Text

RO Requalification Program for MD Univ Training Reactor.
	ML20045G145
Person / Time
Site:	University of Maryland
Issue date:	06/01/1993
From:	; MARYLAND, UNIV. OF, COLLEGE PARK, MD
To:	;
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ML20045G142	List: ML20045G140; ML20045G145;
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Reactor Operator Requalification Program i for MARYLAND UNIVERSITY TRAINING REACTOR i

June 1,1993 B

l 9307120258 9307o7 71 hDR ADOCK 05000166 y PDR Ih

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L PURPOSE This document sets forth the requirements for the Reactor Operator (RO) and Senior Reactor Operator (SRO) requalification program for the Maryland University Training Reactor (MUTR), in accordance with the Code of Federal Regulations, Title 10, i Part 50.54, Condition of Licenses. ,

i IL SCHEDULE i

The operator Requalification Program cycle will last a period of two years, beginning on the first quarter of the bi-annual year. The licensed operator will enter the requalification program on the date the USNRC issues a license and will continue in the program until either the expiration date of the current license or the date the current license is terminated. If the operator should receive his/her operating license no greater than six months prior to the completion of the two year cycle, the operator will be exempt from completing the requirements of the current program, but will be required to enter >

the following requalification program cycle. If the operator should receive his/her operating license greater than six months prior to the completion of the cycle, the operator '

will not be required to complete those program requirements required prior to the issuance of the license.

IIL REACTOR OPERATION The operator will be required to perform, as either a Reactor Operator or Senior .

Reactor Operator, a minimum of ten reactor startups during the two year requalification :

cycle.

IV. REQUALIFICATION PROGRAM As part of the requalification program, licensed personnel will participate (as determined by the Reactor Director) as either a student or an instructor. The program will be on a enntinuing basis throughout the requalification cycle in those areas where annual operator and senior operator written examinations indicate that emphasis in scope and depth of coverage is needed in the following subjects: -

A) Theory and principle of operation P

B) General and specific plant operating characteristics C) Reactor instr ument and control systems D) Reactor protection systems E) Engineered safety systems ;

F) Normal, abnormal, and, emergency operating procedures G) Radiation safety and control H) Technical Specifications I) Applicable portions of Code of Federal Regulations Title 10, Chapters 0, 19,20,21,26,51,54,55,71 H) Applicable portions of the Atomic Energy Act (1974-08)

Additionally, a series of lectures / seminars will be conducted throughout the requalification cycle, the frequency of which to be determined by the Reactor Director or his designee. The purpose of these lectures / seminars is to serve as refresher courses for currently licensed RO and SRO's as well as training and instruction for RO and SRO traince's. These lectures will be on a single topic (or related topics) in the areas outlined above, and will be of an average length of 30 to 35 minutes. It will be the responsibility of each licensee and trainee to review the material presented in every topic. This should be accomplished by attending the formal lectures, or , failing that, reviewing the subject ,

matter on an individual basis. Portions of these requirements may be satisfied (as j determined by the Reactor Director) by the licensed operator's participation in either ,

ENNU 320, Nuclear Reactor Operations, as a student or instructor, or in the instruction :

and/or training of students for the NRC license, or both. See Appendix I V. EVALUATION The evaluation of the licensee's knowledge and performance of the requirements set forth in the requalification program will be accomplished by a written and oral examination, including a demonstration at the reactor console. These will be administered annually to each licensed operator. The written examination for the reactor operator will be prepared in accordance with the modified requirements of USNRC Examiner Standard ES-606, dated 09/01/91, Adminstration of NRC Requalification Examinations at Non-Power Reactors (NPRs), which is included in this standard as Appendix II. The oral examination and console performance evaluation will be administered by the Reactor Director, or his designee.

If a license holder scores less than 70% on any section of the annual written examination, the licensee will attend a makeup session on that section topic and will be administered as a quiz. An overall grade of 80% will be required as a passing score.

If an individual receives a grade ofless than 80% overall, it will be mandatory that he be relieved of his licensed duties and enter an accelerated requalification program.

Upon successfully passing a second written examination and certification of satisfactory rating by the Reactor Director, the individual may return to his licensed duties.

An unsatisfactory evaluation on the annual oral examination will require that

discussions of deficiencies take place between the licensee and the Reactor Director or other suitable qualified person designated by the Director. A second oral evaluation will be administered. If performance is again unsatisfactory, the licensee will be relieved of responsibilities and placed into an accelerated requalification program.

VI. ACCELERATED REQUALIFICATION PROGRAM The additional training that a licensee may require (as indicated by his examination) will consist of additional written exams, console performance, or oral facility ,

examination. The additional training and the examination that the licensee receives will depend upon the weaknesses exhibited on previous examinations. The number oflectures and examinations that a licensee will receive will be determined by either the Reactor Director or his designee. the licensee must obtain a rating of at least 80% on the re-evaluation in order to be reassigned to his licensed duties.

VII. DOCUMENT REVIEW The licensee will review during each requalification cycle the following documents -

and instructions that are pertinent to the operations of the reactor facility: .

1. Reactor License (R-70) 1

2. Technical Specifications

3. MUTR Operating and Emergency Procedures

4. Code of Federal Regulations, Title 10, Chapters: 19,20, 50.54, 50.59, 55 VIII. RECORDS The following records will be maintained for each licensed operator and retained -

for the period until the license of the individual has expired or been terminated:

- Current copy of either the licensee's Reactor Operator or Senior Reactor Operator license.

- Copies of the graded requalification examinations administered.

- The operator's Requalification Program checklist.

- The summary of training received by the licensee in the accelerated Requalification Program documented in a memorandum for record and any additional documentation that is pertinent to additional training received by the licensee.

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IX. ADMINISTRATION The Reactor Director or his designee is responsible for the development, administration, and execution of the Reactor Operator Requalification Program. The Reactor Director will be exempt from taking the annual written examination, oral facility examination, and the console performance evaluation, but will be required to perform the operations set forth in Section III and the review of documents set forth in Section VI.

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ATTACHMENT I Operator Requalification Program Progress Checklist - Used as a means of monitoring qualification progress. Each licensed operator will have this checklist placed l in their personnel file. It will be the responsibility of each individual to ensure his/her checklist is kept current.

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OPERATOR REQUALIFICATION PROGRAM PROGRESS CHECKLIST Name: License #: l License Type: License Issue Date: :

Annual requalification cycle: through ;

SECTION 1 j REACTOR OPERATIONS ,

Operator must complete at least 10 Reactor startups during the requalification cycle.

List the dates and operation numbers of the ten startups during the cycle: ,

OPERATION NUMBER DATE

1) j

2) [

3) 4)

5) ;

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7) l 8)

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10) t SECTION II DOCUMENT REVIEW Sign and date on the line corresponding to the following documents after they have been [

reviewed by the licensee. !

1) Facility License i

2) Tech Specs

3) 10CFR Part 19 :

4) 10CFR Part 20 .

5) 10CFR Part 50.54 .

SECTION II-Continued I

6) 10CFR Parc 50.59

7) 10CFR Part 55

8) MUTR OP Series .

9) MUTR SP Series

10) MUTR MP Series

31) MUTR AP Series ,

12) MUTR EP Series SECTION III AhWUAL WRITTEN EXAMS Theory of reactor operations Score: %:

Section I Facility design Score: %: ,

Section II Procedures & Rad Con Score: %:

Section III Aggregate Score: %:

SECTION' IV OPERATIONAL / ORAL EXAM Operational exam administered: date by Comments:

Oral exam administered: date by ,

Comments:

NOTE: The instruction of ENNU 320 may substitute for certain categories. If the operator is an instructor or T/A they should note this on the appropriate line in the " Document Review" section.

l Reactor Director's approval: date: j l

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9 APPENDIX I The following pages are the lesson outlines for the various topics to be discussed l in the lecture / seminar program of the requalification cycle. Included in these outlines are the applicable reference material. Space has been provided for each licensee or trainee to sign and date his/her name as a record of attending the lecture, or individual review.

Below is a listing of the current training topics, more to be added throughout the training ,

cycle:

Topic 1 Startup and Shutdown Checklists Topic h Reactor Startup Topic 3 Reactor Operations Topic 4 Reportable Occurrences ;

Topic 5 EP - Evacuation and Organization l Topic 6 EP - Primary Coolant Leak .

Topic 7 EP - Release of Radioactivity !

Topic 8 - Emcrgency Plan l Topic 9 Power Calibration i Topic 10 Control Rod Drop Time ,

Topic 11 Control Rod Inspection :

Topic 12 Control Rod Calibration Topic 13 Area Radiation Monitor Calibration Topic 14 Pool Water and EfIluent Release Topic 15 Administration Topic 16 Primary Water System ,

Topic 17 Secondary and Make-up Water Systems ;

Topic 18 Reactor Core Topic 19 Control Rod Drive Mechanism !

Topic 20 Reactor Instrumentation Topic 21 Experiments Topic 22 Reactor Facility l

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MUTR Requalification/ Training Program Topic 1: Startup and Shutdown Checklists .

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Learning objectives:

1. Discuss the requirements for an Initial Startup Checklist and an Intermediate Startup Checklist, when each can be performed, and why such checklists are required

2. Discuss and review each item of an Initial Startup Checklist.

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3. Discuss and review each item of a Shutdown Checklist, and the importance of performing such a checklist. ,

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4. Discuss the procedures to be taken when a checklist cannot be performed or i completed due to abnormality in plant conditions.

5. Differentiate the difference between a Channel Check, Channel Calibration, and a Channel test.

References !

Technical Specifications, Section 1.0: Definitions.

Operating Procedure 101: Reactor Startup Chechout.

Operating Procedure 102: Reactor Shutdown Checkout.

Attendance Record Printed Name Signature Date j i

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MUTR Req.ualification/ Training Program Topic 2: Reactor Startup l Learning objectives:

1. Review the procedure for a reactor startup, and the discuss the importance of observing all precautions and limitations.

2. Discuss the indications observed during a startup and when the reactor is considered critical.

3. Discuss and review the differences of startups by " Standard Procedure" and by "Other Methods."

References:

Technical Specifications, Section 1.0: Definitions.

Operating Procedure 103: Reactor Startup.

Attendance Record Printed Name Signature Date Training conducted by:

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MUTR Requalification/ Training Program Topic 3: Reactor Operations Learning objectives:

L Review the Safety Limit and Limiting Conditions of Operation, and discuss the basis for those limits and the importance of not exceeding them.

