Issue Date: 12/04/08 1 50054 

NRC INSPECTION MANUAL CVIB

INSPECTION PROCEDURE 50054 

REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 

PROGRAM APPLICABILITY: 2504 

50054-01 INSPECTION OBJECTIVES 

To verify by review of the applicant=s reactor vessel (RV) surveillance capsule program as 

described in the combined operating license (COL) and as approved pursuant to 

10 CFR 52 requirements that: 

a. Capsule brackets (CBs) are designed, fabricated, and installed as per the design 

document and operational program description. 

b. Capsules are designed, fabricated, and installed as per design documents and 

operational program description. 

c. Test specimens that are included in capsules conform to the surveillance capsule 

program. 

50054-02 INSPECTION REQUIREMENTS AND GUIDANCE 

02.01 General Inspection Guidance 

This inspection procedure will be implemented prior to the approval of fuel loading. The 

design document containing a level of detail sufficient to implement this inspection 

procedure (IP) regarding the surveillance capsule program required by 10 CFR 50, 

Appendix H will be reviewed by the NRC headquarters staff. Upon approval of the 

surveillance capsule program, the associated inspections will be performed by the regional 

inspectors. 

The RV surveillance capsule program inspection consists of three major areas: (1) CB 

design, (2) capsules design, and (3) test specimens. 

The design of the CBs and the means of attachment shall (1) preclude structural material 

degradation of the attachment welds, (2) avoid interference with inservice inspection 

required by Section XI of the American Society of Mechanical Engineers Boiler and 

Pressure Vessel Code (ASME Code), and (3) ensure the integrity of the capsule during the 

service life of the reactor vessel. 

The capsules are located typically at four azimuths at a common elevation in the core belt 

line region and may be attached to either the vessel wall, vessel cladding or the internals 

(e.g., the core barrel). A minimum capsule lead factor of 1 is used in determining the 

locations of the capsules. A lead factor is the ratio of the average neutron flux at the 

location of the specimens in a surveillance capsule to the average neutron flux at the 
Issue Date: 12/04/08 2 50054 

reactor pressure vessel inside surface at the peak fluence location. The sealed capsules 

are not attached directly to the vessel or internals but are in welded CBs. The capsules are 

mechanically retained by the CBs. 

02.02 Specific Requirements

a. Capsule Brackets

 The CBs itself are not ASME Code-designed products. The CBs may be welded to 

the vessel wall, vessel cladding or internals. If the CBs are attached to the vessel 

wall or to the vessel cladding, construction and inservice inspection of the 

attachments and attachment welds must be performed according to the 

requirements for permanent structural attachments to reactor vessels specified in 

Sections III and XI of the ASME Code in accordance with 10 CFR Part 50, 

Appendix H, III.B.2 (10 CFR 50, App H).

1. Design Specification - Verify by review of design documents: 

(a) that the CBs and attachment welds will not interfere with inservice 

inspection required by ASME Code Section XI by confirming that the 

design specification requires that at least 90 percent of the attachment 

weld is accessible for visual examination; 

(b) that the design provides for a minimum capsule lead factor of 1 based 

on the locations specified for the capsules (in essence CBs); 

(c) that the sealed capsules are not attached directly to the vessel, but are 

in welded CBs. Verify that the surveillance capsule holder locations 

specified are consistent with the facility=s design basis and 10 CFR 50, 

Appendix H requirements. This will be done by NRC headquarters 

staff. 

2. Fabrication - Verify by review of fabricated samples, design and material 

certification records:

(a) that the materials and as-built design of the bracket assembly conform 

with the requirements of the design specification; 

(b) that welding records conform with the specified welding procedure, 

welder qualifications, and welding materials; 

(c) that the fabrication of CBs and the attachment welds meet the 

requirements of the specification and or the ASME Code. 

If the brackets are attached to the vessel wall or vessel cladding, verify 

that additional nondestructive examinations are to be performed on the 

vessel base metal, stainless steel cladding or weld buildup pads during 

vessel manufacture in accordance with the ASME Code Section III. 

