NRC seeks trainers for future inspectors, USA (Deadline: 27 May 2009)

15 May 2009

The U.S. Nuclear Regulatory Commission (NRC), Office of Human Resources/Technical Training Center is conducting a market survey and analysis to determine the range of available contractors that exist and to assess their capabilities to perform the work areas described below. All interested parties must ensure that there are no Conflict of Interest (COI) issues.

Contact:

Monique B. Williams,

Senior Contracts Specialist

monique.williams@nrc.gov

Phone: 301-492-3640

Fax: 301-492-3437

Summary of Requirement:

As part of the effort to train qualified inspectors in anticipation for the licensing of new reactors, the NRC’s Office of New Reactors is seeking sources that are interested in developing and conducting a two-week technical course in Mechanical Codes and Standards. This course will consist of the following components:

Requirements of 10 CFR 50, Appendix A and 10 CFR 50, Appendix B:

Review in detail the criteria of 10 CFR 50, Appendix A as it pertains to construction and manufacturing related activities associated with Mechanical SSC(s).

Provide a general overview of 10 CFR 50, Appendix B and state how its criterion relate to construction and manufacturing activities associated with Mechanical SSC(s).

ASME NQA-1-1994 and more recently endorsed versions, as applicable:

General overview of the Basic Requirements and Supplements relevant to nuclear power plant and fuel facility construction and operational programs with an emphasis on Mechanical SSC(s).

Overview of 10 CFR 50.34 in that NQA-1-1994 provides guidance on how to implement the requirements of 10 CFR Part 50, Appendix B.

NRC Standard Review Plan for Mechanical Systems, Structures and Components:

NUREG 0800 Chapters:

3.0 - Design of Structures, Components, Equipment, and Systems;

4.0 - Reactor;

5.0 - Reactor Coolant System and Connected Systems;

6.0 - Engineered Safety Features;

9.0 - Auxiliary Systems;

10.0 - Steam and Power Conversion System

(as it relates to safety-related systems that utilize these systems for safety and/or design purposes - e.g., AFW, RCIC, HPSI/HCIC, LPSI, etc.);

14.0 - Initial Test Program; and

17.0 - Quality Assurance

General overview of the SRP and selected examples of review criteria:

• Seismic Classifications and Qualifications;

• External Environmental Loadings;

• SSCs Testing and Analysis;

• Materials Testing and Analysis;

• Environmental Qualification Classifications;

• Quality and Code Classifications of SSCs;

• Internally and Externally Generated Missiles;

• Design Requirements for SSCs;

• Overpressure Protection;

• Reactor Coolant Pressure Boundary Materials and SSCs;

• Pressure-Temperature Limits and Pressurized Thermal Shock;

• Applicable Code Cases;

• Materials used for Construction & Fabrication of Reactor Vessels; NSSS, ECCS and other Safety-Related SSCs;

• Protective Coatings;

• Design, Use and Functions of HVAC SSCs;

• Isolation Functions and Requirements (i.e. - Main Steam, Feedwater, Containment, etc.);

• Chemistry Control, Degradation and Failures;

• Crane Functions, Loading, Ratings & Design;

• Piping Supports Design and Testing;

• Quality Assurance (QA) and Quality Control (QC) Program and Implementation – overview only.

Demonstrate an understanding of the basic installation and testing requirements for fluid process systems and physical parameters, such as: temperature, flow, pressure, level & chemistry.

Discuss the basic installation and testing requirements specific to mechanical system components.

Compare and contrast the installation processes and testing criteria for the different types of mechanical components and systems.

Industry and Manufacturing Codes & Standards directly related to application, implementation and installation of Mechanical SSC(s) important to safety:

• Emergency Diesel Generators (EDGs) and other types of mechanical equipment and systems used for Emergency Back-Up Power (i.e. - gas turbines, hydro turbines, etc.);

• Emergency Core Cooling Systems (ECCS);

• Pumps;

• Valves;

• Piping;

• Welding – overview only;

• Non-Destructive Examination (NDE) – overview only;

• Pressure Vessels (incl. Active & Passive Tanks);

• Heat Exchangers;

• Motors;

• Alternate Mechanical Drive devices (i.e.- steam & gas turbines, diesels, variable speed drives, etc.);

• Gearboxes;

• Actuators (electric, pneumatic, hydraulic, etc.);

• Fans, Blowers and Compressors;

• HVAC;

• Dampers and Louvers;

• Bolted Connections (incl. bolting & fasteners);

• Hangers, Supports and Snubbers;

• Bellows and Expansion Joints;

• Cable Trays and Supports;

• Piping and Instrument Racks and/or Stands;

• Anchorages of components to walls, floors, structural members etc.;

