Issue Date: 10/16/12 - 1 - 41502

NRC INSPECTION MANUAL COLP

INSPECTION PROCEDURE 41502

NUCLEAR POWER PLANT SIMULATION FACILITIES

PROGRAM APPLICABILITY: 2504

41502-01 INSPECTION OBJECTIVES

01.01 To verify the plant-referenced simulator is designed and implemented so that it is 

sufficient in scope and fidelity to be suitable for conduct of the evolutions listed in 10 

CFR 55.45(a)(1) through (13), and 55.59(c)(3)(i)(A) through (AA), as applicable to the 

design of the reference plant and allows for the completion of control manipulations for 

operator license applicants.

01.02 To verify continued assurance of simulator fidelity is maintained by the facility licensee 

per 10 CFR 55.46 (d).

01.03 To verify the suitability of the plant-referenced simulator for use, if applicable, by the 

facility licensee to meet the control manipulation requirements in 10 CFR 55.31(a)(5), 

and 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 to verify that simulator fidelity has been demonstrated and 

met per 10 CFR 55.46(c)(2)(i) and (ii). 

01.04 To verify that a simulator facility for a “new reactor” has sufficient fidelity to be 

designated a „plant reference simulator‟ and conforms to objectives 1.01 through 1.03

above. (A „new reactor‟ for the purposes of this procedure means as a reactor plant 

under construction with no core operating history.)

41502-02 INSPECTION REQUIREMENTS AND INSPECTION GUIDANCE

02.01 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-plantreferenced-simulator”) by May 26, 1991, for use in administering NRC operating tests and 

licensed operator requalification training (52 FR 9460; March 25, 1987).

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). 
Issue Date: 10/16/12 - 2 - 41502

In March 2011, the staff issued Revision 4 of Regulatory Guide (RG) 1.149, “Nuclear Power 

Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant 

Experience Requirements.” The RG describes methods acceptable to the staff for complying 

with those portions of the Commission‟s regulations [10 CFR 55.46] 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. The RG also explains that NRC accepts and endorses industry consensus 

standards such as ANSI/ANS-3.5-2009, “Nuclear Power Plant Simulators for Use in Operator 

Training and Examination.” 

Facility licensees are expected to adhere to a single version of ANS-3.5, Nuclear Power Plant 

Simulators for Use in Operator Training [and Examination], for simulator technical requirements 

to ensure the plant-referenced simulator meet the scope and fidelity requirements of 10 CFR 

55.46. All licensees will have committed to a version of ANSI/ANS-3.5 as a way of ensuring the 

plant-referenced simulator meets the requirements of 10 CFR Part 55. This commitment is 

usually contained in the licensee‟s plant licensing basis. 

In preparation for the simulation facility inspection, inspectors should review the specific 

ANSI/ANS 3.5 version [and associated RG] to which the licensee is committed. These 

documents should be used in conjunction with the specific guidance and inspection 

requirements contained in this inspection procedure (IP).

This IP can be used for new or operating reactors. All or part of this IP may be used as 

necessary to supplement IP 71111.11, Licensed Operator Requalification Program. This IP is 

to be performed by a qualified Operator Licensing Examiner.

02.02 General Inspection Requirements.

a. Goals

1. The intent of these inspection activities is to verify conformance with the

simulator requirements specified in 10 CFR 55.46 and to assess the adequacy of 

the facility licensee's simulation facility for use in operator training, license

examinations, and applicant experience requirements as described in 10 CFR 

55.31(a)(5), if applicable, (if used for applicant experience requirements). 

2. Additionally, these inspection activities assess the effectiveness of the facility 

licensee's process for continued assurance of simulator fidelity with regard to 

performance testing, and identifying, reporting, correcting, and resolving 

simulator hardware and modeling discrepancies via a simulator corrective action 

program.

b. Inspection Requirements

1. Verify simulator performance testing as defined by the Commission [meaning

simulator testing conducted to verify performance as compared to actual or 

predicted reference plant performance] is accomplishing the following objectives:
Issue Date: 10/16/12 - 3 - 41502

(a) 10 CFR 55.46(d) requires licensees conduct simulator performance testing 

throughout the life of the simulation facility in a manner sufficient to ensure 

simulator fidelity. The testing demonstrates the plant-referenced simulator 

utilizes models relating to nuclear and thermal-hydraulic characteristics that 

replicate the most recent core load (the most recent core load is only 

required if the plant referenced simulator is used to meet control 

manipulation requirements in 10 CFR 55.31(a)(5)); 

(b) The testing demonstrates the plant-referenced simulator performance 

mimics the reference plant performance (actual or expected),

(c) All hardware discrepancies and discrepancies identified from scenario 

validation and performance testing are documented in the simulator 

corrective action process,

(d) Uncorrected performance test failures are available for NRC review,

(e) Performance test results are retained for four years after the completion of 

each performance test or until superseded by updated test results.

