different it is listed in Section II)

Chemistry per SA 508 Table 1.

Mechanical properties per SA 508 Table 2.

Dimensional checks to confirm cross-sectional diameter i.a.w. NB 4222.1 and deviation from specified shape i.a.w. NB 4222.2.

Diameter and thickness measured is within Fabrication drawing tolerances.

CMTR Fabrication Process Control Sheets.

Head Forging -

Toughness NB 2330 ASME Code Section II SA-508/SA-508M and A-788 Drop weight test (IAW ASTM E-208-

91) to establish the nil ductility transition temperature (T NDT).

Charpy Impact test (IAW SA-370) of heat of forging 1/4 T from surface.

Three specimens tested at (T NDT +

60°F) shall each have a minimum of 35 mils lateral expansion and 50 ft-lbs. absorbed energy.).

Also, meet SA -508 Table 3 impact toughness acceptance criteria.

CMTR

Issue Date: 02/04/25 AppD-4 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments Head Forging Material NDE NB 2540 NB 6220 ASME Code Section II SA-508/SA-508M and A-788 Visual Testing (VT), Magnetic particle testing (MT) Ultrasonic testing (UT) by forging vendor IAW SA-508 to meet ASME Code,Section III acceptance criteria and Perform UT to NB 2542 and Section V Article 5, and MT or Liquid penetrant testing (PT) all external/internal surfaces IAW Section V Article 6 or 7 and NB 2545 or NB 2546. NDE after quench and temper (NB 2520).

Hydro head forging and RPB nozzles and CRDM assembly IAW NB 6100 and hydro pressure at 1.25 design for 10 minutes IAW NB 6221 - No leaks.

CMTR, NDE records, Hydrostatic test records.

Fabrication Process Control Sheets.

Head Forging -

Repairs NB 2549 NB 4132 Head repair locations > 3/8 inch deep have been documented and RT after repair and heat treatment occurs after repair.

Repair areas blended and MT or PT after repair.

CMTR Fabrication Process Control Sheets.

Issue Date: 02/04/25 AppD-5 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments VHP Nozzles -

material NB-2120 NB 2550 ASME Code Section II SB-167 Chemistry per SB spec Table 1 Mechanical properties per SB spec Table 2.

Hydrostatic test 1000 psig per SB spec Section 12.3.

UT are performed in 2 circumferential and 2 axial directions (NB 2551, NB 2552.1 & NB 2552.2).

CMTR, Purchase Spec, Hydrostatic Test Record, NDE records.

J-groove Weld Qualification NB 4330 ASME Code Section IX, QW-432, ASME Code Section II SFA 5.14 ERNiCrFe-7 Weld procedures qualified per Section IX and NB 4330.

Verify procedure qualification record (PQR) requires minimum 1/4-inch butter deposit on mock J-groove weld prep before PWHT of qualification weld (NB-4622.8 (a) 1).

Weld operators qualified per Section IX.

Weld Material IAW SFA spec.

WPS, PQR, CMTR, Welder qualification records or QA Audit of welder qualifications.

Issue Date: 02/04/25 AppD-6 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments J-Groove Weld Fabrication NDE NB 5240 ASME Code Section V Article 6 Category C partial penetration joint, PT of weld (NB 5231(d) and 5245).

Progressive PT examination at 2-inch intervals.

Final PT again of all welds or repair areas after PWHT (NB 5120) and after hydro IAW NB 5410.

PT procedure IAW Section V Article 7 and acceptance criteria IAW NB 5350.

PT exam records show acceptable exam results.

NDE personnel qualified IAW NB-5500.

NDE records and Fabrication Process Control Sheets. PT procedure and examination records.

NDE personnel qualification records or QA Audit of qualification records.

J-groove Weld

- Repairs NB 4622, NB 4450 ASME Code Section IX, QW-432, ASME Code Section II SFA 5.14 ERNiCrFe-7 Weld repairs are documented and PT exam before and after repair including drawing to shows specific location and size of repair IAW NB 4450.

Weld procedure qualified IAW NB 4331 and NB 4622.11 for repairs which extend to within 1/4-inch of ferritic base material and repairs limited to 100 sq inches.

