U.S. NUCLEAR REGULATORY COMMISSION April 2011

Revision 4

REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable 

for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating specific problems 

or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. Regulatory guides are not 

substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in 

regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a 

permit or license by the Commission. 

This guide was issued after consideration of comments received from the public. 

Regulatory guides are issued in 10 broad divisionsC1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials 

Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 

9, Antitrust and Financial Review; and 10, General. 

Electronic copies of this guide and other recently issued guides are available through the NRC’s public Web site under the 

Regulatory Guides document collection of the NRC’s Electronic Reading Room at 

http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s Agencywide Documents Access and Management 

System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML110420119. The regulatory analysis 

may be found in ADAMS under Accession No. ML110420133. 

REGULATORY GUIDE 1.149 

(Draft was issued as DG-1248, dated May 2010) 

NUCLEAR POWER PLANT SIMULATION FACILITIES FOR 

USE IN OPERATOR TRAINING, LICENSE EXAMINATIONS, 

AND APPLICANT EXPERIENCE REQUIREMENTS 

A. INTRODUCTION 

This guide describes methods acceptable to the staff of the U.S. Nuclear Regulatory Commission 

(NRC) for complying with those portions of the Commission’s regulations associated with approval or 

acceptance of a nuclear power plant simulation facility for use in operator and senior operator training and 

license examination operating tests and for meeting applicant experience requirements. 

Title 10, of the Code of Federal Regulations, Part 55, “Operators’ Licenses” (10 CFR Part 55) 

(Ref. 1), defines the term “simulation facility” in 10 CFR 55.4, “Definitions,” as meaning one or more of 

the following components, alone or in combination, used for either the partial conduct of operating tests 

for operators, senior operators, and license applicants, or to establish on-the-job training and experience 

prerequisites for operator license eligibility: (1) a plant-referenced simulator, (2) a Commission-approved 

simulator under 10 CFR 55.46(b), or (3) another simulation device, including part-task and limited scope 

simulation devices, approved under 10 CFR 55.46(b). In particular, 10 CFR 55.46, “Simulation 

Facilities,” addresses the use of a simulation facility for the administration of the operating test and 

plant-referenced simulators to meet experience requirements for applicants for operator and senior 

operator licenses. In addition, 10 CFR 55.59, “Requalification,” addresses, in part, the use of a simulation 

facility to perform required control manipulations and plant evolutions not performed at the plant for 

on-the-job training of licensed operator and senior operators. 

This regulatory guide contains information collection requirements covered by 10 CFR Part 55 

that the Office of Management and Budget (OMB) approved under OMB control number 3150-0018. 
Rev. 4 of RG 1.149, Page 2 

The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information 

collection request or requirement unless the requesting document displays a currently valid OMB control 

number. The NRC has determined that this regulatory guide is not a major rule as designated by the 

Congressional Review Act and has verified this determination with OMB. 

B. DISCUSSION 

Background 

In March 1987, the Commission amended its regulations requiring all utilization facility licensees 

to have a simulation facility (either a “plant-referenced simulator” or an “other-than-a-plant-referenced 

simulator”) by May 26, 1991, for use in administering NRC operating tests and licensed operator 

requalification training (Volume 52, page 9460, of the Federal Register (52 FR 9460; March 25, 1987)) 

(Ref. 2). 

In October 2001, the NRC amended its regulations to permit facility licensee applicants for 

operator’s licenses to fulfill a portion of the required experience prerequisites by manipulating a 

plant-referenced simulator as an alternative to manipulating the controls of the actual nuclear power plant 

(66 FR 52667; October 17, 2001) (Ref. 3). The final rule became effective November 16, 2001. 