2. If the licensee is committed to scenario-based testing (SBT), i.e., ANSI/ANS 3.5,

1998 or 2009, review licensee administered scenario-based testing, see 

Attachment 2, “Plant-referenced Simulator Scenario Based Testing Methodology 

Checklist”. The SBT should confirm parameters/alarms/automatic actions to be 

evaluated are identified, that the SBT is electronically capturing that data and 

evaluating the data against reference plant performance, and attesting that 

simulator performance was satisfactory or documenting discrepancies. 

3. Review simulator physical fidelity (i.e., the degree of similarity between the 

simulator and the reference plant control room, such as physical location of 

panels, equipment, instruments, controls, labels, and related form and function), 

especially regarding recent modifications implemented in the control room. 

Simulation scope and fidelity must be sufficient to allow conduct of evolutions in 

10 CFR 55.45 and 55.59.

For operating reactors, if any simulator fidelity inspection issue impacts licensed 

operator requalification, refer to Inspection Manual Chapter (IMC) 0609, 

Appendix I, and “Operator Requalification Human Performance SDP” for 

determining the significance of the issue.

For new reactors, the physical fidelity is confirmed by reviewing the Inspection, 

Test, Analysis and Acceptance Criteria (ITAAC) as discussed in 02.02.b.6 below

and by performing Attachment 1, "Checklist for Evaluating Plant-referenced 

Simulator Operating under 10 CFR 55.46(c) and (d)," of this inspection 

procedure.

4. Determine the suitability of the licensee's simulation facility for use in operator 

training, license examinations as described in 10 CFR 55.46, and applicant 

experience requirements as described in 10 CFR 55.31(a)(5), if applicable (if 

used for experience requirements). This assessment is to be carried out on a 
Issue Date: 10/16/12 - 4 - 41502

sampling basis and is not intended to be an exhaustive inspection of the 

licensee's simulation facility.

(a) Refer to 10 CFR 55.46, "Simulation facility," for specific requirements 

regarding plant-referenced simulators. Use Attachment 1 of this inspection 

procedure, "Checklist for Evaluating Plant-referenced Simulator Operating 

Under 10 CFR 55.46(c) and (d)," to determine, on a sampling basis, if the 

plant-referenced simulator is acceptable for use in operator examinations, 

and to satisfy experience requirements. Assess any negative responses to 

the questions and if necessary, seek NRR/NRO program office guidance on 

the issue. 

(b) Verify that the facility licensee has a configuration management control 

process in place to maintain the fidelity of the plant-referenced simulator.

(c) Assess simulator discrepancies and the safety impact of any negative training 

caused by these discrepancies.

(d) If the simulator was used for any license candidate(s) to meet the control 

manipulation requirements in 10 CFR 55.31(a)(5), the determination that the 

simulator was deemed suitable for the control manipulations per the criteria in 

10 CFR 55.46(c)(2)(i) and (ii) should be documented in the examination 

report. 

(e) New reactor inspections should evaluate the areas listed above as well as 

verify that discrepancies in the Issue Resolution Verification portion of the 

ITAAC are assessed per the configuration management control process and 

entered in the licensee‟s simulator corrective action program. The results 

from verification and integrated validation activities performed in accordance 

with the Design Certification and documented is the Licensee‟s ITAAC 

closure letter(s) may be cited as the bases for satisfactorily addressing 

applicable 10 CFR 55.46 requirements. 

5. Review open (uncorrected) and also sample closed simulator discrepancy 

reports, including simulator modeling and hardware discrepancies and 

discrepancies identified from scenario validation and performance testing, to 

assess the effectiveness of the licensee's process for: problem identification and 

prioritization, reporting, evaluation, schedule for implementing timely corrective 

actions, and corrective actions (where simulator discrepancies could result in 

negative training, corrective actions should include training on actual plant 

behavior). Verify that the licensee adequately captures simulator problems and 

that corrective actions are performed, tracked, trended and completed in a timely 

fashion commensurate with the safety significance of the item. Implicit in this 

review is confirmation that the corrective actions taken have adequately 

addressed the hardware/software issue and did not introduce new errors into the 

modeling. 