2. Review and discuss the precautions and procedures for operating (increasing and decreasing power) in the MANUAL mode of operation.

3. Review and discuss the precautions and procedures for operating (increasing and decreasing power)in the AUTOMATIC mode of operation.

4. Discuss the requirements and techniques for proper log taking, and the "most conservative" approach to reading instruments and gages. .

References:

Technical Specifications, Section 2.0: Safety Limits and Limiting safety System Settings.; Section 3.0: Limiting Conditions for Opera tion.

Operating Procedure 104: Reactor Operations ,

Attendance Record Printed Name Signature Date s

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i MUTR Requalification/ Training Program Topic 4: Reportable Occurrence 1

Learning objectives:

1. Review the six Reportable Occurrences as outlined in the Technical Specifications. Discuss the meaning and scope of each as it applies to the Maryland University Training Reactor.

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2. Discuss the Reactor Operator's response and responsibilities when a Reportable Occurrence occurs.

3. Discuss the Department's response and responsibilities when a Reportable Occurrence occurs.

4. Review the meaning of an " unscheduled shutdown", and when such a shutdown could be considered a Reportable Occurrence.

References:

Technical Specifications, Section 1.0: Definitions.; Section 6.0: Administration Emergency Procedure 403: Response to Reportable Occurrences.

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Attendance Record ;

Printed Name Signature Date i i

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4 MUTR Requalification/ Training Program Topic 5: Emergency Procedures - Evacuation and Organization Learning objectives:

1. Review the Emergency Procedures for evacuation. Discuss the various assembly t areas, where emergency phones are located, and review the Calldown list.

2. Discuss the Reactor Oper_ tor's response and responsibilities during an evacuation.

3. Discuss the Department's response and responsibilities during an evacuation.

4. Differentiate between the Evacuation buzzer and the door buzzer.

References:

Technical Specifications, Section 6.0: Administration Emergency Procedure 401: Reactor Building Evacuation.

Emergency Procedure 406: MUTR Emergency Organization.

Emergency Procedure 407: Nuclear Reactor Em.ergency Call List.

Attendance Record Printed Name Signature Date Training conducted by:

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MUTR Requalification/1' raining Program ;

Topic 6: Emergency Procedures - Primary Coolant Leaks Learning objectives:

1. Review the Emergency Procedure for Primary Coolant Leaks. Discuss the various areas where leaks could occur, what is acceptable water losses (valve ;

stem leaks, etc.), and the importance of keeping the core covered. I I

2. Discuss the Reactor Operator's response and responsibilities during a Primary l j

Coolant leak.

3. Discuss the Department's response and responsibilities during an evacuation, j

References:

Technical Specifications, Section 5.1: Reactor Coolant System Emergency Procedure 401: Reactor Building Evacuation.

Emergency Procedure 402: Primary Coolant System Leaks.

FSAR, Section 4.0: Primary Coolant and Purification System.

Attendance Record i

Printed Name Signature Date l

Training conducted by:

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Topic 7: Emergency Procedures - Release of Radioactivity l

Learning objectives:

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1. Review the Emergency Procedure for Release of Radioactivity. Discuss the exposure limits for personnel as set forth by 10-CFR-20.

2. Distinguish the difference between a Minor spill (dry and liquid), Major spill (dry and liquid), and airborne release. Review the response to each.

3. Describe the actions for External and Internal contamination of personnel, as well as for personnel injuries.

4. Review the line of authority.

References:

Emergency Procedure 401: Reactor Building Evacuation.

Emergency Procedure 404: Release ofRadicactivity.

Emergency Procedure 406: Mutr Emergency Organization.

Cod e of Federal Regulations, Title 10, Chapter 20: Standards for P vtection Against Radiation Attendance Record Printed Name Signature Date Training ecnducted by:

MUTR Requalification/Praining Program Topic 8: Emergency Plan Learning objectives:

1. Review the Emergency Plan. Discuss the three levels of emergency (Personnel Emergency, Unusual Event, and Alert), and identify possible scenarios and appropriate responses for each.

2. List the emergency organization members. Review the responsibilities of each member and the line of authority of the group. Identify who currently holds these positions

3. Discuss the various emergency facilities and equipment available to MUTR during an emergency event.

References:

1 Emergency Preparedness Plan 4 1

Emergency Procedure 406: MUTR Emergency Organization.

Emergency Procedure 407: Nuclear Reactor Emergency Call List.

Attendance Record Printed Name Signature Date Training conducted by:

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MUTR Requalification/ Training Program Topic 9: Power Calibration Learning objectives:

1. Review the procedure for a power calibration. Identify the precautions and prerequisites that mustbe observed before performing a power calibration. Give the frequency at which this surveillance procedure must be performed

2. Review the power calibration equation used, and identify each term used.

3. Discuss the method of data collection during a calibration, and how the data is used. Review a Power Calibration Worksheet, and how it is used.

4. Discuss the actions taken when measured thermal output does not match indicated power by less than 21 ,

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References:

FSAR, Section 3.0: Reactor j Surveillance Procedure 202: Reactor Power Calibration.

Attendance Record Printed Name Signature Date ,

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MUTR Requalification/ Training Program Topic 10: Control Rod Drop Time Learning objectives:

1. Review the procedure to determine control rod drop times. Discuss the equipment used and how it is set-up. Give the frequency that this surveillance ;

procedure is required to be preformed.

2. Review the Control Rod Drop Time Data Sheet.

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3. Discuss the actions taken when control rod drop times are greater than 1 second. j 1

References:

l FSAR, Section 3.0: Reactor.

Surveillance Procedure 203: Control Rod Drop Times.

Attendance Record Printed Name Signature Date Training conducted by:

6 MUTR Requalification/ Training Program Topic 11: Control Rod Inspection ,

Learning objectives:

1. Review the procedure for inspection of control rods. Give the frequency that this surveillance procedure is required to be preformed.

2. Review the requirements for a fuel movement. Identify the manning requirements, and the responsibility of each (SRO, RO, etc.). .

3. Review Control Rod Inspection Sheet. Note the specific dimension to be taken and what to look for in a visual inspection.

References:

Technical Specifications, Section 4.0: Surveillance Requirements l FSAR, Section 3.0: Reactor. f Surveillance Procedure 201: Control Rod Inspection. ,

Maintenance Procedure 303: Fuel Movement. 1 Maintenance Procedure 304: Control Rod Drive and Control Rod Removal.

Attendance Record 4 Printed Name Signature Date )

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Training conducted by:

r-MUTR Requalification/Praining Program Topic 12: Control Rod Calibration l Learning objectives:

1. Review the procedure for calibration of control rods. Give the frequency that this surveillance procedure is required to be preformed.

2. Discuss the requirements for a control rod calibration (waiting for stable period, not exceeding 500 watts, etc.), and the reason behind each.

3. Review the Reactivity vs Asymptotic Period charts and understand their use.

4. Review Control Rod Calibration Data Table, and identify what data is entered in this table. Understand how to construct a rod worth curve from this table.

References:

Technical Specifications, Section 4.0: Surveillance Requirements.

FSAR, Section 3.0: Reactor.

Surveillance Procedure 204: Control Rod Inspection.

Attendance Record Printed Name Signature Date

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Training conducted by:

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I MUTR Requalification/ Training Program ,

Topic 13: Area Radiation Monitor Calibration Learning objectives:

1. Review the procedure for radiation monitor calibration. Give the frequency that this surveillance procedure is required to be preformed.

2. Discuss the importance of using a traceable source for RAM calibrations.

3. Review the Area Radiation Monitor Calibration Worksheet.

4. Specify the requirements for operating with both RAM's down for maintenance.

References:

Technical Specifications, Section 3.4: Radiation Monitoring System.

Section 4.0: Surveillance Requirements.

FSAR, Section 6.4: Area Radiation Monitoring System.

Surveillance Procedure 205: Control Rod Inspection.

Attendance Record Printed Name Signature Date i

Training conducted by: ;

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: l MUTR Requalification/ Training Program Topic 14: Pool Water and Effluent Release Learning objectives:

1. Review the procedure for pool water sampling. Give the frequency that this surveillance procedure is required to be preformed.

2. Review the Pool Water Data Sheet.

3. Review the procedure for sump water sampling. Discuss the importance of performing an analysis of sump water before dumping to city sewers (effluent).

Review 10CFR20 appendix B, activity limits for effluent. !

4. Discuss how gaseous effluent is produced at MUTR (Ar-41), and how this gaseous efIluent is released to the environment.

References:

Technical Specifications, Section 3.3: Primary Coolant Condition.

Section 4.0: Surveillance Requirements.

Surveillance Procedure 206: Pool Water Conductivity Determination. 5 Surveillance Procedure 207: Gamma Ray Spectroscopy ofPool Water.

Surveillance Procedure 208: Sampling of Sump Water.

i FSAR Section 8.0: Radioactive Waste Management.

Code of Federal Regulations, Title 10, Chapter 20, Appendix B: Annual Limits.

Attendance Record Printed Name Signature Date i

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: j MUTR Requalification/ Training Program Topic 15: Administration l

4 Learning objectives:

1. Review the administrative organization of the University of Maryland and for the MUTR.

2. List the facility staff requirements for operating the MUTR.

); 3. List the Requirements for when a SRO must be present during MUTR -

operations. Define "on call" and where the on call SRO is allowed to go and what he/she is allowed to do while in this status.

4. Discuss training requirements for MUTR, and define who is allowed to manipulate the controls of the MUTR.

References:

Technical Specifications, Section 1.0: Definitions.

Section 6.0: Administration.

Code of Federal Regulations, Title 10, Chapter 55: Operators' Licenses, t

I Attendance Record l Printed Name Signature Date i

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Training conducted by.

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MUTR Requalification/ Training Program Topic 16: Primary Water System i

Learning objectives:

1. Draw the primary water system, identifying major components. Give the purpose for each component.

2. Classify the primary water pump, heat exchanger (s), and ion exchanger.

3. Discuss the operating characteristics of the primary water system (flowrate, etc.).

Review the importance for maintaining secondary water pressure higher than primary.

4. Discuss surveillance requirements for the primary water system.

References:

Technical Specifications, Section 3.3: Primary Coolant Condition.

Section 4.3: Reactor Coolant System.