Review nondestructive examination documentation records to verify 

the NDE procedures and personnel were qualified in accordance with 

the Code. 
Issue Date: 12/04/08 3 50054 

3. Capsule Installation - Verify by independent measurement or observation, or 

by review of as-built records: 

(a) that the capsule bracket locations meets design drawings, specifically 

that the locations of the capsule brackets and capsule, typically at 

four azimuths at a common elevation in the core belt line region are 

correct; 

(b) that at least 90 percent of each attachment weld is accessible for 

visual ISI examination; 

(c) that the capsules have been loaded with neutron surveillance and 

vessel material samples as specified in the design specification. 

b. Capsule Design, Fabrication and Installation 

 Specimens must be maintained in an inert environment within a corrosion-resistant 

capsule to prevent deterioration of the surface of the specimens during radiation 

exposure. Capsule design requires the verification of the following: 

1. that capsule assembly conforms with the capsule program; 

2. that the specimens are in an inert environment; 

3. that the as-built capsules conform to the capsule design specifications 

(materials, welding etc.); 

4. that approved welding procedures, welder qualifications, and welding 

materials were used. 

c. Capsule Contents 

 The RV materials surveillance test specimens must meet the requirements of 

American Society for Testing and Materials (ASTM) Standard Practice E-185 and 

10 CFR Part 50, Appendix H. The test specimens for the program are selected to 

represent materials used in the reactor beltline region. The specimens contained 

in the capsules typically include Charpy V-notch impact, tensile, and compact 

tension specimens from the limiting beltline region. Each capsule also contains 

Charpy V-notch impact specimens of weld heat-affected-zone (HAZ) metal as well 

as dosimeters and thermal monitors to measure the integrated neutron flux and 

temperature in the individual test capsules. The thermal history or heat treatment 

given these specimens is similar to the thermal history of the reactor vessel 

material with the exception that the post weld heat treatment received by the 

specimens has been simulated. Specifically, verify that capsules include material 

samples as described in the NRC-approved surveillance program. 

 Verify by review of design construction and installation records that the contents of 

the capsules include (see note): 
Issue Date: 12/04/08 4 50054 

1. Charpy V-notch impact, tensile, and compact tension from the limiting core 

region; 

2. Charpy V-notch impact specimens of HAZ metal; 

3. Neutron dosimeters and temperature monitors as required by ASTM E185. 

 Note: actual contents of the capsule will vary depending on the nuclear 

steam supply system (NSSS) vendors. Specimens inside the capsule are 

stored in an inert environment and are separated using separators. 

50054-03 RESOURCE ESTIMATE 

This inspection procedure is estimated to take, on the average 16 to 32 hours for each unit 

prior to loading the fuel in the reactor vessel. 

Depending on availability, resident staff members may assist the regional ISI inspectors. 

50054-04 REFERENCES 

American Society for Testing and Materials (ASTM), ASTM E185, AStandard 

Recommended Practices for Surveillance Tests for Nuclear Reactor Vessels.@

American Society for Testing and Materials (ASTM), ASTM E185-82, AStandard Practice 

for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels.@

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 

Section III, NB 5000. 

ASME Boiler and Pressure Vessel Code Section XI, IWB 2500. 

U.S. Code of Federal Regulations, Title 10, Energy, Part 50, ADomestic Licensing of 

Production and Utilization Facilities.@

U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Appendix H, A Reactor 

Vessel Material Surveillance Program Requirements.@

U.S. Code of Federal Regulations, Title 10, Energy, Part 52, AEarly Site Permits; Standard 

Design Certifications; and Combined Licenses for Nuclear Power Plants.@ 

END 

ATTACHMENT: 

Revision History for IP 50054 
Issue Date: 12/04/08 Att1-1 

ATTACHMENT 1 

Revision History for IP 50054

Commitment Tracking Number 

Issue Date Description of Change Training 

Required 

Training Completion Date 

N/A 12/04/08 

CN 08-034 

Initial issue to support inspection of operation programs described in IMC 2504, Non-ITTAC Inspections 4 year review of CNs was performed and no commitments found. 

No N/A