6. For New Reactors Only - In addition to 2.02.b.1 through 5 above, verify the 

simulation facility is a plant reference simulator suitable for operator licensing 
Issue Date: 10/16/12 - 5 - 41502

examinations and the control manipulation requirements in 10 CFR 55.31(a)(5), if 

applicable, by performing the following: 

(a) If this is the initial simulator inspection for the facility, verify that the ITAAC 

has been completed through the Integrated System Validation (ISV), if not 

contact the NRO Program Office (some portions may be able to be 

performed in parallel as determined by the program office.) 

(b) Confirm physical fidelity by performing Attachment 1, “Checklist for 

Evaluating Plant-referenced Simulator Operating under 10 CFR 55.45(c) 

and (d),” of this inspection procedure.

(c) Verify that the facility licensee has a configuration management control 

process in place to maintain the fidelity of the plant-referenced simulator. 

Assess simulator discrepancies and the safety impact of any negative 

training caused by these discrepancies. Verify simulator discrepancies are 

assessed per the configuration management control process and entered 

into the licensee‟s simulator corrective action program

(d) This simulator inspection shall be performed prior to conduct of each 

operator licensing operating examination to verify the simulator facility is a 

plant-referenced simulator suitable for operator licensing examinations and 

the control manipulation requirements of 10 CFR 55.31(a)(5).

02.03 Sample Selection.

a. Obtain a copy of the simulator management and configuration control procedures –

i.e., the procedure that governs simulator discrepancies and performance testing. 

Discrepancies should be prioritized, corrected and resolved in accordance with the 

management and configuration control procedure.

1. Request a list of all open simulator discrepancies– Review for relevancy to 10 

CFR 55.31, 55.45 and 55.59 operator actions.

2. Request a list of closed discrepancy reports for the last 12 months and review 

for the same criteria as a.1 above.

3. Evaluate summary list of uncorrected simulator discrepancies and list of 

corrected discrepancies over the last twelve months. Specifically evaluate 

discrepancies which directly impact operator immediate actions, abnormal 

and/or emergency operating procedural actions, and/or plant automatic actions 

which contributed to unsatisfactory simulator test performance/test results

failures. 

b. Request a list of simulator performance tests. Select simulator performance tests 

(and associated test results) in each of the following categories: 

Note: ANSI/ANS-3.5-2009 standard is used in the referenced sections below. If the 

facility uses an earlier standard then the section number referenced may vary.
Issue Date: 10/16/12 - 6 - 41502

1. Steady State/Transient tests - Evaluate at least one simulator steady-state 

performance test; and two simulator transient performance tests (such as 

reactor trip from >50% power and loss of all core flow). Sample size (1/2), 

ANSI/ANS reference sections 4.1.3.1, 4.4.3.1

2. Normal evolutions – Evaluate at least one simulator normal evolution test. 

Sample size (1), ANSI/ANS reference section 4.1.3.2.

3. Malfunction tests – Review at least five malfunction tests. This review should 

determine the malfunction cause if not apparent. At least three should relate to 

nuclear or thermal-hydraulic operating characteristics and two should relate to 

extensive logic/interlock performance. (Suggestions include loss of feed, main 

turbine trip, loss of off-site power and main steam line malfunctions.) Note: If 

scenario based testing is used, the malfunction tests are covered in the SBT. 

Sample size (5), ANSI/ANS reference section 4.1.4.

4. Simulator scenario-based testing, if applicable - Evaluate at least one (two for 

new reactors if no requalification scenarios are available) NRC initial license 

examination scenario(s); evaluate at least one licensed operator requalification 

annual examination scenario (may be N/A for new reactors); and evaluate at 

least one simulator scenario used for applicant reactivity control manipulation 

experience, if applicable. Sample size (1/2 in each area), ANSI/ANS reference 

section 4.4.3.2.

c. Simulator reactor core performance testing - Evaluate at least two simulator reactor 

core performance test(s) (if licensee‟s core performance testing is all contained in 

one procedure then evaluate two segments) related to nuclear and thermalhydraulic performance. Examples of items to review include heat balance, 

determination of reactivity coefficients, 1/M plots, and control rod worth using 

permanently installed instrumentation. New reactors may be evaluated against 

predicted values. Sample size (2), ANSI/ANS reference section 4.4.3.3.

d. Simulator post-event testing – Was conducted when a reference unit event 

generates relevant data for evaluating simulator performance. If multiple events 

have occurred, select at least one. Sample size (1), ANSI/ANS reference section 

4.4.3.4.