Final PT exam records show acceptable exam results.

Fabrication Process Control Sheets.

Non-conformance reports (NCRs). Weld procedures and procedure qualification records.

VT and PT examination records.

Issue Date: 02/04/25 AppD-7 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments CRDM/CEDM Housing -

Material NB-2120 NB 2550 ASME Code Section II SA-312 or SA-376 or SA-182 Chemistry per SA spec Table 1.

Tensile test per SA spec Table 3.

UT in 2 circumferential and 2 axial directions (NB 2551, NB 2552.1 & NB 2552.2). If housing is considered a fitting, MT on all external surfaces and accessible internal surfaces and UT if over 6 inches nominal size (NB 2551(b)).

CMTRs, NDE records.

CRDM/CEDM Housing Weld Qualification NB 4330 ASME Code Section IX, QW-432, ASME Code Section II SFA 5.14 ERNiCrFe-7 Weld procedure qualified per Weld procedure qualified IAW NB 4331 and Section IX.

Weld operators qualified per Section IX.

Weld Material IAW SFA spec.

WPS, PQR, CMTR.

Welder qualification records or QA Audit of welder qualifications

Issue Date: 02/04/25 AppD-8 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments CRDM/CEDM Housing Weld Fabrication NDE NB 5220 ASME Code Section V Article 2 &

6 Category B circumferential joint, RT (NB 5320) and PT (NB 5351) of weld and 2 inch of base metal as required by NB 5221 & NB 5140.

RT film records show appropriate penetrameter and image quality indicator (IQI) (e.g., 2T or 4T hole)

IAW Table NB 5111-1 for weld thickness. RT procedure IAW Article 2 of Section V has appropriate acceptance criteria of NB 5320 and film records confirm no rejectable defects.

PT procedure IAW Article 7 of Section V and has acceptance criteria of NB 5350.

RT and PT exam records show acceptable exam results.

NDE personnel qualified IAW NB-5500.

NDE records and Fabrication Process Control Sheets. RT and PT examination records.

NDE personnel qualification records or QA Audit of qualification records..

Issue Date: 02/04/25 AppD-9 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments CRDM/CEDM Housing Weld Repairs NB 4450 ASME Code Section IX, QW-432, ASME Code Section II SFA 5.14 ERNiCrFe-7 Defect removal and documentation, PT of cavity, rewelding and final PT IAW NB 4450.

PT exam records show acceptable exam results.

Fabrication Process Control Sheets.

NCRs. Weld procedures. VT and PT records.

Head Clad Welding NB 2400 NB 4622 NB 4429 NB 4330 ASME Code Section IX, QW-432, ASME Code Section II SFA 5.9 or SFA 5.4 type 308L or type 309 Weld procedures qualified per Section IX and Section III, Articles NB 4330, NB 4429 and NB 4434.

Weld Material IAW SFA spec.

Weld operators qualified per Section IX.

PWHT after cladding per table NB 4622.1-2 (Typical 3 hr. 15 min. for 7-inch-thick head).

Fabrication Process Control Sheets.

WPS, PQR, CMTR.

Welder qualification records or QA Audit of welder qualifications.

Issue Date: 02/04/25 AppD-10 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments Head Cladding

- NDE NB 5272 ASME Code Section V Article 6 Process Control plan has PT of cladding per NB 5272.

PT procedure IAW Section V Article 7 and acceptance criteria IAW NB 5350.

PT exam records show acceptable exam results.

NDE personnel qualified IAW NB-5500.

Specifications should require UT of cladding to check for laminations (this is not a Code requirement).

Fabrication Process Control Sheets.

PT procedure and examination records.

Head Cladding

-Repairs NB 4622.10 NB 4450 Cladding repairs are documented and PT exam before and after repair including drawing to shows specific location and size of repair. Repair conducted IAW NB 4450.

Non-postweld heat treat welded cladding repairs IAW weld procedure qualified to NB 4622.10 (e.g., preheat 350 F and max interpass 450 degrees F). Repair limited to 100 sq. in.

Fabrication Process Control Sheets.

Non-conformance reports. Weld procedures. VT and PT records.

