Issue Date: 08/19/08 1 65001.05 

ATTACHMENT 65001.05 

INSPECTION OF ITAAC-RELATED INSTALLATION OF 

REACTOR PRESSURE VESSEL AND INTERNALS 

PROGRAM APPLICABILITY: 2503 

65001.05-01 INSPECTION OBJECTIVES 

01.01 Verify that the purchased RPV and internal components are in accordance with the 

approved design. 

01.02 Verify that the RPV and internal components are properly stored and handled in 

accordance with approved procedures. 

 

01.03 Verify by observation or records that the RPV is installed in accordance with design 

drawings. 

01.04 Verify that procedures for protection of the installed reactor vessel are being 

followed. 

01.05 Verify that RPV internals are installed in accordance with approved procedures and 

design requirements. 

01.06 Verify that the RPV head is installed in accordance with contractor and licensee 

procedures. 

01.07 Verify that documentation packages for the RPV and internals installation are 

thorough and accurate. 

01.08 Verify that problems identified during the inspection are entered into the 

licensee/constructor corrective action program in accordance with program requirements. 

65001.05-02 INSPECTION REQUIREMENTS AND GUIDANCE 

This inspection procedure (IP) will be performed to verify critical activities related to the 

storage and handling, installation, examination, and testing of the RPV and internal 

components. Critical activities for this procedure include receipt and storage of the RPV on 

site, final placement of the RPV and internals per design drawings, and activities related to 

the installation and preparation of RPV internal components. For this IP, the field activities 

related to the RPV and internals installation ITAAC should be in accordance with the 

provisions of those ITAAC and other appropriate design documents. This IP will probably 

be performed in several inspections; therefore not all of the steps of this IP have to be 

performed for each inspection. 
Issue Date: 08/19/08 2 65001.05 

02.01 Purchase and Receipt of Components. Verify that the purchased RPV and internal 

components are in accordance with the approved design. 

Guidance: The purchase order and accompanying documentation should be in 

compliance with the design requirements. The licensee=s receipt inspection should identify 

any nonconformances and whether the disposition of each was acceptable. The purchase 

order should identify the type of quality documentation required (e.g., Certified Material 

Test Report (CMTR)). For a CMTR, the chemical and physical test results for materials 

such as plate, forgings, piping, and welding consumables, including heat treatment as 

applicable, should comply with the material specification required by the design 

documents. For example, materials in the beltline region of the RPV may have a minimum 

Charpy upper shelf value of 75 foot-pounds at a specified temperature. Although the RPV 

head may not be attached to the RPV at this time, the RPV head if available onsite should 

be included with this review. Typical attributes included in receipt inspections are: 

$ Components in conformance with purchase specification 

$ Marking and identification 

$ Evidence of damage 

$ Cleanliness at time of receipt 

$ Surface protection, closures, and packaging 

$ Maintenance of inert gas cover 

02.02 Storage and Handling. Verify that the RPV and internal components are properly 

stored and handled in accordance with approved procedures. 

Guidance: The RPV and internals require special handling and storage considerations 

due to their size, mass, and cleanliness requirements. The storage and handling of the 

RPV head should also be taken into account. Lifting devices, rigging, and pathways must 

be specifically designed and tested and/or examined by nondestructive examination (NDE) 

before use. For example, prior to transporting the RPV to the building, the access roadway 

may require extensive rework, and a test load transported over it. Procedures will require 

that the lifting device and rigging support the load for some designated time period before 

commencing the lift, and the lift rate should be controlled. This is done to verify lifting 

device stability and wire rope stretch. Travel speed while being transported must be 

controlled. Rigging and lifting procedures for these components must be strictly followed. 

The inspectors may refer to four listed EPRI documents in the references to this IP for 

insights on rigging practices. 