41502-03 INSPECTION GUIDANCE 

03.01 Conduct of Performance Testing.

Verify simulator performance testing has been conducted in a manner sufficient that 

simulator fidelity has been demonstrated so that significant control manipulations are 

completed without procedural exceptions, simulator performance exceptions, or 

deviations from the approved training scenario sequence. Refer to the specific 

ANSI/ANS 3.5 revision committed to by the licensee (this information is to be provided 

by the licensee).
Issue Date: 10/16/12 - 7 - 41502

a. Evaluate simulator operability testing. Test results should meet acceptance 

criteria and confirm any discrepancies are processed in the licensee‟s simulator 

corrective action program. (See 2.03.b.1 for sample recommendations) 

1. Confirm simulator operability testing has been conducted once per 

reference unit fuel cycle by testing: (New reactors may be evaluated using 

predicted values). 

(a) Simulator steady-state performance.

(b) Verify the simulator has been operated from cold shutdown to rated 

full power and back (credit may be taken for training scenarios 

provided the evolutions are performed with the reference unit 

procedures and are evaluated and documented). 

(c) Simulator transient performance for a benchmark set of transients.

b. Evaluate malfunction tests. Verify malfunction testing has been conducted in a 

manner sufficient that simulator fidelity has been demonstrated so that significant 

control manipulations are completed without procedural exceptions, simulator 

performance exceptions, or deviations. Test results should meet acceptance 

criteria and confirm any DRs are processed in the licensee‟s simulator corrective 

action program. Sample per 2.03.b.3.

c. Evaluate simulator scenario-based testing, if applicable to licensee. Attachment 

2, Plant-Referenced Simulator Scenario Based Testing Methodology Checklist, 

has the following attributes: (Reg. Guide 1.149 endorses NEI 09-09, Rev. 1). 

Sample per 2.03.b.4.

1. Review each sampled SBT for attributes in 03.01.c.2 through 7 below and 

verifies those SBT attributes are documented in each SBT. 

2. Confirm the simulator produced the expected reference unit response 

without significant performance discrepancies, or deviations from the 

approved scenario sequence. 

3. Confirm the simulator allows the use of reference unit procedures without 

exception.

4. Observable changes in simulated parameters correspond in direction to 

the change expected from actual or best estimate response of the 

reference unit to the malfunction.

5. The simulator did not fail to cause an alarm or automatic action if the 

reference unit would have caused an alarm or automatic action under 

identical circumstances.

6. The simulator did not cause an alarm or automatic action if the reference 

unit would not cause an alarm or automatic action under identical 
Issue Date: 10/16/12 - 8 - 41502

circumstances.

7. Verify the following attributes are documented in the SBT performance test 

record:

(a) The initial conditions, description of the scenario, and perturbations 

used to induce the transient. 

(b) Listing of key parameters checked and assertion that there were no 

unexpected changes. 

(c) Listing of key alarms and key automatic actions occurring and 

assertion that they would be expected for the scenario. 

(d) Assertion that no unexpected alarms and automatic actions 

occurred. 

8. Assess the SBT test results. Test results should meet acceptance criteria 

and confirm any discrepancies are processed in the licensee‟s simulator 

corrective action program. 

9. Verify that any fidelity issues which impact operator actions have been 

identified by the licensee and the discrepancies have been entered into 

their corrective action program for correction and/or resolution. 

10. Verify licensee=s SBT affirmations of test results are substantiated. 

d. Evaluate sufficiency of simulator reactor core performance testing. 

Sample per 2.03.c.

1. Verify simulator reactor core performance testing has been conducted for 

the most recent reference unit fuel cycle (if simulator used for meeting 

applicant experience requirements in 10 CFR 55.31(a)(5)), (new reactors 

may be evaluated using predicted values.) Verify simulator core testing is 

performed in accordance with the reference unit procedures and 

compared and demonstrated to replicate the response of the reference 

unit. 

2. Verify the simulator reactor core response and performance meets the 

reference unit procedure(s) acceptance criteria.

3. Test results should meet acceptance criteria and confirm any 

discrepancies are processed in the licensee‟s simulator corrective action 

program.

e. Verify post-event simulator testing (N/A for new reactors). Sample per 2.03.d. 