Head Cladding

- Dimensions Fab Drawing Head clad thickness checks IAW drawing.

Fabrication Process Control Sheets.

Issue Date: 02/04/25 AppD-11 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments NDE Acceptance and Machining NB 5300 Fabrication Process Control and NDE records call out and meet acceptance standards of NB 5300 as checked above. Finished head machining dimensional and surface finish checks.

Fabrication Process Control Sheets.

NDE records.

NCR RecordsSection III, Fab Drawings Sample of non-conformance reports (NCRs) and QA audit findings with disposition consistent with Code and fabrication drawings. Deviations from Code have appropriate ANI and NRC approval.

NCRs, Audit findings, condition reports, CVARs, etc.

Audit RecordsSection IX, 10 CFR Part 50 Appendix B

Sample welding and welder & NDE qualification audits or ANI records that confirm welding procedure and welder qualification and NDE qualification was meets Code.

Sample audits of CMTRs and drawing controls by QA or ANI.

Audit Records.

Process Control Sheet required Audits of welding or welder qualifications.

Preservice NDE of CRDM/CEDM Housing Welds ASME Code Section XI, IWB 2200 Table IWB 2500 Cat B-0 Item B.14.

ASME Code Section XI, Appendix III UT,Section V, Article 6 PT 100 percent of peripheral control rod drive housings (typically 9) have volumetric and/or surface examinations IAW Cat B-0 Item B.14.

UT and PT procedures applied acceptance Standards of IWB-3523 to the entire weld surface/volume required by Section XI figure IWB-2500-18.

UT and PT procedures and examination records for periphery housing welds.

Issue Date: 02/04/25 AppD-12 71007 Component Area ASME Code Section III (95 Edition)

Requirement Material Spec/

Drawings Attributes to Verify/ Acceptance Criteria Documents to Review Sat/ Unsat -

Comments Preservice NDE of J-groove Welds NRC Order 03-009.

NA No Code required preservice records for J-groove welds for operating plants prior to 2003. After this period, preservice required by Code Case N-729 with conditions as incorporated by reference in 10 CFR 50.55a.

UT/PT/VT Baseline records exist to support future NRC Order 03-009 mandated examinations.

Extent of examinations is consistent with volumetric and surface examination coverage required by the NRC Order.

Typically, PT white acceptance for PT and 10% of base metal thickness for UT recording criteria.

UT/PT/VT NDE examination records and procedures for J-groove welds.

Other Component Areas to consider if time permits -

Lifting Lugs and Welds, RVLIS and Head Vent Pipe and welded connections, CRDM/CEDM rod travel housings.

Issue Date: 02/04/25 Att1-1 71007 : Revision History for IP 71007 Commitment Tracking Number Accession Number Issue Date Change Notice Description of Change Description of Training Required and Completion Date Comment Resolution and Closed Feedback Form Accession Numbers (Pre-Decisional, Non-Public)

N/A ML030510567 02/12/03 CN 03-003 Initial issuance. Completed Four-year historical review N/A N/A ML031980121 07/10/03 CN 03-024 Revised N/A N/A N/A ML052900107 03/16/06 CN 06-007 IP 71007 has been revised to improve effectiveness of this procedure based on feedback from the regions.

N/A ML060530184 N/A ML062760143 10/19/06 CN 06-028 Revised to incorporate comments from Feedback Form 1048: Changed Section 03.02.a.2.(a.) from an energy requirement of 75 ft-lbs. for the RV head to agree with ASME Section III, Division 1, Subsection NB-2331 requirements of at least 35 mils lateral expansion and not less than 50ft-lbs absorbed energy.

N/A N/A N/A ML071080026 06/04/07 CN 07-018 IP 71007 has been revised to add Appendix D to provide guidance for inspection and review of vendor fabrication processes.

N/A ML071440112 N/A ML17177A068 10/03/17 CN 17-020 Minor revision to include recommendations from the following feedback forms: 71007-1861, 2033, and 2259.

N/A N/A N/A ML22201A503 02/04/25 CN 25-001 Researched commitments for 4 years and found none.

Minor editorial changes. This completes the 5-year review.

N/A ML25006A206