 Also in October 2001, the staff issued Revision 3 of Regulatory Guide 1.149, “Nuclear Power 

Plant Simulation Facilities for Use in Operator Training and License Examinations” (Ref. 4). This guide 

endorsed the industry’s previously adopted consensus standard, American National Standards 

Institute/American Nuclear Society (ANSI/ANS)-3.5-1998, “Nuclear Power Plant Simulators for Use in 

Operator Training and Examination,” dated April 15, 1998 (Ref. 5), as well as two historical editions, 

ANSI/ANS-3.5-1993, dated March 29, 1993 (Ref. 6), and ANSI/ANS-3.5-1985, dated October 25, 1985 

(Ref. 7), as methods acceptable to the NRC staff for implementing specific parts of the Commission’s 

regulations and techniques used by the staff in evaluating compliance. 

As a result of the regulatory experience gained since Revision 3 of Regulatory Guide 1.149, this 

new revision of the guide updates and clarifies the scope of the guideline to better serve simulation 

facility licensees and the regulatory community. The guide helps to ensure that simulation facilities used 

to meet the requirements of 10 CFR Part 55 are sufficient in both scope and fidelity for the regulatory 

purposes for which they are being used with respect to (1) operating tests, as described in 

10 CFR 55.45(a), (2) licensed operator requalification training requirements, as described in 

10 CFR 55.59, and (3) performance of control manipulations that affect reactivity to establish eligibility 

for an operator’s license, as described in 10 CFR 55.31(a)(5). 

Role of Nuclear Power Plant Simulation Facilities in Operator Licensing 

Facility licensees are responsible for ensuring that individuals who receive operator or senior 

operator licenses have the knowledge, skills, and abilities necessary to operate the nuclear facility safely 

and competently. Since 1991, the NRC and facility licensees have been using nuclear power plant 

simulation facilities to determine whether an applicant for an operator’s license has learned to operate a 

facility competently and safely, and, in the case of a senior operator, whether an applicant has learned to 

direct the licensed activities of licensed operators competently and safely. Currently, 72 full-scope 

plant-referenced simulators are in service for use in meeting the regulatory needs of approximately 

4,500 licensed operators manning 104 commercial nuclear power plants operating in the United States. 

When applicants are tested and evaluated on a plant-referenced simulator, major facility differences are 
Rev. 4 of RG 1.149, Page 3 

minimized between the testing and operating environments. As a result, NRC examiners are able to make 

pass-fail judgments with confidence. 

Currently, no facility licensees have proposed to use a simulation facility other than a 

plant-referenced simulator in the administration of an operating test. Facility licensees are required to 

request approval from the Commission should they propose to use other than a plant-referenced simulator 

in the operating test. Absent the use of plant-referenced simulators, operator licensing regulatory 

requirements would be much more difficult to meet since Commission-approved simulation facilities and 

Commission approval of the use of the actual plant would require the Commission to find that the 

simulation facility and its proposed use, or the proposed use of the plant, are suitable for the conduct of 

operating tests. 

The staff anticipates that additional nuclear power plant simulation facilities will be placed into 

service to meet future operator licensing needs with the advent of new nuclear power plants. This guide 

also applies to the use of new full-scope nuclear power plant simulation facilities when used to meet 

10 CFR Part 55 operator licensing requirements. 

Plant-Referenced Simulator Performance Testing 

The guidance in this topical area ensures a more uniform and consistent approach to performance 

testing of a plant-referenced simulator. The Commission’s regulations in 10 CFR 55.4 define the 

following three terms, which are very important to understanding the staff’s perspective on simulator 

performance testing: 

1. “Performance testing” means testing conducted to verify a simulation facility’s performance as 

compared to actual or predicted reference plant performance. 

2. “Plant-referenced simulator” means a simulator modeling the systems of the reference plant with 

which the operator interfaces in the control room, including operating consoles, and which 

permits use of the reference plant’s procedures. 

3. “Reference plant” means the specific nuclear power plant from which a simulation facility’s 

control room configuration, system control arrangement, and design data are derived. 

The simulator must meet specific regulatory requirements, as described in 10 CFR 55.46(c) and 

10 CFR 55.46(d), for the Commission to accept a simulation facility consisting solely of a 

plant-referenced simulator for conducting operating tests, as described in 10 CFR 55.45(a) and 

10 CFR 55.59(a)(2); for requalification training, as described in 10 CFR 55.59(c)(3); or for performing 

control manipulations that affect reactivity to establish eligibility for an operator’s license, as described in 

10 CFR 55.31(a)(5). Specifically, 10 CFR 55.46(c) prescribes the minimum scope and fidelity 

requirements for a plant-referenced simulator, while 10 CFR 55.46(d) prescribes the performance testing 

requirements necessary for continued assurance of simulator fidelity. 