1. Post event simulator testing should be conducted when a reference unit 

event generates relevant data for evaluating simulator performance. If 
Issue Date: 10/16/12 - 9 - 41502

multiple events have occurred, select at least one. This testing:

(a) Considered the sequence of events, operator actions, and was

performed in accordance with reference unit procedures

(b) Demonstrated that post-event simulator testing was conducted and 

relevant data compared to ensure that the simulator is capable of 

reproducing the response of relevant reference unit parameters 

within the scope of simulation. 

f. Verify discrepancies identified from this inspection are entered into the simulator 

corrective action process. Follow up with the licensee regarding any simulator 

discrepancies that prevent overall satisfactory acceptance of a performance test.

03.02 Simulator Performance Testing Acceptance Criteria.

a. Verify the sampled simulator performance tests/test results met the following 

acceptance criteria (if necessary, refer to the specific ANSI/ANS-3.5 standard 

applicable to the simulator being inspected for additional acceptance criteria that may 

apply):

1. allows the use of applicable reference unit procedures (i.e., startup test 

procedure, surveillance procedure, or operating procedure) including procedural 

acceptance criteria.

b. Any observable parameter change corresponds in direction to those expected from 

actual or best estimate response of the reference unit.

c. The simulator shall not fail to cause an alarm or automatic action if the reference unit 

would cause an alarm or automatic action under identical circumstances.

d. The simulator shall not cause an alarm or automatic action if the reference unit would 

not cause an alarm or automatic action under identical circumstances.

03.03 Simulator Performance Record Retention.

Verify the results of simulator performance tests are retained for a minimum of four years 

after completion of each performance test (four years may not be available for new 

reactors, in this case test records should go back to testing done since site delivery) or 

until superseded by updated test results.

41502-04 RESOURCE ESTIMATE

For planning purposes, the direct inspection effort to complete this inspection procedure is 

estimated to be 40 hours of on-site inspection, consistent with the scope of the planned regional 

initiative(s) to be performed. 

It is expected that the actual hours required to complete the inspection may vary from the 

estimate. More effort may be needed if major modeling changes/enhancements have taken 
Issue Date: 10/16/12 - 10 - 41502

place such as complete primary thermo/hydraulic model replacement or simulator platform 

rehost. The inspection hours allocated for the inspection procedure are an estimate for 

budgeting purposes. The hours expended during an inspection should be tailored for the facility 

licensee and accurately recorded.

41502-05 REFERENCES

10 CFR 55, Operators‟ Licenses.

Inspection Manual Chapter 2504, “Construction Inspection Program: Inspection of Construction 

and Operational Programs”.

Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program -- Operations Phase.

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

Examination] (includes prior versions). 

Regulatory Guide, 1.149, Rev. 4, Nuclear Power Plant simulation Facilities for Use in Operator 

Training, License Examinations, and Applicant Experience Requirements (includes prior 

versions). 

41502-06 PROCEDURE COMPLETION

This IP is considered complete when the required number of minimum samples specified in 2.03

above is complete and a determination has been made as to suitability of the plant-referenced 

simulator is of sufficient scope and fidelity for the purposes of 10 CFR 55.

Note: Attachments 1 and 2 are for inspector use only and are not part of the inspection 

report. 

END
Issue Date: 10/16/12 - 11 - 41502

ATTACHMENT 1

CHECKLIST FOR EVALUATING PLANT-REFERENCED 

SIMULATORS OPERATING UNDER 10 CFR 55.46(c) AND (d)

(Circle yes [Y] or no [N]. Answer questions based upon sampling inspection. It is not intended 

that these questions be answered on the basis of exhaustive inspection.)

Y / N 1. Does the plant-referenced simulator demonstrate expected plant response to 

operator input and to normal, transient, and accident conditions to which the

simulator has been designed to respond? [§55.31(a)(5) and §55.46(c)(1)]

Y / N 2. Is the plant-referenced simulator sufficient in scope and fidelity with the reference 

plant to allow conduct of the evolutions listed in 10 CFR 55.45(a)(1) through 

(13),as applicable to the reference plant? [§55.46(c)(1)(i)]

Y / N 3. Is the plant-referenced simulator sufficient in scope and fidelity with the reference 

plant to allow conduct of the evolutions listed in 10 CFR 55.59(c)(3)(i)(A) through 

(AA), as applicable to the reference plant? [§55.46(c)(1)(i)]

Y / N 4. Is the plant-referenced simulator designed and implemented in a manner that

allows for the completion of control manipulations for operator license applicants? 