Section 4.1: Reactor Coolant System.

FASR, Section 4.0: Reactor Coolant and Purification System.

1 Attendance Record Printed Name Signature Date !

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MUTR Requalification/ Training Program Topic 17: Secondary and Make-up Water System i

Learning objectives:

1. Draw the secondary water system, identifying major components. Give the purpose for each component.

2. Draw the make-up water system, identifying major components.

3. Discuss the operating characteristics of the secondary primary water system (flowrate, etc.). Review the importance for maintaining secondary water pressure higher than primary.

4. Discuss the operating characteristics of the make-up water system. Review the purpose of the 121b reducer and check-valve in this system. I

References:

FASR, Section 4.0: Reactor Coolant and Purification System.

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Attendance Record Printed Name Signature Date h

Training conducted by:

MUTR Requalification/Fraining Program Topic 18: Reactor Core Learning objectives:

1. Draw an overhead view of the reactor core, identifying major components (control rods, startup source, etc.).

2. Describe the characteristics (dimensions and materials) of a standard fuel rod, instrumented fuel rod, and control rod.

3. Describe the PuBe startup source. Explain how this source gives off neutrons for startup.

4. Explain how the thermocouples in the instrumented fuel rod works.

References:

Technical Specifications, Section 5.0: Reactor Fuel FASR, Section 3.0: Reactor.

Attendance Record Printed Name Signature Date Training conducted by:

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MUTR Requalification/ Training Program Topic 19: Control Rod Drive Mechanism Learning objectives:

1. Identify the major components of a control rod drive mechanism (CRDM).

Distinguish between the three micro-switches, and hoe each is physically linked i to a control rod. ;

2. Describe the operation of the logic circuit, and the various indicating lights available to the operator. l

3. Draw a simplified drawing of the drive motor operating circuit, and describe :

how this works to raise / lower a control rod.

4. Explain how a CRDM operates during a sram. ,

References:

Technical Specifications, Section 3.2: Reactor Control and Safety Control.

FASR, Section 3.0: Reactor.

Attendance Record 1

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MUTR Requalification/ Training Program ,

Topic 20: Reactor Instrumentation Learning objectives:

1. List the three type of nuclear detectors used in the MUTR, and give the location -

for each around the reactor core.

2. Describe the operation of the fission chamber, and list which instruments this detector provides a signal to.

3. Describe the operation of the compensated ion chambers, and list which instruments these detectors provide signals to.

4. Describe the operation of the un-compensated ion chamber, and list which instruments this detector provides a signal to.

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References:

l FASR, Section G.0: Instrumentation and Control.

ENNU-320 Manual: Volume II. ;

i Attendance Record 1 Printed Name Signature Date Training conducted by:

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l l MUTR Requalification/ Training Program Topic 21: Experiments Learning objectives:

1. List the three type of experiment classifications, and who can approve each one.

2. List the seven specifications / limitations of experiments for MUTR.

3. Describe the various experimental facilities at the MUTR, their locations, and how they operate.

4. Discuss potential casualty situations involving experiments, and the response of the Reactor Operator.

References:

Technical Specifications, Section 1.0: Definitions.

Section 3.5: Limitations on Experiments.

FASR, Section 5.0: Experimental Facilities. l ENNU-320 Manual: Volume II.

i Attendance Record Printed Name Signature Date Training conducted by:

MUTR Requalification/ Training Program l Topic 22: Reactor Facility l

Learning objectives:

1. Describe the construction of the reactor pool tank, give dimensions and material. ,

2. Describe the biological shield, its construction, dimensions, and material composition. Discuss expected radiation doses around the shield and review a Radiation Survey. r

3. Explain where potential Radiation Areas are in the facility (Hot Room, bridge, etc.), and the importance ofmaintaining security. Locate the fuel storage pit, and discuss importance of maintaining Keffless than 0.8.

4. Describe the basic features of the facility building, the ventilation system, communication system, and the alarm system. Review the various evacuation routes.

References:

Technical Specifications, Section 5.2: Ventilation System.

Section 5.3: Fuel Storage.

FASR, Section 2.0: Reactor Facility.

Section 6.G: Communication.

Section 7.8: Fuel storage.

Attendance Record B

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Training conducted by:

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APPENDIX II USNRC Examiner Standard ES-G0G Dated: 09/01/91

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ES-606

. 09/01/91 ADMINISTRATION OF NRC REQUALIFICATION EXAMINATIONS AT NON-POWER REACTORS (NPRs) i A. _ Purpose The NRC requalification examinations for Non-Power Reactors are adminis-tered under this stancard in accordance with the provisions of 10 CFR 55.59(a)(2)(iii) and 10 CFR 55.59(c)(7). The program described in this standard will minimize the potential for an adverse impact on the safe l operation of NPR f acilities, provide the NRC with an assessment of the effectiveness of the f acilities requalification training programs, and meet the requirements of 10 CFR 55.57(b)(2)(iv).

. B. Scope t This standard provides guidance and requirements to NRC examiners for the administration of NRC recualification examinations at NPR f acilities. This ,

effort follows the regulatory policy specified in the Atomic Energy Act Section 104.c, (i.e., the Commission was directed to impose only such minimum anount of regulation to protect the public health and safety and permit the conduct of independent and diverse research and development).

The examiner must keep this policy of minimum regulation in mind during the-administration of the NFR requalification examinations, and remain flexible to the circumstances at NPRs. .

Where possible, the requalification examination will be developed by an ;

examination team consisting of NRC examiner (s) and f acility representative (s). 2 The examination will be based upon the f acility requalification program and available f acility learning objectives. This approach will result in a more technically sound and operationally oriented examination. In addition, 3 co tvaluation of operator performance by the f acility and the NRC 3 will enhance the ability of the NRC to assess both individual and program performance. ;

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The NRC-administered requalification examination is composed of an operating test and a written examination. The operating test consists of the performance of five control console and in-facility operator tasks or procedures. These tasks will cover f acility systems identified by the f acility and reviewed and accepted by the NRC, that are important to the sa'4 operation of the facility. The written examination consists of three sections: Section A will be " Theory," Section B will be " Procedures and ;

Radiological Controls," and Section C will be " Facility and Radiation Monitoring Systems."

Facilities with small staff size (2-3 operating personnel) or simple reactor design and operations may not find it feasible to comply with this standard. In such instances, exemption from the specifics of this standard may be requested by the f acility and granted on a case basis at the discretion of the Chief, Non-Power Reactor Section, NRR.

C. Administrative Controls

1. Responsibilities

a. Schedule of Notifications (1) NRC notifies the f acility to be evaluated approximately 90 days in aovance of the examination date using the attached

" Notification Letter" ( Attachment 1). Examination visits ,

should be scheduled to coincide with the requalification training cycle of the f acility, if possible.

(2) The f acility responds to the " Notification Letter" approximately 60 days in advance of the evaluction by i providing to the NRC the following: !

Reference Materials and Test Items i List of operators to be examined ;

Staff employee (s) assigned to assist NRC Examiner (s) 1 2 of 31 i

ES- E06

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(3) The NRC will confirm the examination schedule, and the operators participating in the examination, with the f acility at least 30 days in adva'nce. i

b. Selection of Operators The f acility will submit the list of operators for NRC examination 60 days prior to the administration date. The NRC will review and concur on the individuals to be examined, based on the following criteria:

(1) Number of licensed personnel not examined during current license term.

(2) Length of time until license expiration.

(3) Mininial perturbation on f acility schedules and oper ations.

(4) Total number of operators at the f acility.

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c. Examination Preparation (1 ) The f acility supplies the reference and examination materials :

as requested in the " Notification Letter" (Attachment 1).

The NRC evaluates the f acility materials for adequacy for .

examination _ preparation.

(2) The NRC will prepare the examination from the materials supplied by the f acility. The f acility will retain the option to assist in the development of the examination.

(3) NRC reserves the right to reschedule NRC-administered requalification examinations if the facility generated materials are inadequate for examination preparation.

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d. Facility Involvement 1

(1) The f acility will be requested to provide an employee to assist the NRC examiner (s). Tne employee is expected to be a licensed or previously licensed SRO at the facility or a similar facility. If desired by the f acility, and agreed to by the Chief Examiner, an additional employee may be a member of the examination team. The function of these indi-viduals is to provide f acility specific technical assistance to the NRC in the developuent and review of the written ,

examination items, control console tasks, and in-f acility' ;

operator tasks. Normally, the f acility representatives will participate in the conduct of the operating test and written examination as f acility evaluators.

(2) To ensure examination security, the f acility representatives who are on the examination team have examination security restrictions placed upon them. These restrictions begin

- upon review of the actual examination and continue until the examination administration is concluded.

Facility representatives shall not knowingly communicate by any means the content or scope of the examination to unauthorized persons.

Each f acility representative shall be required to sign. an -

Exam Security Agreement (Attachment 2) prior to review of '

the actual examination as stated above and a Post Exam Security Agreement ( Attachment 3) at the conclusion of the examination process. These agreements reinforce adherence to the above restrictions. ,

1 4 of 31 j

ES- 606 ,

. '. 09/01/91 (3) Provide by the end of the exam day the f acility evaluator (s) ,

preliminary pass /f ail results for the operating test and the final results prior to the exit meeting.

(4) The f acility grades the written examinations and the l operating tests in parallel with the NRC Examiner (s). [

(5) On a case basis, f acilities may opt for a solely HRC administered examination or one administered by an outside evaluator (s) from a similar f acility.

2. Aaministrative Procedure ;

a. Ex amination Administration Each portion of the requalification examination includes the -

appropriate oral briefing or rules handout. The NRC's position as established by the NRR Office Director or his designee shall-be final on the evaluation of an individual.

b. Requalification Program Evaluation The program will be evaluated for any deficiencies or weaknesses based on examination and test adequacy and operator performance ,

on the examination. The wide variance in staff sizes and tne relttively small nun.ber of operators that will typically be evaluated precludes performing a statistical program evaluation. r However, if any of the items listed below are noted dcrits the conduct of an NRC-administered requalification examinations, a subsequent evaluation of the f acility's training program will be considered. These items are:

t (1) Greater than 50 percent of the operators fail the exam ,

where 4 or more operators are evaluated during an examination.