The underlying purpose of the performance testing requirement is to ensure that plant-referenced 

simulators (when used to meet operator licensing requirements) demonstrate on a continuing basis 

(1) expected plant response to operator input and to normal, transient, and accident conditions to which 

the simulator has been designed to respond, and (2) sufficiency in scope and fidelity to allow conduct of 

the evolutions associated with operating test content and licensed operator requalification program 

on-the-job training, applicable to the design of the reference plant. Additionally, the Commission’s 

regulations in 10 CFR 55.46(c)(2) require that facility licensees that propose to use a plant-referenced 

simulator to meet the experience requirements in 10 CFR 55.31(a)(5) ensure that (1) the plant-referenced 
Rev. 4 of RG 1.149, Page 4 

simulator utilizes models relating to nuclear and thermal-hydraulic characteristics that replicate the most 

recent core load in the nuclear power reference plant for which a license is being sought, and 

(2) simulator fidelity has been demonstrated so that significant control manipulations are completed 

without procedural exceptions, simulator performance exceptions, or deviation from the approved training 

scenario sequence. 

ANSI/ANS-3.5-2009, “Nuclear Power Plant Simulators for Use in Operator Training and 

Examination” 

On September 4, 2009, ANSI approved ANSI/ANS-3.5-2009, “Nuclear Power Plant Simulators 

for Use in Operator Training and Examination” (Ref. 8), as an American National Standard. The ANS 

Standards Committee Working Group ANS-3.5 developed and approved this industry consensus standard. 

The 2009 version is the sixth issuance of the standard since its initial approval in 1979. The revised 

standard received substantial support from a diverse and dedicated group of professionals, representing 

many utilities and interested parties, experienced in the use of full-scope nuclear power plant simulators. 

The ANS-3.5 Working Group comprised a wide range of utility, independent and industry oversight 

organizations (including official representatives from the Institute of Nuclear Power Operations and the 

NRC) during the development of the revised standard. 

The revised standard continues to establish the functional requirements for full-scope nuclear 

power plant control room simulators for use in operator training and examination, as well as criteria for 

the scope of simulation, performance, and functional capabilities of simulators. In addition to enhanced 

readability, users of the revised standard will find improvements and clarifications in simulator 

scenario-based performance testing, new sections addressing simulator core performance testing and 

postevent simulator testing, and other important guidance required to ensure accurate simulation for use 

in operator training and examination. 

NEI 09-09, “Nuclear Power Plant-Referenced Simulator Scenario Based Testing 

Methodology” 

On December 11, 2007 (Ref. 9), the NRC and the Nuclear Energy Institute (NEI) Licensed 

Operator Focus Group agreed, in principle, on a methodology for performing, evaluating, and 

documenting simulator scenario-based testing (SBT) that facilitates implementation of a standardized 

approach to SBT mutually acceptable to both parties. 

On December 8, 2009, NEI provided for NRC review and endorsement its industry guidance 

document, NEI-09-09, Revision 1, “Nuclear Power Plant-Referenced Simulator Scenario Based Testing 

Methodology” (Ref. 10), which provides an equitable and consistent approach and methodology for the 

conduct and documentation of SBT, as described in Section 4.4.3.2, “Simulator Scenario-Based Testing,” 

of ANSI/ANS-3.5-2009. 

C. REGULATORY POSITION 

1. Use of Voluntary Consensus Standards 

The National Technology Transfer and Advancement Act of 1995 (Pub. L. 104-113) (Ref. 11) 

requires that Federal agencies use technical standards developed or adopted by voluntary consensus 

standard bodies unless the use of such a standard is inconsistent with applicable law or otherwise 

impractical. NRC representatives participated in the development of ANSI/ANS-3.5-2009 in support of 
Rev. 4 of RG 1.149, Page 5 

its mission and to encourage industry to develop a standard that the NRC can endorse and industry 

(e.g., simulation facility licensees) can voluntarily carry out. 