[§55.46(c)(1)(ii)]

Y / N 5. If the plant-referenced simulator is used to meet experience requirements for

applicants for operator and senior operator licenses, does the plant referenced

simulator utilize 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? The phrase "most recent" means the current core 

or if the reference plant is in a refueling outage, the core just previous to the 

outage. [§55.31(a)(5)], [§55.46(c)(1), and §55.46(c)(2)(i)]

Y / N 6. Has the plant-referenced simulator fidelity been demonstrated so that significant 

control manipulations are completed without procedure exceptions, simulator 

performance exceptions, or deviation from the approved training scenario 

sequence? [§55.46(c)(2)(ii)]

Y / N 7. Has there been any lapse in the facility licensee conducted simulator performance 

testing throughout the life of the simulation facility? [§55.46(d)(1)]

Y / N 8. Are the results of performance testing retained for four years after the completion 

of each performance test or until superseded by updated test results? 

[§55.46(d)(1)] 71111.11, App C C-2

Y / N 9. Are modeling and hardware discrepancies and discrepancies identified from

scenario validation and from performance testing being corrected? [§55.46(d)(2)]

Y / N 10. Are results of any uncorrected performance test failures that may exist at the time 

of the operating test or requalification program inspection available for NRC 

review? [§55.46(d)(3)]
Issue Date: 10/16/12 - 12 - 41502

Y / N 11. Has simulator fidelity been maintained such that license application, examination, 

and test integrity are consistent with 10 CFR 55.49 requirements? [§55.46(d)(4)]
Issue Date: 10/16/12 - 13 - 41502

ATTACHMENT 2

PLANT-REFRENCED SIMULATOR

SCENARIO BASED TESTING METHODOLOGY CHECKLIST

SBT Number: Date Validated:

Item Simulator Performance

1 Simulator performance supported scenario objectives if applicable. Y/N

2 Simulator initial conditions (IC) agreed with reference plant with 

respect to reactor status, plant configuration, and system operation.

Y/N

3 Simulator operated in real time during conduct of SBT. 

Note: Use of “freeze” allowed when evaluating specific performance.

Y/N

4 Simulator demonstrated expected plant response to operator input 

and to normal, transient, and accident conditions to which the 

simulator has been designed to respond.

Y/N

5 Simulator permitted use of the reference plant‟s procedures so that 

the scenario was completed without procedural exceptions, simulator 

performance exceptions, or deviation from the scenario sequence.

Y/N

6 Simulator did not fail to cause an expected alarm or automatic action 

and did not cause an unexpected alarm or automatic action. Note: 

Attach simulator alarm summary (versus time) to SBT Test Results 

record.

Y/N

7 Observable change in simulated parameters corresponded in 

direction to those expected from actual or best estimate response of 

the reference plant. Note: Attach predetermined Monitored 

Parameter List (versus time) to SBT Test Results record.

Y/N

8 Reference plant design limitations were not exceeded. Y/N

9 Each scenario malfunction demonstrated expected plant response to 

its initiating cause.

Y/N

10 SBT conducted in a manner sufficient (i.e., meets requirements of 

ANSI/ANS-3.5-2009) to ensure that simulator fidelity has been 

demonstrated and met for this scenario. Note: Attach relevant “asrun” marked-up plant procedures and or procedure portions/pages 

utilized to support assertion. 

Y/N

11 SBT documentation includes, at a minimum, the scenarios, 

procedures, data collected, and documentation used for initial license 

examinations, requalification examinations and reactivity 

manipulations.

Y/N

12 Modeling and hardware discrepancies identified during the conduct Y/N
Issue Date: 10/16/12 - 14 - 41502

of SBT are documented and entered in the site simulator Corrective 

Action Program (CAP). Note: Discrepancies that directly affect 

operator response (or action) or expected plant response must be 

resolved before the SBT test results can be judged as satisfactory. 

13 Simulator SBT performance test results:

___ SATISFACTORY / ___ UNSATISFACTORY

Note: Attach list of SBT test personnel (include name, job title, and 

level of effort).

Y/N

Technical comments attached: Y/N
Issue Date: 10/16/12 Att3-1 41502

Attachment 3 - Revision History for IP 41502

Commitment 

Tracking 

Number

Accession Number

Issue Date

Change Notice

Description of Change Description of

Training Required and 

Completion Date

Comment and 

Feedback 

Resolution 

Accession Number

N/A ML12233A564

10/16/12

CN 12-024

This is an Initial Issuance. N/A ML12233A562