4 i

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- . 09/01/91 (2) A significant deviation exists between the NRC examiners and f acility evaluators on pass /f ail'results. (i .e. , the f acil-ity is less conservative in their evaluation of more than one operator).-

(3) The f acility evaluator -is unable to administer a satisfactory ex amination. (e.g. leading the candidate, cueing by providing answers, or performing steps for the candidate.)

For the purpose of license renewal, NRC examiner evaluations are used. If the facility evaluators judge their operators as ,

unsatisfactory, while the NRC does not, then f acility corrective actions are expected and may be required. 3

c. Recualification Performance of an Individual For an individual to successfully pass the requalification i examination as graded by the NRC, they shall satisfactorily ,

' complete the written and the operating examinations as described later in D.l.c(2)(c) and D.2.c(2).

Implementation

1. Operatino Test ,

r

a. Introduction .

t J

The operating test portion of the exaniniation is open reference.

During the Operating Test portion of the requalification examination each individual will be evaluated. on his/her ability to satisf actorily complete five tasks, using appropriate f acility ;

procedures. These tasks are used to evaluate:

.i

- activities pertinent to facility safety and control .

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- f acility requalification training program effectiveness !

- operators' understanding of f acility system operations they may be required to perform or direct' ,

t

- individual competencies. !

Individuals will be evaluated on task / procedure performance by both an NRC and a facility evaluator. After the completion of ;

each task, the f acility evaluator will ask the examinee a minimun of two predetermined questions about the task / procedure or system involv ed. The NRC evaluator may ask additional questions directly of the operator after completion of each task; however, to the ,

extent possible these questions will be asked through the facility evaluator. These additional questions are for clarification or ,

verification of tasks performed and are not intended to expand the scope of the predetermined questions.

b. Res ponsibili ties (1) Facility (a) The f acility identifies those systems and procedural .j duties applicable to safe operation. For example:

- Systems covered during the f acility requalification cycle

- New oc recently modified systems ,

- Fuel accountability and handling

- Building and pre-startup requirements ;

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- Experiment handling 7 of 31

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- Radiation nonitoring and control i

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- Other systems and procedures as appropriate to the safe operation of the specific facility ,

(b) Five tasks are selected for each operator to perform.

Where appropriate, there should be a differentiation between R0 and SRO level tasks. An R0 is only- ;

responsible for R0 tasks; an SR0 is responsible for ,

all tasks. For each task, the f acility specifies the criteria for satisfactory completion and indicate ,

critical steps. Critical steps are those actions which, ,

when not performed correctly or not performed at all ,

would: prevent the system from operating safely or prevent completion of an essential safety action.

Examples of essential safety actions are: .

- ability to effectively manipulate controls

) affecting reactivity;

- ability to actuate a reactor trip; end

- ability to comply with technical specifications

- ability to reauce excessive Ievels of radiation and to guard against personnel exposure for those tasks for which a written procedure exists, it is acceptable to use a copy of the procedure or procedure section and mark those steps considered critical. If no written procedure exists, a written description of the task, list of expected actions, and indication of ;

critical steps will be generated for the examination.

(c) Efforts must be made to avoid operating test compromise. Operators examined on the same day may all perform the same tasks. Operators examined on l subsequent days must perform a minimum of two tasks not previously administered. Other reasonable logistics to administer the requisite operating tasks may be agreed to by the Chief Examiner.

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- . '. 09/01/91 (d) Of the five tasks each operator performs, at least ~one must be a control console operation involving a reactiv-ity manipulation. This operation may be part of an over-all evolution including more' than one task. For example, an operator may perform a reactor start-up as his first task, then respond to a simulated instrument f ailure ' ,

during the start-up as a second task.

At least one of the tasks performed by each operator must involve response to an abnormal event. Examples i are an instrument failure, component f ailure, radiation monitor alarm, or similar probiem.

At least one of the tasks performed by each operator must involve response to an emergency situation. Exam-ples of emergency situations are building evacuation, large reactor pool leak, or high radiation levels, t At least one of the tasks to be performed by each operator must be performed in the f acility.

(e) At least two questions will be developed to ask the '

operator at the completion of each task. Questions may be selected from f acility question banks or previously administered NRC examinations. However, to the extent possible the questions selected should:

- be based on the task or system being operated

- discriminate between R0/SRO responsibilities where appropriate

- emphasize knowledges required for task performance or procedure implementation and compliance ;

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09/01/91 (2) NRC

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(a) The NRC examiner (s) will evaluate the f acility identified systems, tasks, and questions to ensure that the examination tests knowledges and abilities appropriate for NPR operators and is applicable to that f acility.

(3) Examination Team (a) An examination team consisting of NRC examiner (s) and

! f acility representative (s) may be used to review the ex aminati on. The NRC and the facility representative (s) on the exam team will jointly review and agree upon critical steps prior to exam administration.

(b) The NRC may substitute up to 20 percent of the f acility derived tasks and/or questions with those selected or developed by the NRC. Any added test items, including successful completion criteria and critical steps, will be reviewed with facility evaluators prior to their administration. The NRC Chief Examiner has the final ,

authority in deciding exam content. If additional questions are asked based on observations during task performance, these should be reviewed with the f acility as soon as possible after the tar * ; are completed. ,

(c) The set of tasks and questions to be administered to each operator shall be reviewed by the Chief Examiner or his designee. Any disagreements in selection of tasks will be reviewed by the Chief, Non-Power Reactors Secti on.

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c. Recualification Exam Process (1) Conduct of Doeratino Test (a) The operating test will be planned for approximately 90 minutes in length. This includes both the control ;

room and in-f acility time and is reflective of actual' ;

examination contact time. Non-contact time may include, but is not limited to the following:

- briefings, console setup, f acility problems

- time spent complying with f acility security and health physics administrative requirements

- transit time between f acility locations (b) The f acility evaluator will brief the operator using the " Briefing Checklist" (attachment 4). If desired, the operators may be briefed as a gecup prior to the start of the operating tests.

(c) Normally, passive observations of task performance are m ade. An operator should not be interrupted during console control manipulations to be asked questions or to be presented the next task. New tasks in an evolution should be presented when the f acility is in a steady state condition.

(d) The f acility evaluator will conduct the operating test while the NRC examiner _ grades in parallel. The NRC examiner may ask followup questions directly of the operator after task completion, however to the extent possible these questions will be asked through the facility evaluator.

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09/01/91 (e) The NRC. examinee ensures that the f acility evaluator is j 4

conducting an appropriate examination. If the NRC examiner has determined that the examination being conducted is inadequate to allow a pass /f' ail determination, the NRC examiner shall discuss this concern with the facility ev aluator. If the examination conduct continues to be ,

t unsatisfactory, the NRC examiner may choose to conduct the remainder of the examination with the facility ,

evaluator grading in parallel. The Chief Examiner will be informed at the completion of the individual !

exam if this option is chosen.

(f) As soon as possible af ter such issues arise the NRC Chief Examiner shall resolve with the facility representatives all unforseen technical questions or \

issues that could result in'an individual f ailing- the examination.

(2) Evaluation of Operatino Tests .

(a) Any deficiencies noted will be recorded using the appropriate NRC or facility form. Significant defi-ciencies will normally be associated with identified critical steps. Additional or alternative critical steps may be identified af ter the initiation of a task due to unanticipated operator actions. These will be f identified and conflicts resolved in the same manner as the original critical steps, in accordance with the exam team responsibilities contained in paragraph D.I . b .3. a . ?

(b) Should an individual incorrectly perform a critical l step, the task will be graded as UNSATISFACTORY.

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?, - . 09/01/91 (c) In order to be evaluated as SATISFACTORY on the operating examination, each operator shall: l (1) Successfully complete 80 percent (4 of 5) of the tasks evaluated.

(2) Correctly answer 70 percent of the prewritten task system / procedure questions. Followup questions will be used only to confirm step performance and/or to confirm the initial response to a ques ti on.

(d) The NRC will notify the f acility immediately of any !

individual whose performance on the examination is considered to require immediate removal from licensed duties.

2. Written Examination Evaluations

a. In troduc ti on The written section of the examination is open reference. The purpose of the three section written examination is to assess the individual's knowledge of f acility systems, procedures, radiological controls / systems, operational theory, and operating limits including the Technical Specifications.

Section A of the written examination is composed of. theory, thermodynamics and f acility operating characteristics. The questions should be related to facility theory fundamentals and applicable to operations.

Section B of the written examination relates to procedures. The focus is on f acil.ity emergency, normal operation, and abnormal

) procedures; administrative controls (including TS, E-plan, and-Administrative Proceoures ); and radiological controls procedures. >

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Section C of the written examination is composed of reactor and radiation monitoring systems. The focus is on systems applicable j to reactor operations. '

i

b. Responsibility i

(1) Facility Responsibility (a) The f acility provides requalification examination question items with the appropriate training material ref erence for each item.

t These items should be reviewed for appropriateness, l clarity, and iniportance to saf ety. 'I (b) The f acility is expected to provide sufficient test *i items to prepare an examination of twenty questions I per section. At least 50 percent of the items are I

expected to be objective questions.

(c) The written examination will not discriminate between R0 and SR0 knowledge level. ,

(d) Three hours will be allcwed for the written examination. {

r (e) The facility shall be responsible for providing all )

required reference material.

i (f) The f acility representative will review all revised test items, evaluating them for: ,

- appropriateness

- technical accuracy and clarity 3

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( 2) NRC Responsibility (a) The NRC may augment the f acility's test questions.

The test will encompass the f acility's test items with an addition of no more that 20 percent of items beyond those submitted by the f acility.

(b) Each test question should be verified as job related and relevant.

(c) If a clear tie to job relevancy does not exist, the applicability of the question shall be discussed with the f acility representatives.

(d) Should it be necessary to develop additional items to satisfy the examination content, the f acility will be requested to do so.

(e) Proposed items may be modified, deleted, or replaced

-if deemed necessary by the NRC.

c. Written Examination Process (1) Written Examination Conduct Each section of the examination will be proctored by a facility representative.

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(2) Written Examination Evaluations j

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l Using the examination and key, the f acility and NRC will independently grade each section of the written examination. ,

The grading of all written examinations shall be completed ,

within 5 working days of the examination administration-date. Grades will be recorded on the written examination cover sheet.

i In ceder to be judged satisfactory on the written :

portion of the examination, each operator must achieve ,

at least a 70 percent overall score as graded by the NRC. Less than 70 percent in one section will not constitute a f ailure but indicate an area requiring j remedial action by the facility.