2. NRC Acceptance and Endorsement of ANSI/ANS-3.5-2009 

In general, the NRC accepts and endorses industry consensus standards through incorporation by 

reference in regulations and through reference in such documents as regulatory guides, NUREG reports, 

standard review plans, and technical specifications. The NRC recognizes that the designation of 

ANSI/ANS-3.5-2009 as an American National Standard attests that the principles of openness and due 

process have been followed in its approval and that a consensus of those directly and materially affected 

by the standard has been achieved. Therefore, the agency’s sponsoring office, the Office of Nuclear 

Reactor Regulation (NRR), through reference in this regulatory guide, accepts and endorses 

ANSI/ANS-3.5-2009 as described below. The clarifications outlined in the following paragraphs apply to 

the Commission’s endorsement of ANSI/ANS-3.5-2009. 

a. ANSI/ANS-3.5-2009 sets forth provisions acceptable to the NRC staff for (1) addressing 

minimum design, testing, performance, and configuration criteria for a full-scope plant-referenced 

simulator, (2) comparing a simulator to its reference plant, (3) upgrading a simulator to reflect changes to 

reference plant response or control room configuration, and (4) improving simulator fidelity. As such, 

ANSI/ANS-3.5-2009 provides methods acceptable to the NRC staff for a facility licensee to demonstrate 

that, through meeting the criteria of the standard, a plant-referenced simulator will be sufficiently 

complete and accurate to meet the requirements of 10 CFR 55.46. Although the scope statement of 

ANSI/ANS-3.5-2009 is limited to the use of full-scope nuclear power plant simulators in operator training 

and examination, the staff has concluded that simulators meeting this standard should also be satisfactory 

for meeting the applicant experience requirements described in 10 CFR 55.31(a)(5). 

b. In regard to Section 3.1.4, “Malfunctions,” 10 CFR 55.46(d)(1) allows simulation facility 

licensees to discard malfunction performance tests and test results after 4 years or until superseded by 

updated test results. 

Additionally, previous certification of completed simulator malfunction performance tests and 

results through Form NRC-474, “Simulation Facility Certification,” submittals is sufficient evidence that 

the required malfunction testing has been conducted at least once within the life of the simulator as 

referenced in NEI-09-09, Revision 1, Section 2, Recommendation Number 4. Through its endorsement of 

NEI-09-09, Revision 1, without exceptions, the staff concludes that the SBT methodology should provide 

sufficient assurance that ANS-3.5 required malfunctions remain suitable should they be used for the 

conduct of licensed operator requalification or initial operating test evolutions. 

c. In regard to Section 3.4.1, “Simulator Verification Testing,” and Section 3.4.2, “Simulator 

Validation Testing,” the NRC neither expects nor requires the standard’s quality assurance methodology 

(during software model development in a controlled configuration environment) to be included in the 

facility licensee’s quality assurance program, as described in Appendix B, “Quality Assurance Criteria for 

Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50, “Domestic Licensing of 

Production and Utilization Facilities” (Ref. 12). Appendix B does not apply to simulation facilities as 

defined in and used for meeting 10 CFR Part 55 requirements. 

d. In regard to Section 3.4.3.2, “Simulator Scenario-Based Testing,” simulation facility licensees 

should meet the requirements of the standard with respect to the following type of SBTs for inclusion as 

simulator performance tests: (1) NRC initial license examination (operating test) scenarios, (2) licensed 

operator requalification annual examination (operating test) simulator scenarios, and (3) scenarios used 

for performing applicant control manipulations that affect reactivity to establish eligibility for an 
Rev. 4 of RG 1.149, Page 6 

operator’s license. All other operator and senior operator training simulator scenarios (such as 

just-in-time training and routine plant system and equipment startup and shutdown training) are excluded 

from SBT for purposes of meeting the standard’s SBT requirements. 

