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.

02.01 [Purchase and Receipt of Components.]{.underline} Verify that the
purchased RPV and internal components are in accordance with the
approved design.

[Guidance:]{.underline} 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.]{.underline} Verify that the RPV and
internal components are properly stored and handled in accordance with
approved procedures.

[Guidance:]{.underline} 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 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.]{.underline} Verify by observation or records
that the RPV is installed in accordance with design drawings.

[Guidance:]{.underline} 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]{.underline}. Verify that procedures
for protection of the installed reactor vessel are being followed.

[Guidance:]{.underline} 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.
>
> \$ 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]{.underline}.
Verify that RPV internals are installed in accordance with approved
procedures and design requirements.

[Guidance:]{.underline} 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.

02.06 [Installation of RPV Head:]{.underline} Verify that the RPV head
is installed in accordance with contractor and licensee procedures.

[Guidance:]{.underline} 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]{.underline}: 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:]{.underline} 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]{.underline}: 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:]{.underline} 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

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

Attachment 1

Revision History For 65001.05

+--------+-------+-----------------------+------+-------+-------------+
| Comm   | Issue | Description of Change | Trai | Tra   | Comment     |
| itment | Date  |                       | ning | ining | Resolution  |
| Tr     |       |                       | Ne   | Com­pl | Accession   |
| acking |       |                       | eded | etion | Number      |
| Number |       |                       |      | Date  |             |
+--------+-------+-----------------------+------+-------+-------------+
| N/A    | 08/   | Researched            | N/A  | N/A   | N/A         |
|        | 19/08 | commitments for 4     |      |       |             |
|        |       | years and found none. |      |       |             |
|        | CN    |                       |      |       |             |
|        | 0     | Initial issue to      |      |       |             |
|        | 8-024 | support ITAAC related |      |       |             |
|        |       | New Reactor           |      |       |             |
|        |       | Construction          |      |       |             |
|        |       | Inspections under     |      |       |             |
|        |       | 10CFR52               |      |       |             |
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