E. Actions Recuired for an Individual Examination Failure Failure of one written examination section: If one or more sections of the written examination are f ailed, but an overall passing grade of 70' l percent or greater is attained the f acility would determine the appropriate corrective action and retest the individual on the f ailed sections.

In this situation, no NRC involvement is necessary for license renewal purposes.

First Failure: If an operator scores less than 70 percent overall on the j written examination or is evaluated as unsatisfactory on the operating test, the operator is expected to be renoved from licensed duties, given . remedial i training, and retested by the f acility. If the NRC does nct observe and co-evaluate the f acility's retest, the NRC would re-examine the operator i for license renewal during the next scheduled NRC examination at the ,

facility.

l 1

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- .' ES-606 09/01/91 First Retake With Second failure: Only f ailed sections would be r e-ex ami ned. Failure of the first retake would not require licensing action, but would necessitate a subsequent compl'ete written examination and an operating test. I Second Retake With Third f ailure: The second retake examination would be a full written examination and operating test. Failure of the written examination or the operating test in the second retake will normally result in an order to suspend the license and show cause why the license should not be revoked.

F. Actions Recuired for Requalification Prooram Deficiencies For any apparent program deficiencies, the following NRC actions will be considered. Additional actions may be taken at the discretion of the NRR Office Director or his designee. !

4

)

a. Request that the f acility review program deficiencies and identify I

corrective actions needed to improve operator performance.

b. Meet with senior f acility management to review program deficiencies and determine root causes, corrective actions proposed, schedule for i corrective action implementation, and follow-up inspections and ex amination s. t

c. Determine:

(1) The significance of generic performance deficiencies identified during the program evaluation.

(2) If recent facility events relate to licensed operator performance, and (3) Recommendations by NRC regional and RRR staff.

) t t

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G. Operator License Renewal Policy

1. Licenses for operators and senior operators will be renewed upon timely application, as described in ES-203 if the individual in question has successfully passed an NRC-administered requalification examination .

)

within the term of their license.

2. If an individual has not successfully passed an NRC-administered requalification examination within the term of their license but t has f ailed an NRC requalification examination no more than twice, f

then the individuti license is extended under the timely application provisions until the individual conforms with G.1 above. .

H. Final Requalification Proccani Evaluation Report A final requalification results sunmary sheet (Attachment 5) similar to ;

the final examination report for an initial licensing examination shall be

' l prepared when the grading of requalification examinations has been completed.

A complete copy of the report shall be filed in the f acility requalification file. The results summary is required to verify OLTS data and for statistical data.

I. Individual Requalification Examination Report ,

Attachcent 6 should be filled out for each cperator who is administered an {

NRC requalification examination. One copy of this report should be sent to the f acility, one copy filed in the individual's docket folder in the OLB office and one copy filed in the f acility requalification file. 7 J. Record Retention i

1. A f acility requalification file will be maintained for each f acility.

All f acility evaluation forms, records, assignment sheets, individual examination reports and correspondence relating to the requalification ;

I

- program audit for the latest two evaluations will be retained.

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2. When the requalification evaluation has been completed by the OLB, a copy of all NRC-administered written, cperating console and walk-through examinations shall be supplied to the f acility. The f acili-ties are required to maintain these records until the operator's or senior operator's license is renewed in accordance with 10 CFR 55.59' or for two years af ter license expiration. ;

3. Material relating to an individual f ailure will be retained by the OLB as necessary to support denial of license renewal per 10 CFR 55.57(b)(2)(iv). This will include:

a. Examination cover page for all exaninations.

b. The portions of the examination that resulted in the f ailure.

Attachments:

l

1. Notification Letter

2. Pre-Exan Security Agreement

3. Post-Exan Security Agreement

4. Briefing Checklist-System Walk-through

5. Requalification Results Sunnary Sheet

6. Individual Requalification Examination Report >

19 o f 31 l

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2 ES-606 l

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ATTACHMENT 1 NOTIFICATION LETTER (INSERT FACILITY ADDRESSEE)

~

SUBJECT:

REQUALIFICATION PROGRAM EVALUATION In a telephone conversation between M (title) and M (Section Chief), arrangements were made for an evaluation of the requalification program and licensed personnel at the (f acility name). The evaluation visit is scheduled for the week of (date).

r for this visit, the NRC examiners will administer the operating and written ex amination s. The NRC examiners will discuss with the appropriate f acility personnel and operators the schedule and the process for these examinations.

For the examiners to adcquately prepare the examination, 60 days prior to the examination, provide the items listed in Enclosure 1 " Reference Material Requirements" ano a list of operators to be examined. M has ,

been advised of our reference material needs and where they are to be sent.

NRC reserves the right to postpone NRC-administered requalification examinations if the f acility generated materials are inadequate for examination preparation.

It is requested that an employee be provided to complete the examination team.

The employce is ex>ected to be a licensed or previously licensed SRO at your ,

f acility or similar f acility. If desired by the facility, and agreed to by the Chief Examiner, an additional employee may be a member of the examination team.

These individuals must not be scheduled for an NRC-adainistered examination during this visit. Upon review of the examination, the f acility representative will be required to sign a security agreement.

The f acility representative (s) shall be restricted from knowingly communicating by any means the content or scope of the examination to unauthorized person (s).

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- 09/01/91 i The f acility management is responsible for providing adequate space and accommodations to properly develop and conduct the examinations. Enclosure 2,

" Administration of Requalification Examinations," describes our requirements for developing and conducting the exmainations.

Enclosure 3, contains the "NRC Rules and Guidance for Exmninees" that will be in effect during the administration of the written examination. The f acility managenent is responsible for ensuring that all operators are aware of these rules. The requalification examinations and the subsequent evaluation of the f acility requalification program will be performed in accordance with ES- .

This request is covered by Office of Management and Budget Clearance Number '

3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months per response, including gathering, xeroxing and mailing the required materi al . Com!nents on the accuracy of this estimate and suggestions to reduce .

the burden may be directed to the Office of Management and Budget, Paperwork ,

Reduction Pecject (3150-0101), Room 3208, New' Executive Office Building, Washington D.C. 20503, and the U.S. Nuclear Regulatory Commission, Records and Reports Management Branch, Office of Information Resources Management, ,

Washington, D.C. 20555. ,

Thank you for your cooperation in this matter. If you have any questions I

on the evaluation process, please contact (Headquarters Section Chief and telephone nunber).

Sincerely, ;

(Appropriate Headquarters Title) !

J a

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Enclosures:

i

' Reference Material P quirements

1. !

l

2. Administration of Requalification \

Examinations

3. NRC Rules and Guidance for l Ex aminees DISTRIBUTION:

Project Manager Branch Chief, OLB Examiner (s)

Facility Training Coordinator f acility Operations Manager i

)

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09/01/91

- s Attachment 1 (Continued)

ENCLOSURE 1- 1 I

REFERENCE MATERIALS AND TEST ITEMS l i

-i The following items are needed by the NRC 60 days prior to the examination date. ;

1. Written exanination test items meeting the following criteria:

a. Items should require that the examinee comprehend, interpret, integrate or apply information.

b. Items should be appropriate to the f acility, clear, and important to s af ety.

c. At least 50% objective test items.

' The written examination will be composed of three separate sections, each designed to be completed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Section A evaluates the operator's ,

knowledge of f acility' theory, thermodynamics, and operating characteristics.

Section B evaluates normal and emergency procedures and radiation control.

Section C evaluates f acility systems and radiation monitoring systems.

2. Operating examination test criteria:

A list of the systems and procedural duties applicable to safe operation developed per paragraph D.1.b.1.a. in ES .

i r

The tasks selected for performance with evaluation criteria, developed per paragraph D.I.b.1.b. in ES .

The questions ano answers associated with the selected tasks.

Reference material associated with the above.

3. Any additional reference material required for examination preparation {

requested by the examination team.

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09/01/91 Attachment 1 (Continued)

ENCLOSURE 2 ADMINISTRATION OF REQUALIFICATION EXAMINATIONS

1. Nominees for the NRC Requalification Examination will be submitted by the f acility. Normally individuals currently in the requalification cycle will be selected.

2. A f acility representative may be made available for examination development. The date(s.) and duration of time needed to develop the examinations will be agreed upon by the chief examiner and the f acility. ,

3. The reference material used in the operating examination will be reviewed by the chief examiner.

4. A single room shall be provided for completing the written examination.

1 The location of this room and supporting rest room f acilities shall be such as to prevent contact with all other f acility personnel during the duration of the examination.

5. Minimua spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one examinee per table, with a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination room.

6. Since concon tasks and detailed systems knowledge may be probed during the operating test, operators will be requested not to discuss the operating test with other examinees until after the complete examination has been administered.

7. The operating test is expected to distinguish between R0 and SR0 knowledge and abilities to the extent that such a distinction is supported by the f acility training materials.

1 24 of 31

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. ' Attachnent 1 (Continued)

ENCLOSURE 3 NRC RULES AND GUIDANCE FOR EXAMINEES

1. Use black ink or dark pencil ONLY to facilitate legible reproductions.

2. Print your name in the blank provided on the cover sheet of the examination.

3. Fill in the date on the cover sheet of the examination, if necessary.

4. Answer each question en the exanination.

5. Use abbreviations only if they are commonly used in f acility literature.

6. The point value for each question is indicated in parentheses after the question.

7. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.

8. Unless solicited, the location of reference need not be stated.

9. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.

10. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.

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11. Rest room trips are to be limited and only one examinee at a time may leave.

You must avoid all contact with anyone outside the examination room to 2

avoid even the appearance or possibility of examination compromise.

12. Cheating on the examination would result in a revocation of your license and could result in noce severe penalties.

13 . Each section of the examination is designed to take approximately 60 minutes f to compl ete. You will be given 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to complete the examination.

14. When you are finished and have turned in your completed examination, leave the examination area.

l

15. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is

worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth ,

0.20 points. If one of your five responses is incorrect, 0.20.will be deducted and your total credit for that question will be 0.80 instead of ,

1.00 even though you got the four correct answers.

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26 of 31

-ES-606

'. . 09/01/91 j ATTACHMENT 2 e j PRE-EXAMINATION SECURITY AGREEMENT !

1

-I agree that I will not knowingly divulge any information ,

Print Name i

concerning the requalification examination for to any unauthorized persons.