The RPV and internal components are often stored outside and exposed to the elements in 

lay-down areas located around the construction site. As such, carbon steel components 

may develop a light coating of oxidation (rust). This condition is generally acceptable; 

however, welding surfaces such as machined or ground bevels must have the rust 

completely removed prior to the welding operation. Stainless steel components should be 
Issue Date: 08/19/08 3 65001.05 

stored separate from carbon steel components as contact with carbon steel will 

contaminate the stainless steel and cause surface rust to appear. Likewise, carbon steel 

chains should be avoided when rigging to lift stainless components. Any tape used on 

stainless steel, such as to hold end caps in place, should be verified as containing low 

halogen and chlorides as these are known to promote cracking. 

The RPV may be stored in a covered building or may be stored outside. The following 

criteria, as applicable, should be addressed for storage of the RPV head. Typical attributes 

to verify are: 

$ The reactor vessel is stored in accordance with approved procedures. 

$ The condition of seals and devices to maintain and indicate vessel internal 

atmospheric conditions are in accordance with requirements. 

$ The condition of protective coating or/and protective covering is/are in conformance 

with requirements. 

$ The dunnage or packing should prevent entry of dirt and water 

$ The RPV=s support structure should prevent flooding based on its height and have 

the appropriate strength to be able to bear the weight of the RPV. 

02.03 RPV Installation. Verify by observation or records that the RPV is installed in 

accordance with design drawings.

Guidance: The RPV as-installed elevation and azimuth are most critical. The location of 

the RPV and support system are generally established with laser equipment that is very 

precise. Any deviation from design may result in unacceptable cold spring of connecting 

piping and must be resolved. 

02.04 Installed Vessel Protection. Verify that procedures for protection of the installed 

reactor vessel are being followed. 

Guidance: The installed RPV will be exposed to a construction environment within the 

containment and must be protected from both physical damage and foreign material entry. 

 The vessel closure head flange surface and vessel nozzles are particularly susceptible to 

physical damage. Foreign material exclusion (FME) practices must be maintained 

throughout construction. Typical attributes to verify during inspection are: 

$ Procedures for protection of the installed reactor vessel are followed. 

$ Protective devices installed around the top of the open vessel prevent entry of 

foreign objects and debris and protect the flange surface. 

$ Vessel side openings are blanked off to prevent entry of foreign objects, and nozzle 

ends are protected from construction damage. 
Issue Date: 08/19/08 4 65001.05 

$ Work platforms and scaffolding inside vessel are nonflammable or treated to 

prevent the spread of accidental fires, and fire watch procedures are implemented 

when applicable. 

$ Access to RPV is controlled, i.e., entry of authorized tools, equipment, and 

personnel only. 

02.05 Installation and Welding of Reactor Internals. Verify that RPV internals are installed 

in accordance with approved procedures and design requirements. 

Guidance: The extent of field welding activities of reactor vessel internals may vary 

significantly with different contractors. Historically, BWRs have required more field welding 

of internals than PWRs. Welds will require some form of nondestructive examination. 

Accurate orientation of internals and maintenance of cleanliness requirements are of 

primary concern. The upper and lower internals assemblies, control rod drive 

mechanisms, and incore instrumentation guide tubes are classified as American Society of 

Mechanical Engineers (ASME), Section III components. Typical inspection attributes to 

verify are: 

$ Documentation, such as Code data reports for internal components is in 

compliance with ASME Section III requirements. 

$ The orientation and fit up of internal components is in accordance with the Nuclear 

Steam Supply System (NSSS) contractor and design document requirements. 

Application of excessive force to the extent of bending or cold springing of internal 

components is not permitted unless required by engineering analysis. 

$ Welding activities are in accordance with NSSS specifications and Code 

requirements. IP 65001.B, AWelding@ can be used as a general guide to inspect 

RPV internals welding. Historically, alignment of components has necessitated the 

use of Adraw bead@ welding. This technique relies on weld bead shrinkage to effect 

movement of components. If this technique is utilized, there should be strict 

procedural conformance. 