e. In regard to Section 4.4.3.2, “Simulator Scenario-Based Testing,” simulation facility licensees 

should also adhere to the NEI standardized approach for the conduct, performance, and documentation of 

simulator SBT, as described in NEI 09-09, Revision 1. The NRC expects licensees to perform simulator 

performance testing described in Section 4.4.3.1 (“Simulator Operability Testing”), Section 4.4.3.3 

(“Simulator Reactor Core Performance Testing”), and Section 4.4.3.4 (“Post-Event Simulator Testing”) 

separately and independently from the testing described in Section 4.4.3.2. 

f. In regard to Section 4.4.3.3, “Simulator Reactor Core Performance Testing,” simulation facility 

licensees should meet the requirements of the standard with respect to real time during the conduct of 

core evolutions performed in accordance with reference unit procedures. The NRC expects a facility 

licensee’s plant-referenced simulator to use models relating to nuclear and thermal-hydraulic 

characteristics that replicate a core load in the nuclear power reference plant. If the plant-referenced 

simulator is used to meet NRC applicant experience requirements, as described in 10 CFR 55.31(a)(5), 

then the most recent core load (e.g., the current reference plant core load, or if the reference plant is in a 

refueling outage, the core load just previous to the outage) in the nuclear power reference plant for which 

a license is being sought must be utilized. 

g. In regard to Section 4.4.3.4, “Post-Event Simulator Testing,” simulation facility licensees should 

meet the requirements of the standard with respect to demonstrating that the plant-referenced simulator’s 

performance and response compares favorably to the reference plant’s performance and response without 

significant deviation from the sequence of events for the reference plant event. Simulation facility 

licensees are encouraged, but not required, to conduct post-event simulator testing within 120 days of the 

actual reference plant event.

3. NRC Acceptance and Endorsement of NEI-09-09, Revision 1 

 The NRC staff has reviewed NEI-09-09, Revision 1, and finds the implementation guidance an 

acceptable method for simulation facility licensees to demonstrate their compliance with the requirements 

of Sections 3.4.3.2 and 4.4.3.2 of ANSI/ANS-3.5-2009 regarding simulator SBT. Therefore, the NRC 

accepts and endorses NEI-09-09 as an acceptable method for an equitable and consistent approach and 

methodology for the conduct and documentation of SBT, as described in ANSI/ANS-3.5-2009. 

4. Acceptability of Licensee’s Simulation Facility 

Licensees that maintain simulation facilities certified under previous editions of ANSI/ANS-3.5 

(1998, 1993, and 1985) endorsed by the NRC are encouraged to, but are not required to, revise the 

software and testing documentation to maintain the simulation facility in accordance with 

ANSI/ANS-3.5-2009. The NRC expects that a simulation facility will be maintained in accordance with 

a single version of the standard, preferably ANSI/ANS-3.5-2009. 

5. Use of Simulation Facility for Multiple Plants 

a. If a simulation facility licensee desires to use its plant-referenced simulator to train and or 

examine operators and senior operators for more than one nuclear power plant (other than the reference 

plant), the licensee must be able to demonstrate to the NRC staff that the differences between the nuclear 

power plants are not so significant that they will result in negative training. This demonstration should 
Rev. 4 of RG 1.149, Page 7 

include an analysis and summary of the differences between each nuclear power plant, including the 

following: 

(1) facility design and systems relevant to control room personnel, 

(2) technical specifications, 

(3) procedures, primarily abnormal and emergency operating procedures, 

(4) control room design and instrument control location, and 

(5) operational characteristics. 

b. The NRC will administer operating tests only on a plant-referenced simulator that meets the 

Commission’s requirements, as described in 10 CFR 55.46. In addition, a licensee must request 

Commission approval if the licensee plans to administer the NRC operating test using other than a 

plant-referenced simulator or the actual plant. 