I

/

Signature /Date f

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27 of 31 I

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'. '.- 09/01/91 ATTACHMENT 3 POST EXAMINATION SECURITY AGREEMENT i I did not, to the best of my knowledge, divulge any '

Print Name ,

information concerning the examination administered on to any unauthorized persons. .

I Signature /Date t

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28 of 31 1

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4 ES-606

09/01/91 ATTACHMENT 4 k

BRIEFING. CHECKLIST-OPERATING TEST TASKS

1. If the NRC examiner is a visitor, escort responsibility for ensuring compliance with safety, security and radiation protection procedures is the responsibility of the operator escorting the examiner.

2. Facility equionent should not be operated unless specifically allowed by procedure, management direction, standing order, routine operating proce-dures or other ad'ninistrative allowances. If equipment cperation is speci-fically prohibited, nothing the f acility or NRC examiner says or asks will be intended to violate that principle.

3. If clarification of questions is needed during the walk-through, there should be no hesitation to request the examiner reword or clarify the q ues ti on.

1

4. The examinee will be taking notes througnout the: test to document operator performance. Frequently an examiner will stop questioning for this purpose.

The amount of note-taking is not dependent upon the operator's level of performance. The examiner must document satisf actory as well as less than satisf actory performance.

5. The operating task is consioered "open reference." The reference material in the facility / control ecom which it normally available to operators is available, including calibration cc- , previous log entries, piping and instrumentation diagrams, calculation sheets, and procedures. However, operators are responsible for knowing from memory .5e inmediate actions of emergency and other procedures as appropriate to the f acility.

6. The operating test has been planned for approximately 90 minutes in length.

However, there is no specific time limit. The examiner will take whatever time is necessary to cover the areas selected, in the depth and scope required. There will be a minimum of 5 tasks evaluated.

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7. The examiner will explain what tasks are to be completed, which steps to simulate or discuss and provide initial conditions. The operator is to proceed with completing the task as if directed by plant procedures and/or shift supervision. During the task the examiner ~ will supply the necessary plant conditions and/or parameters needed to simulate the task. The opera-tur should explain each step of the task to the examiner before doing it.

B. The examiner is not allowed to reveal the results of the examination at its conclusion. ;

9. Th e NRC examiner may ask clarifying questions of the operator at the end of each task. To the extent possible and reasonable these questions will ,

be asked via the f acility evaluator.

)

10. The NRC examiner will indicate to the operator that no aspects of his exar.ination should be discussed with any other examinees until the conclusion of the examination.

) 11. The operator may request a break at any time during the operating test.

30 of 31

L ES-606

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ATTACHMENT 5 s ,

REQUALI ' CATION RESULTS

SUMMARY

SHEET !

(To Be Developed) 1 31 of 31 :

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I APPENDIX III f NRC INSPECTION MANUAL l Inspection Procedure 40750 ,

Dated: 08/07/92 I I

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- I narcy p' 'o UNITED STATES NUCLEAR REGULATORY COMMISSION JS ,f m sm ucrou.o.c.:csss

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NRC INSPECTION MANUAL PoNP INSPECTION PROCEDURE 40750 CLASS II NON-POWER REACTORS PROGRAM APPLICABILITY: 2545 40750-01 INSPECTION OBJECTIVE To detennine if activities- at Class II non-power reactors were conducted safely ;

and in accordance with regulatory requirements _ and commitments, since the last inspection. ,

i 40750-02 INSPECTION REQUIREMENTS 02.01 Orcanization and Staffino Determine if changes in the licensee's organiza-

a. Orcanizational Chances.

tion meet technical specifications (TS) requirements, and licensee comitments.

b. Shift Staffino. Determine if the minimum shift staffing composition for operation, including on-call personnel, is as described in the TS.

02.02 Operations locs and Records ;

a. Determine if operation logs and records are maintained as required by the ,

t licensee's administrative procedures. ;

b. Determine if significant problems and events identified by review of the operations logs and records are reported, and resolved in accordance with the requirements in the TS and the licensee's administrative procedures.

c. Determine if the measured parameters for one TS-required recorder meet TS requirements.

02.03 Procedures I

a. Administrative Controls. Determine if the licensee's administrative control procedures are consistent with TS, license requirements, and licensee comitments.

40750 l Issue Date: 08/07/92 !

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Determine if the procedures for use by the operator [

b. Current Procedures are reviewed and approved, and are the latest revision in accordance with l the requirements of the licensee administrative control procedures. , .

'l '

c. Procedural Imolementation. Determine if TS required procedures can perform the required function. i Procedural Adherence.

Determine if reactor personnel are observing -

d.

administrative control procedural and TS requirements on adhering to i procedures. l i

02.04. Recualification Trainina e

a. Determine if the requalification records for licensed operators are maintained as required by the requalification plan. .

b. Determine if the licensee completes the required actions for any disqualified individual not meeting the requirements of 10 CFR 55.53 (e) <

or the requalification plan. !

c. Determine-if the licensee implements the following items, consistent with -

the Office of Nuclear Reactor Regulation (NRR) approved Requalification Plan:

f and reviews ~ changes ~. ~in the facility, ' procedures, and l' . " Discusses '

l license. ;

2. Reviews and simulates abnormal and emergency procedures. !

3. Assures the operators maintain an active duty status in accordance -!

with 10 CFR Part 55.53(e). :

i Conducts formal training, e.g., lectures, and seminars.

j 4.

02.05. Surveillance and t.initino Conditions for Ooeration i

a. Determine if surveillances meet the TS surveillance requirements and are l acceptably conducted for the as-built condition of the facility.

b. Determine if Limiting Conditions of Operation (LCOs) are maintained in accordance with the licensee's procedural requirements.

02.06 Experiments

a. Determine if the licensee reviews and approves experiments and any l subsequent changes in accordance with the requirements in the T5 and the

~

licensee's procedures. .

l

b. Determine if the experiments represent an unreviewed safety question or. ,

require a TS change as delineated in 10 CFR 50.59. ,

q

c. Determine if the licensee identifies hazards that could be associated with experiments and remedial action in accordance with the licensee's i procedures.

d. Determine if the licensee accounts for and controls irradiated items as i required by the regulations and licensee procedures.

Issue Date: 08/07/92 40750

i e.

Determine if experiments are constrained as required by the TS and the l licensee's procedures.

_s Determine if experiments are installed in the reactor a'nd removed' from f.

the reactor in accordance with experiment authorizations and protocols as required by the licensee's procedures. ?

are evaluated, and reactivity worth of experiments ;

g. Determine verified byifmeasurements the in accordance with the TS _ and .the licenseeo ,

procedures. ,

h.

Determine if the licensee installs engineering _ controls to limit ,

radiation exposures, as required by the applicable experiment protoco and authorization, procedures and TS. ,

s 02.07 Health Physics _

f a.

Determine if the exposure limits in 10 CFR Part 20 were satisfied.

sampling, and monitoring are i

b. Determine if required radiation survey, performed in accordance with the regulatory requirements and the! i licensee's procedures. t

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c. Determine if required calibration of radiological survey, sa=pling, or monitoring instruments are in accordance with .the. TS .and the. licens e procedures.

d.

Determine if required personnel dosimetry program is conducted in accordance with licensee procedures and 10 CFR 20.202. -

l

e. Determine if the licensee satisfies the requirements for radiolog ;

effluent releases in 10 CFR 20.106, 30 i and the TS. ,

f. Determine if the use and calibration for instruments CFR 20.106, the TS, and the licensee's procedures.

g.

Determine if notices to workers are posted in accordance with 10 CFR .

I 19.11 and the licensee's procedural requirements. ,

b.

Determine if restricted areas as defined in 10 CFR 20.3 are posted inj accordance with the requirements in 10 CFR 20.203 and 20.204, and '

' licensee's procedures. i i.

Determine if appropriate protective clothing is used in accordance w ,

the licensee's procedural requirements. i f

j.

Determine if personnel working around radioac CFR 19.12.

k. Determine if the principles of As Low As Reasonably Achievable (ALR i

implemented by the licensee.

1.

Determine if the licensees Radiation Safety Officer (ori equivalent) t reviewed and approved radiation protection program' in changes, accordance exper m and radiation protection related events and conditions, i 40750 Issue Date: 08/07/92 ;

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with licensee procedures and the TS.

02.08 Desion Chances a.

Determine if the design changes were reviewed and i approveddures.in accordan with 10 CFR 50.59, the TS, and the licensee's administrat ve proce meets regulatory if the performance of modified equipment

b. Determine requirements, licensee commitments, and procedural requirements.

icensee reviews and approves procedures related to the ;

c. Determine if themodified system in accordance with the TS and the licens:l

d. Determine if the licensee changes as-built draw t change package. ,

02.09 Committees. Audits and Reviews _

l a.

Determine if the safety review committee met in accordance with the T l 5

- requirements.

b.

Determine if independent audits are conducted in accordance with thell

'r'equirements and'the licensee's procedures. l

c. - Determine if identified problems from the licensee's required reviews ar ;

resolved in accordance with the TS requirements 3

procedures. P 02.10 Emercency Plannino i a.

Determine if procedures required by the emergency plan are current -

readily available to users as required by the plan.

b.

Determine if the licensee conducts exercises and drills as required b ;

l the emergency plan. t r

if ' the licensee conducts training for emergency response !

c. Determine personnel in accordance with the emergency plan.

d. Determine if key emergency response personnl l ing procedures. 1 02.11 Maintenance loos and Records ;

a.

Determine if maintenance logs and records are maintained as requir ,

the licensee's administrative procedures.

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b. Determine if significant problems and events idl with the requirements in the TS and the licensee's administrative

-t procedures. ;

if maintenance is performed consistent with the TS and the l

c. Determine ;

licensee's procedures that govern maintenance activities.

08/07/92 i 4- Issue Date:

40750 ,

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Determine if the fuel handling logs 02.12 Fuel Handlino Loos and Records.

satisfy the requirements in the T5 and the licensee's procedures.