$ Bolting material for internal components meets design requirements, and preload 

specifications have been met. RPV internal bolting will generally include some 

positive means for preventing loosening. 

$ Housekeeping and FME procedures must be strictly enforced. 

$ Final NDE has been performed on any installation welds and found acceptable, in 

accordance with the applicable code and the work package instructions. Observe 

NDE in progress on at least three welds, but the inspector can observe more welds 

in progress than just three. Examiners must be qualified for the method and 

procedure that they are performing. If NDE is not being performed during the 

inspection, perform a record review. 
Issue Date: 08/19/08 5 65001.05 

02.06 Installation of RPV Head: Verify that the RPV head is installed in accordance with 

contractor and licensee procedures. 

Guidance: This procedure is concerned mainly with the RPV and internals. However, 

this step is included to ensure that inspectors observe the first installation of the RPV head 

at a time late in construction. 

02.07 Records Review: Verify that documentation packages for the RPV and internals 

installation are thorough and accurate. Confirm installation in accordance with the 

provisions of the design specification and applicable codes. Review the completed 

documentation for the RPV and at least one internal component. 

Guidance: The final documentation package for the RPV and internals installation shall 

contain the necessary information and references to confirm that the installation meets the 

design and Code requirements, including. 

$ Components and welding consumables are uniquely identified (e.g., heat number) 

such that the inspector can verify material composition and physical characteristics 

are in accordance with the design documents. 

$ Welding and NDE procedures and personnel are identified for each weld. NDE 

results indicate that acceptance criteria were met. 

$ As-built drawings are available and any deviations from original design are 

reconciled with the design documents (e.g., design report). 

$ Documentation indicates that all required tests (e.g., hydrostatic test) and 

examinations (e.g., alignment verifications) have met the acceptance criteria. 

$ Code data reports are complete and signed off by the assigned Authorized Nuclear 

Inspector. 

02.08 Problem Identification and Resolution: The inspector should confirm that problems 

identified during the inspection are entered into the licensee/constructor corrective action 

program in accordance with program requirements. The inspector may review licensee 

actions to address similar or related problems that were previously identified, in order to 

verify that the licensee identified the extent of conditions and to confirm the effectiveness 

of the licensee=s corrective measures. 

Guidance: This inspection activity is to assure that the licensee identifies, prioritizes, and 

take measures to correct problems. Inspections of QA Program implementation, 

effectiveness of Problem Identification and Resolution, and Self-Assessment will be 

performed under IMC 2504. 

65001.05-03 RESOURCE ESTIMATE 

Inspection resources necessary to complete this inspection procedure are estimated to be 
Issue Date: 08/19/08 6 65001.05 

920 hours of direct inspection effort over the course of plant construction. 

65001.05-04 REFERENCES 

Regulatory Guide 1.39, "Housekeeping Requirements for Water-Cooled Nuclear Power 

Plants" 

Regulatory Guide 1.31, AControl of Stainless Steel Welding@

ASME Boiler and Pressure Vessel Code, Section III, Subsections NA and NB 

ASME Boiler and Pressure Vessel Code, Sections V and IX 

Regulatory Guide 1.65, "Materials and Inspections for Reactor Vessel Closure Studs" 

EPRI 1007914, ALifting, Rigging, and Small Hoist Usage Program Guide@

EPRI 1009706, ARigger=s Handbook@

EPRI 1007676, AGuidelines for Using Synthetic Slings for Lifting and Rigging@

EPRI 1000986, ACrane Maintenance and Application Guide@

END 

Attachment 1: Revision History for IP 65001.05 
Issue Date: 08/19/08 Att1-1 

Attachment 1 

Revision History For 65001.05 

Commitment Tracking Number 

Issue Date Description of Change Training 

Needed 

Training Completion Date 

CoAc

N/A 08/19/08 

CN 08-024 

Researched commitments for 4 years and found none.

Initial issue to support ITAAC related New Reactor Construction Inspections under 10CFR52 

N/A N/A N/A