6. Use of Other Simulation Devices 

 If a simulation facility licensee desires to use other simulation devices, including part-task and 

limited scope simulation devices, approved under 10 CFR 55.46(b) to train and or examine operators and 

senior operators, the licensee must be able to demonstrate to the NRC staff that use of such devices will 

not result in negative training. The NRC staff recognizes that other simulation devices not approved 

under 10 CFR 55.46(b) are being used extensively to supplement operator and senior operator training in 

classroom settings or on personal computers or both. The NRC acknowledges the use of other simulation 

devices when simulation models have been derived directly from the facility licensee’s plant-referenced 

simulator. 

D. IMPLEMENTATION

The purpose of this section is to provide information on how applicants and licensees1

 may use 

this guide and information regarding the NRC’s plans for using this Regulatory Guide. In addition, it 

describes how the NRC staff has complied with the Backfit Rule, 10 CFR 50.109 and any applicable 

finality provisions in 10 CFR Part 52.

Applicant and Licensees’ Use 

Applicants and licensees may (i.e., voluntarily) use the information in this regulatory guide to 

develop applications for initial licenses, amendments to licenses, or other requests for NRC regulatory 

approval (e.g., exemptions). Licensees may use the information in this regulatory guide for actions which 

do not require prior NRC review and approval (e.g., changes to a facility design under 10 CFR 50.59 

which do not require prior NRC review and approval). Licensees may use the information in this 

Regulatory Guide or applicable parts to resolve regulatory or inspection issues (e.g., by committing to 

comply with provisions in the regulatory guide). 

Current licensees may continue to use the guidance that was found acceptable for complying with 

specific portions of the regulations as part of their license approval process, which may be a previous 

version of this Regulatory Guide. 

 

1

 In this section, “licensees” refers to licensees of nuclear power plants under 10 CFR Parts 50 and 52; and the term 

“applicants,” refers to applicants for licenses and permits for (or relating to) nuclear power plants under 10 CFR Parts 

50 and 52, and applicants for standard design approvals and standard design certifications under 10 CFR Part 52. 
Rev. 4 of RG 1.149, Page 8 

A licensee who believes that the NRC staff is inappropriately imposing this Regulatory Guide as 

part of a request for a license amendment or request for a change to a previously issued NRC regulatory 

approval may file a backfitting appeal with the NRC in accordance with applicable procedures. 

NRC Staff Use 

The NRC staff does not intend or approve any imposition or backfitting of the guidance in this 

Regulatory Guide. The staff does not expect any existing licensee to use or commit to using the guidance 

in this Regulatory Guide in the absence of a licensee-initiated change to its licensing basis. The NRC 

staff does not expect or plan to request licensees to voluntarily adopt this Regulatory Guide to resolve a 

generic regulatory issue. The NRC staff does not expect or plan to initiate NRC regulatory action which 

would require the use of this regulatory guide (e.g. issuance of an order requiring the use of the 

Regulatory Guide, requests for information under 10 CFR 50.54(f) as to whether a licensee intends to 

commit to use of this regulatory guide, generic communication, or promulgation of a rule requiring the 

use of this Regulatory Guide) without further back-fit consideration. 

During inspections of specific facilities, the staff may suggest or recommend that licensees 

consider various actions consistent with staff positions in this regulatory guide, as one acceptable means 

of meeting the underlying NRC regulatory requirement. Such suggestions and recommendations would 

not ordinarily be considered backfitting even if prior versions of this Regulatory Guide are part of the 

licensing basis of the facility with respect to the subject matter of the inspection. However, unless this 

regulatory guide is part of the licensing basis for a plant, the staff may not represent to the licensee that 

the licensee’s failure to comply with the positions in this Regulatory Guide constitutes a violation. 

If an existing licensee seeks a license amendment or change in an already approved area of NRC 

regulatory concern, the NRC staff’s consideration of the request involves a regulatory issue directly 

relevant to this revised regulatory guide, and the specific subject matter of the new or revised guidance is 

an essential consideration in the NRC staff’s determination of the acceptability of the licensee’s request, 

then the staff may (in the absence of a licensee proposal complying with the underlying NRC regulatory 

requirement) require the licensee to use this Regulatory Guide as a prerequisite for NRC approval. This is 

not considered backfitting as defined in 10 CFR 50.109(a)(1) or a violation of any of the issue finality 

provisions in 10 CFR Part 52. 