• Personnel and Equipment Hatches/Air-Locks;

• Waterproof/ Watertight Doors;

Provide a general overview of Industry Codes & Standards applicable to Mechanical SSCs important to safety to include, but not limited to:

• ASME Section III – RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS;

• ASME Section III - Subsection NCA General Requirements for Division 1 and Division 2 RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS;

• ASME Section III Division 1 – RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS

o Subsection NB Class 1 Components,

o Subsection NC Class 2 Components,

o Subsection ND Class 3 Components,

o Subsection NE Class MC Components,

o Subsection NF Supports,

o Subsection NG Core Support Structures,

o Subsection NH Class 1 Components in Elevated Temperature Service;

• ASME Section III Division 1 – Appendices RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS;

• ASME NQA-1, Quality Assurance Requirements for Nuclear Facility Applications – overview only;

• ASME Code for Operation and Maintenance (OM) of Nuclear Power Plants (including an overview of some applicable Code Cases);

• ASME Section II – Materials

o Part A - Ferrous Material Specifications,

o Part B - Nonferrous Material Specifications,

o Part C - Specifications for Welding Rods, Electrodes, and Filler Metals,

o Part D - Properties;

• ASME Section V – Nondestructive Examination – overview only;

• ASME Section VIII – RULES FOR CONSTRUCTION OF PRESSURE VESSELS;

• ASME Section IX – Qualification Standard for Welding and Brazing Procedures, Welders, Brazers, and Welding and Brazing Operators – overview only;

• ASME AG-1, Code on Nuclear Air and Gas Treatment;

• ANSI/ASME B16.5, Pipe Flanges and Flanged Fittings NPS 1/2” Through NPS 24”;

• ANSI/ASME B16.11, Forged Fittings, Socket-Welding and Threaded;

• ANSI/ASME B16.34, Valves - Flanged, Threaded, and Welding End;

• ANSI/ASME B16.47, Large Diameter Steel Flanges NPS 26” Through NPS 60”;

• ANSI/ASME (USAS) B31.1, Power Piping - overview only;

• ANSI/ASME (USAS) B31.3, Process Piping - overview only;

• ANSI/ANS 51.1, Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants;

• ANSI/ANS 52.1, Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants;

Provide an overview summary of the various Codes & Standards listed in “Attachment 1” and how they relate to construction and manufacturing activities associated with Mechanical SSC(s).

Upon completion of this section, the student/ attendee should be able to successfully:

• Summarize the Code requirements and standards applicable to this functional area of Mechanical SSCs;

• Understand and describe piping system design fundamentals and fabrication requirements;

• Describe pipe support systems and their design function;

• Describe the function, installation and operational testing requirements for centrifugal and positive displacement pumps;

• Understand the potential causes of water hammer and pressure spiking;

• Summarize the design, installation and operational requirements of pressure regulating, temperature control, and flow control valves in a process system;

• Explain the basic design, installation and operational testing Code and QA/QC requirements for a heat exchanger used in a process system;

• Explain the basic design, installation and operational testing Code and QA/QC requirements of a typical heating, ventilation and air conditioning (HVAC) system, including supporting chilled water systems and isolation dampers for fire protection and radiation control;

• Determine whether mechanical component installation and related QA/QC activities are being performed in accordance with Design Specifications, and Code or Regulatory requirements.

NRC Regulatory Guides (RG) associated with Mechanical Codes & Standards, and Mechanical SSCs:

Review a few current Regulatory Guides associated with Mechanical Codes & Standards to provide the student with an overall understanding and purpose of Regulatory Guides as they relate to construction and manufacturing activities associated with Mechanical SSC(s):

• RG 1.43, Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components;

• RG 1.73, Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants;

• RG 1.87, Guidance for Construction of Class 1 Components in Elevated-Temperature Reactors.

Requirements for Seismic and Environmental Qualification of Mechanical SSC(s)

Overview of guidance provided in Regulatory Guides to include, but not limited to:

• RG 1.29, Seismic Design Classification;

• RG 1.40, Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants;

• RG 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants;

• RG 1.61, Damping Values for Seismic Design of Nuclear Power Plants;

• RG 1.73, Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants;

• RG 1.92, Combining Modal Responses and Spatial Components in Seismic Response Analysis; and

• RG 1.100, Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants.

• ASME QME-1, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants;

• ASCE 4, Seismic Analysis of Safety-Related Nuclear Structures and Commentary;

• ANSI/ANS 2.26, Categorization of Nuclear Facility SSCs for Seismic Design; and

• AISC 341, Seismic Provisions for Structural Steel Buildings.