40750-03 INSPECTION GUIDANCE General Guidance. If practical, the inspector shoulb use direct observation of activities to meet the inspection requirements of this inspection procedure, :

otherwise a combination of simplified measurements, wal k-throughs,Also, recordsif ;

review, or discussions with licensee personnel should be used.

practical before inspecting a non-power reactor, otherwise 'during the onsite inspection, the inspector should review the license, the TS, the Safety Analysis ,

Report (SAR), the as-built descriptionThese of thedocuments facility, the maySafety referenceEvaluation standards ;

Report (SER), and licensee ccanitments. i of the American Nuclear Society (ANS) and the American National Standards l Institute (ANSI), and the regulatory guides. The Appendices lists the regulatory !

guidance for non-power reactors.

guides and standards that provide generalAdditional general guidancel Possible Interest to Division 2 Recipients" listed as an attachment to the

~

The reference to the standards i Division 2 Regulatory Guides Table of Contents. !

and guides in the appendices is to provide additional general guidance toThe aid the !

technical evaluation of the licensee's activities. !

inspector in..theinspector should not use these standards and guides as commitme!

ments unless the licensee;has co=nitted or the NRC has required the licensee in writing to use the specific guidance document.

I l

Additionally, many requirements are specified in licensee written procedures. ;

There may be conditions where licensee procedures are informal and appear toInbe

- inadequate for the task, or where written procedures simply do not exist. :

these instances, the inspector should, as generally directed throughout this l inspection procedure, continue to verify licensee activities through perfol based inspection observations. .

and per the requirements, regardless of the formality or If quality of their written the licensee is not procedures, the inspector should find this acceptable. i performing the function safely and in accordance with the requirements because ,

of inadequate or non-existent written procedures, the inspector should raise _the issue with appropriate regional management and the NRR project manager to ;

establish an action plan to address the concern.

The sample sizes and resource estimates suggested in the inspection procedure is f provided for broad planning purposes and to define the typical depth of the !

inspection. It is not intended to be a rigid requirement on the inspector. !

Actual inspection at any facility may require more or less effort depending sianificance.on .

past inspection history, conditions at the facility, and safety f

The inspector should, as a matter of course, conduct a facility tour accompanied l early in the inspection. This tour should include l by licensee managementconsideration of plant activities and conditions, with particular radiation protection.

Soecific Guidance i 03.01 Oraanization and Staffino

' During the inspection, the licensee's organiza- f

a. Orcanizational Chances. j tional or administrative records should be reviewed with cognizant staff t i and management to detemine if changes were made to the licensee's organization. Only changes since the last inspection need be reviewed. i 40750 08/07/92 Issue Date:

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If changes have been made, particular attention should be -given to (2)(1) organizational structure, reporting chains and lines of s I ity of key personnel and (4) assignment andorganization qualifications of new should be All changes to the licensee *s personnel. consistent with the TS and the SAR, and supporting documentation. i

b. Shift Staffino. Where If the practical, the inspector should observe staffing facility is shut down, examine the records on two shifts.

associated with two startup operations to verify that the licensee had The TS provide the require-satisfied the TS requirements for staffing.The records and guidance provided to -

ments for this item.

should clearly indicate the specific personnel required at the facility for operations (such as a licensed operator and another individual toThe record i

contact appropriate personnel in an emergency).

provided to the operator should also clearly indicate Having required on-call both a personnel such as a licensed Senior Reactor Operator.

licensed reactor operator and licensed senior reactor operator at the ,

facility generally satisfies the requirements for operations, onsite, and on-call personnel. i Selected operations logs and records should 03.02 Operations loas and Records, be reviewed.

a. A' review of about 50 pe'rcent of the operational logs and records, and 10 - :

percent of the pre-startuo and startup checklists and records, should The review .

~ provide an acceptable sample for this inspection requirement.after the previous -

of logs and records from several time intervals inspection. should be performed to identify if there were problems that have not been identified elsewhere.

1

b. This inspection requirement should include examination of the licensee's evaluation of the cause and implementation of the corrective . actions prior to returning the reactor to power for all unplanned reactor scratsPro since the last inspection. Credit in this area may be taken with licensee procedural requirements.

to satisfy the requirements in the review and audit portion of this '

inspection procedure.

c. Examining the records of one TS-required recorder for the two most recent times the reactor was taken critical should provide an acceptable sample for this inspection requirement. If possible, vary the selected At some facilities, only a few .

parameters from the previous inspection. facilities, only a few TS pai not be varied. If the parameters can not be varied, the same parameters should be observed.

Examples of the type of parameters include nuclear power and primary system temperature instrumentation.

f 03.03 Procedures. Required procedures are specified in TS or licensee ,

administrative procedures.

l The administrative control procedures should be

a. Administrative Controls. l reviewed. The requirements for administrative controls may be found in Licensee commitments may be ,

the facility-specific TS and the license. The licensee's found in the SAR, SER, and supporting documentation. l administrative procedures may include, but are not limited to, the following:

)

J Issue Date: 08/07/92 40750

1.

Operator Responsibilities. The. responsibilities listed below should be addressed- in the licensee's administrative procedures or guidance.

i (a) The operator's and senior operator's responsibility to use written procedures. The TS may require that the licensee radioactive provide written procedures for malfunctions, releases and contaminations, and emergencies. Further, the TS may require that operators use these procedures.

e (b)

The operator's and senior operator's responsibility to adhere ,

to the TS. ,

The logging of operating information, including description of (c) log item, date, time and identification of the individual logging the information.

(d) The method of shift turnover. '

The operator's responsibility to shut down the reactor when it (e) is . felt that.the safety of the reactor is in.. jeopardy. l l

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return the reactor to ,

(f) ~ The operator's responsibility to not power following a scram or unexplained.. power reduction without ;

the' presence and direction cf the senior operator (10 CFR 50.54 (1) and (m)(1)). ;

-)

(g) The senior operator's responsibility to determine the circum- ;

stances, analyze the cause, and correct the fault, before l directing the return of the reactor to power after a scram or unexpl.ained power reduction in accordance with the licensee's procedures.

(h) The' operator's responsibility to believe instrument indications until the indications proven to be incorrect.

(i) The operator's responsibility to shut down the reactor if the control system does not automatically shut down the reactor

when operating parameters exceed the reactor protection set ,

points. l

2. Review and Acoroval Recuirements.

If the .TS or the licensee's '

administrative procedures do not describe the requirements for i review and approval of procedures, the following method is one of j several acceptable alternatives. Before granting final approval, the licensee should review sequentially and walk-through the steps in new procedures and in significant revisions in existing proce- ;

dures, to test the effectiveness of the procedure to control the -

Persons representing applicable disciplines such as operation. nuclear engineering, health physics, instrumen'tation, or electrical engineering should concur in procedures after perfoming a detailed i review in their areas of specialty (This may simply be the review'

. and approval by the safety review comittee and reactor supervisor.)

The safety review comittee should review the procedure, and .the minutes of the review committee meetings should verify that procedures have been reviewed. Each procedure should be approved by an appropriate member of the facility management,The usually the approval facility director or other designated person.

40750 Issue Date: 08/07/92

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signature and issue date should appear on the procedure.

Licensee procedures should contain i 3. Temocrarv Chances to Procedures. and updating procedures when provisions for chancing, revising, deficiencies or discrepancies become apparent while the reactor is operating. If the TS or the licensee's administrative procedures do not describe tne requirenents, the following provides The supervisor an acceptable may example of a way to make changes to procedures.

make changes that do not change the intent of the original proce- ,

dure if the supervisor is a licensed senior operator and if a note l of the change, listing the date and the authorizing personnel, is The operators l recorded in the operating log or procedures manual.The change should should be informed of the change.

the review committee and approved by the facility director, Theorchange other designated person at the earliest convenient time.

should then, in accordance with licensee procedures, be made i

" permanent through this review and approval process or. deleted when l it is no longer necessary.

b. Current procedures. The review of two procedures should provide an ,

Procedures should be reviewed on acceptable a rotating basis. sample for this inspection.Once a procedure .is found acceptable, lio

~

The procedures that should to be checked include These l should be reviewed. '

.those . for system chackouts, startup, operation, and shutdown.

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procedures' should be currsnt and up to'date.-

The inspector should observe the licensee's The

c. Procedure Imolementation.

l personnel conduct the . activities for one TS required procedure.

inspector should consider the observation of a proced The procedure reactor shutdown to satisfy this inspection requirement.shou the design characteristics and safety review considerations. To evaluate the procedure, the inspector should use the the TS (

ings), and the as-built systems drawings or descriptions design change and maintenance drawings and descriptions if they differ from the SAR descriptions). The inspector should concentrate on the review of major systems and components and their appropriate in-Items such as complete valve lineups need not be

' terlock features. If it is not possible to observe the procedure being conducted verified.

by operators, then an adequate functional check could includeThis reviewing selected steps for the as built condition of the facility.

inspection activity should determine if the operation can be safely accomplished using the procedure as a guide.

The inspector should try to make sure that this inspection does not distract the operator from their duties.

Procedural Adherence.

Operators need not have procedures in hand d.

l depending, on the complexity of the procedure and the familiarity of the operator. Additional guidance may be found in J

42745, " Class I Non-Power Reactor Procedures."

)

03.04 Recualification Trainino. The licensee's records should be sufficient to verify compliance with the licensee's NRR-approved permit the inspector to j

recualification program, and to evaluate the technical adequacy of examinat that have been administered by the licensee.

Issue Date: 08/07/92 an7cn

+ . - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 contents of the written examinations taken by. licensed operators and management'sThe evaluations of the operator's performance. cover areas recuired by the requalification germane program, to the specific reactor,and demonstrate that the operator has the knowledge ~ to continu safely operate the reactor facility. The inspector should discuss with licensee management their evaluations of operators which may simply be observation of startup, operations or shutdown with commensurate discussions with the operator.

These evaluations should also be verified by licensee records.

If the inspector has questions on the technical adequacy or implementation of the requalification program, the questions should be resolved with appropriate If necessary, NRR regional management, and the responsible HRR project manager.

technical branches, Human Factors Assessment Branch (LHFB) and Operator Licensing Branch (LOLB), may be requested to provide assistance in the reso questions.

programs.

The LOLB has the responsibility for administering NRC requalification Resolution of these questions could included and initial operator examinations.

the reexamination of an individual licensed operator, or a re-review of an area of concern or the entire requalification program.

a. A review of-the records for 50 percent of the. licensed operators should The provide an acceptable. sample for this inspection requirement.

licensee should maintain records in accordance with the requirements of the requalification plan and associated administrative control-s.