Conclusion 

This regulatory guide is not being imposed upon current licensees and may be voluntarily used by 

existing licensees. In addition, this Regulatory Guide is issued in conformance with all applicable 

internal NRC policies and procedures governing backfitting. Accordingly, the NRC’s staff issuance of 

this regulatory guide is not considered backfitting, as defined in 10 CFR 50.109(a)(1), nor is it deemed to 

be in conflict with any of the issue finality provisions in 10 CFR Part 52. 

 
Rev. 4 of RG 1.149, Page 9 

REFERENCES2

1. 10 CFR Part 55, “Operators’ Licenses,” U.S. Nuclear Regulatory Commission, Washington, DC. 

2. 52 FR 9460, “Operator’s Licenses and Conforming Amendments,” Final Rule, Federal Register, 

Volume 52, Number 57, p. 9460, Washington, DC, March 25, 1987. 

3. 66 FR 52667, “Operator License Eligibility and Use of Simulation Facilities in Operator 

Licensing,” Final Rule, Federal Register, Volume 66, Number 201, p. 52667, Washington, DC, 

October 17, 2001. 

4. Regulatory Guide 1.149, “Nuclear Power Plant Simulation Facilities for Use in Operator Training 

and License Examinations,” Revision 3, U.S. Nuclear Regulatory Commission, Washington, DC, 

October 2001. 

5. ANSI/ANS-3.5-1998, “Nuclear Power Plant Simulators for Use in Operator Training and 

Examination,” American Nuclear Society, La Grange Park, IL, April 15, 1998. 

6. ANSI/ANS-3.5-1993, “Nuclear Power Plant Simulators for Use in Operator Training and 

Examination,” American Nuclear Society, La Grange Park, IL, March 29, 1993. 

7. ANSI/ANS-3.5-1985, “Nuclear Power Plant Simulators for Use in Operator Training,” American 

Nuclear Society, La Grange Park, IL, October 25, 1985. 

8. ANSI/ANS-3.5-2009, “Nuclear Power Plant Simulators for Use in Operator Training and 

Examination,” American Nuclear Society, La Grange Park, IL, September 4, 2009.3

9. Memo from Nancy L. Salgado, Chief, Operator Licensing and Human Performance Branch, 

Division of Inspection and Regional Support (DIRS), Office of Nuclear Reactor Regulation 

(NRR), to Frederick D. Brown, Director, DIRS, NRR, re: Summary of December 11, 2007, 

Meeting with Industry Focus Group on Operator Licensing Issues, January 3, 2008. 

(Agencywide Documents Access and Management System (ADAMS) Accession 

No. ML073511714) 

10. Letter to the NRC from John C. Butler, Director, Operations Support, Nuclear Generation 

Division, NEI, to John McHale, Chief, Operator Licensing and Training Branch, DIRS, NRR, re: 

NEI 09-09, “Nuclear Power Plant-Referenced Simulator Scenario Based Testing Methodology,” 

Revision 1, December 8, 2009. (ADAMS Accession Nos. ML093521654 (cover letter) and 

ML093521659 (associated attachment)) 

11. The National Technology Transfer and Advancement Act of 1995, Pub. L. 104-113. 

 

2

 All publicly available NRC documents are available electronically through the Electronic Reading Room on the NRC’s 

public Web site at http://www.nrc.gov/reading rm/doc collections/cfr/. The documents can also be viewed on-line for 

free or printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the 

mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301) 415 

3548; and e mail pdr.resource@nrc.gov. 

3

 Copies of American Nuclear Society (ANS) standards may be purchased from the ANS Web site 

(http://www.new.ans.org/store/); or by writing to: American Nuclear Society, 555 North Kensington Avenue, La 

Grange Park, Illinois 60526, U.S.A., Telephone 800-323-3044. 
Rev. 4 of RG 1.149, Page 10 

12. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” U.S. Nuclear 

Regulatory Commission, Washington, DC. 

13. 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” U.S. 

Nuclear Regulatory Commission, Washington, DC.