Upon successful completion of this section, the student/attendee should be able to successfully summarize Equipment Qualification requirements (for both mild and harsh environments), age and service related degradation, explain types of testing and/or similarity analyses, discuss requirements for an acceptable test report, and how test and/or analyzed conditions must replicate as-built installations, seismic requirements and classifications.

Case studies of Mechanical related issues:

Focus on construction programs of nuclear power plants and fuel facilities with emphasis on the activities associated with Mechanical SSC(s).

Overview of other internationally and industry recognized Mechanical standards and guidance.

General overview of Industry, IAEA or other internationally recognized Safety Standards or Codes related to Mechanical SSC(s) to include, but not limited to:

• ISO 389, Shielding for Nuclear Plants. Erection and Testing;

• ISO 921, Nuclear Energy Glossary;

• ISO 6258, Nuclear Power Plants. Design Against Seismic Hazards;

• ISO 899-1, Nuclear Plants. Supports, Attachments and Anchors for Piping. Testing;

• ISO 899-2, Nuclear Plants. Supports, Attachments and Anchors for Piping. Certification and Documentation;

• ISO 2818, Nuclear Plants. Supports, Attachments and Anchors for Piping. Supports;

• ISO 3167, Nuclear Plants. Supports, Attachments and Anchors for Piping. Anchors;

• ISO 10555, Nuclear Plants. Supports, Attachments and Anchors for Piping. Design;

• ISO 11380, Nuclear Plants. Supports, Attachments and Anchors for Piping. Nomenclature and Definitions;

• ISO 5893, Nuclear Power Plants. Power Reactors. Criteria for Protection Systems;

• ISO 8856, Nuclear Facilities. Criteria, Requirements and Recommendations for a Quality Assurance Program;

• ISO 9563, Protective Coatings in Laboratories and Nuclear Plants. Characteristics and Classification System;

• ISO 11985, Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Structures and Components. Determination of Resistance under LOCA conditions.

MECHANICAL CODES AND STANDARDS

ATTACHMENT 1

1) ASME PTC 32.1, Nuclear Steam Supply Systems.

2) ASME NOG-1, Rules for Construction of Overhead and Gantry Cranes.

3) ASME Code Case N-253-12, Construction of Class 2 or Class 3 Components for Elevated Temperature Service Section III, Division 1.

4) ASME Code Case N-307-3, Ultrasonic Examination of Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1 Section XI, Division 1.

5) ANSI/ASME N278.1, Self-Operated and Power-Operated Safety-Related Valves Functional Specification Standard.

6) ANSI/ANS 56.2, Containment Isolation Provisions for Fluid Systems After a LOCA.

7) ANSI/ANS 56.3, Overpressure Protection of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary.

8) ANSI/ANS 56.4, Pressure and Temperature Transient Analysis for Light Water Reactor Containments.

9) ASTM E-748, Standard Practices for Thermal Neutron Radiography of Materials.

10) ANSI/ISA-67.02.01, Nuclear Safety-Related Instrument Sensing Line Piping and Tubing Standard for Use in Nuclear Power Plants.

PLEASE COMPLETE THE MARKET RESEARCH QUESTIONS BELOW:

For information on NRC COI regulations, visit NRC Acquisition Regulation Subpart 2009.5 (www.nrc.gov/who-we-are/contracting/48cfr-ch20.html). All interested parties, including all categories of small businesses (small businesses, small disadvantaged businesses, 8(a) firms, women-owned small businesses, service-disabled veteran-owned small businesses, and HUBZone small businesses) are invited to submit a response to the market research questions set forth below.

The Page Limit for Questions 1 to 7 must be no more than three pages in length.

1. How long has your business been in operation?

2. What type of business is your company (i.e. 8(a), large, etc.)?

3. Has your company worked for any of the potential applicants in the past year? (Currently the potential applicants are Constellation, Dominion, Duke, Entergy, Exelon, Progress and Southern)?

4. Describe the types of work and technical disciplines your company offers.

5. List any companies or government agencies your company plans to perform work related to New Reactors in the next two years?

6. Has your company previously faced organizational conflict of interest issues with NRC? How were they resolved?

7. Describe any other information your company deems relevant to supporting New Reactors training in Mechanical Codes and Standards as noted in the above listed training components.

Any organization responding to this SOURCES SOUGHT NOTICE should ensure that its response is complete and sufficiently detailed to allow the government to determine the organization’s qualifications to perform this work. A government employee will evaluate all submissions for responsiveness to this announcement. This is not a Request for Proposals and this in now way commits the Government to award a contract. The Government does not intend to award a contract based solely on this submission to this Sources Sought Notice nor does it intend to pay for any costs incurred in response to this announcement. The submission of additional materials such as glossy brochures or videos is discouraged.


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