10 CFR 55.53 (f) to requalify licensed

b. Requirements are specified in I operators after disqualification for not maintaining Additional active duty status requirements for in accordance with 10beCFR 55.53 (e).

specified in the requalification plan. to The ;

requalification may and is required licensee may report to the NRC disqualifications The licensee should report medical disqualifications by 10 CFR 55.25.

have implemented any corrective actions specified in these reports.

Reasons for operator disqualification may include:

1. They were inactive as defined in 10 CFR 55.53 (e).

2. They received an unsatisfactory rating in a supervisor's evaluation.

3. They failed an annual examination.

4. They failed to meet medical requirements.

should provide an

c. A review for 50 percent of the licensed operatorsThe licensee should acceptable sample for this inspection requirement.

conduct the requalification activities Theininspectoraccordanceshouldwithbethealert NRR-for approved requalification program. areas in which, or individuals for whom, training in accordance with the requalification program or the licensee's administrative control requirements.

The specific param-03.05 Surveillmce and Limitina condition for Operation.

eters verified should be varied from the last insoection.

a. Observations of three TS required surveillance activities Anyshould design provide changes an acceptable sample for this inspection requirement. ii should be reflected in licensee surveillance activ t es.

40750 08/07/92 Issue Date:

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4 b.

Those values or conditions that have a definite bearing on safety, although they are specified or assumed by the These T5 and couldhave includeno assigned surveill ance frequency, should be verified.

parameters such as required air flow for the argon-41 exhaust system.

Observations of one T5 LCO or design condition should provide an l s

acceptable sample for this inspection requirement.

Surveillance is the verification of set points This and aconditions includes wide variety required of set by the TS i both on a regular and e.g., irregular basis.

reactivity measurements that may be required once points and conditions, kly, and ;

or twice a year, certain conductivity checks that may be required weeAlthough som:

interlocks that must be checked before startup.

surveillance frequencies established in more recent For such olderTS, TS, some if a needolderis T5 may n

~

have requirements for surveillance frequency. i established for specification of a surveillance requirement, such as determin n that a safety significant value or condition has a significant potential to not be satisfied because of inadequate surveillance, '

project manager. r The licensee should conduct all surveillance items. associated with safet:

systems requirements.

or components in accordance with the licensee's l dures..

In those cases, ' the inspector should consider the need . for such ,

requirements based on the 'results'of performance For example, if personnel based' do nothinspection-obs have in the conduct of this inspection. by procedures, they may calculate rod worth by the positive period method, t je :

the rod drop method, and then by the 1/M method'.results for the same rod. This wide

' could produce different, widely disparate variation would make the worth measurements meaningless because d the val ,

result in a uniform basis for determining that core conditions had not change . '

Thus, finding inconsistent results that do not meet the intent of a requireme ,

l may establish the need for specific procedures. raised to appropria :

NRR project manager. !

The inspector should review various chart recorder records Charts and logs for th of the surveillance to verify that they support the surveillance results.Often rec i should be marked regularly with date and time. Avoid looking for small errors in the record l

making it difficult to be precise.of time; instead, assure that the record can f

The surveillances should verify the design characteristics and the safety re For example, nuclear instrument power calibration ont l

considerations are met.

most non-power reactors is simply a verification that safety assumption of 110 percent power for initiation of assumptions have been exceeded, i.e.,

transients. If the licensee determines that nuclear instrument calibratio incorrect but the safety assumptions were still satisfied, the safety signifi -

The descriptions in the TS, LCD, SAR, includ'ing plan and cance would be minimum.

instrument drawings, and applicable as-built system descript during this evaluation. features for important safety features should be examine I

)

The appropriate individuals as designated in the licensee's administrative controls should verify satisfactory completion of the surveillance requirement For example, college students may perform some of the reactivity measuremen i class projects, and before accepting these results, the licensee should rev e Issue Date: 08/07/92

'^'en

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4, ,

and approve them in accordance with procedural requirements.

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'03.06 Exoeriments. The observation of 50 percent of the new experiments that ;

have been approved since the last inspection should provide an acceptable sample j

for this inspection requirement. - .l ,

The j

a. Meeting minutes for the safety review committee should be reviewed. ;

safety review committee should have reviewed each experiment or class of i experiment prior to conduct. The need for specific experiment review If ;

depends on the degree of complexity and safety significance. l' additional guidance is needed the inspector should see Inspection Procedure 69745, " Class I Non-Power Reactor Experiments." ,

b. If additional guidance is needed, see Inspection Procedure 69745, " Class j I Non-Power Reactor Experiments" and NRC Inspection Manual 9900 directive 1 on " Changes to Facilities, Procedures and Tests (or Experiments)" for 10 ,

CFR 50.59.

c. The guidance for this inspection requirement may be found in applicable :

sections of Inspection Procedure 69745, " Class I Non-Power Reactor ,

Experiments." !

d. The licensee should control irradiated items until they were disposed of l or they decayed 'to' an acceptable level in accordance with their proce-dures and 10 CFR 20,' or until they arr acceptably-transferred to:another another license. Additional guidance for this inspection requirement may l

, be found in applicable sections of Inspection Procedure 69745, " Class I Non-Power Reactor Experiments."

e. Operators should be provided guidance on any unusual hazards associated with the experiment, and methods for identifying and responding to them. ,

f.

The movement of the experiment 'should be consistent with the level of ;

radioactivity and will further depend on the qualifications of the individuals handling the items.

g. If the regulating rod position has not substantially changed with an .

experiment inserted, then this Ifisananexperiment adequate reactivity check for most has an unexpected large ;

near ::ero worth experiments. For example, the l it.

worth, the operator should be able to detect !

operator should have a conservative cutoff point of regulating rod ,

movement or power level change, so that the value is actuallyThis calculated should l from information that is readily available to the operator.

effectively assure that constraint limits, shutdown margin, excess l reactivity, and individual and total worth of experiments are controlled as required by TS. i l

h. Any engineering controls for experiments, such as temporary shielding, i time, distance, or remote handling devices, should effectively limit '

occupational exposures to the levels required by 10 CFR Part 20, and the licensee's ;

including as low as reasonably achievable (ALARA), Access to areas wh administrative limits. and ,

be posted in accordance with the 10 CFR Parts 20.203 and 20.204 j

should be limited as required by licensee radiation protection program. ,

l

- ' Special attention should be given to experiments that involved the use of j neutron beam ports, if there is a reasonable potential for radiation dose to i to a major part of the body including gonads and lens of the eye, :

ensure that controls are established that satisfy 10 CFR Part 20.203 (c) !

40750 l Issue Date: 08/07/92 I l

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1 l

requirements.

If additional guidance is needed, refer to applicable " Inspection Guidance" in Inspection Procedure 69745.

l This section provides guidance for the health physics 'l 03.07 Health Physics. It is not to be used for the ;

inspection at Cl ass II non-power reactors.

inspection of other material If there licenses, are concernsincluding on otherthose such of the NRC licenses, the and if i applicable the State. inspector should infom appropriate regional managemen ;

' of action.

records to facility -

a. The review of about 50 percent of the exposure i personnel (e.g., TLD or film badge records) since the last inspection 10 i j should provide an acceptable sample for this inspection requirement. l j CFR 20.101 provides the occupational dose standards for individuals in :

~

10 CFR 20.103 and Appendix B to 10 CFR 20 Table I l restricted areas.

3 Column I provides requirements for' exposure of individuals to10concentra- CFR t

tions of airborne radioactive materials in restricted area ;

i

) j Requirements and co=mitments for this inspection are inc

b. :

SAR, and SER. .10 CFR Parts 20.103 and The !

~

maintained in accordance with 10 CFR 20.401. implementation' 20.201 providEs the requir !

inspector should observe licensee personnel conduct or the inspector 7 should perform radiological surveys of one or two of the potent' higher radiation dose areas. include those around

~

beam ports, thermal colu where

, and ion exchangers for cleanup of primary water, Current ongoing radiation measurements should be compared with a recen completed surveys, sampling, or monitoring in the same area to verify that both meet These the recuirements measurements shouldof thereasonable show licensee's administra agreement a.

l and 10 CFR Part 20.

with those in the licensee's records, or the licensee should have The inspector explanation for the difference.

reasonable technical surveys of solid waste material and should use l should also examineInformation8511270325),Notice 85-92, as "guidance.

SurveysIfofactual Wastes Beforl I

Reactor Facilities," (Accession No.the review of three radiation survey, observations can not be made, samples or monitoring activities may also provide an acceptable sam for this inspection requirement. !

c. The review of about 50 percent of the instruments ,

licensee's radiological control programANSI should provide" Radiation N323-1978, an acceptable l sample for this inspection requirement.

and Calibration" provides additional l' Protection Instrumentation TestThe inventory of radiation measurement instru-guidance in this area. appropriate to the types and ments should have current calibrations The licensee should be calibrating i

energies of radiation to be detected.and maintaining this equipmi dations.

f l The inspector should determine whether facility personnel have been i

Normally, d.

issued appropriate dosimetry and are wearingincludes it as required.

provisions for j the licensee's personnel monitoring program ,

Issue Date: 08/07/92 l 40750

The monitoring monitoring beta, gamma, and fast and slow neutrons.

devices include, but are not limited to, film or TLD whole body badges and, where appropriate, extremity badges and direct and indirect reading If the licensee performs their own process-

- >I pocket ionization chambers.

ing of personnel dosimeters, the inspector should review these activities for required measurements. Regardless of who performs the processing of personnel monitoring devices, it is required to satisfy the requirements ;

of 10 CFR 20.202.c. i

e. The review of one record each for gaseous and liquid effluent releases to i the environment should provide an acceptable sample for this inspection l requirement. The licensee's records should show compliance .with applicable conditional release limits in 10 CFR 20 Appendix B, the TS, or the license. The licensee may have been authorized by TS or license condition to release concentrations above the limits in Appendix B to 10 CFR 20.

f f.

The above review of one gaseous and one liquid effluent release, plus the ,

verification of location and calibration for one monitoring instrument The should provide an acceptable sample for this inspection requirement. ;

licensee may use on-line monitoring- or grab. sampling in.accordance The licensee's with procedures !

requirements to monitor effluent releases. i should provide a calibration frequency for effluent monitoring instrumen-tation and should- provide a schedule for maintenance consistent with -i manufacturer recommeiidations. All instrumentation'should be calibrated - !

and maintained as required. Argon-41 is normally the most common gaseous :

effluent and the monitoring instrumentation should be calibrated and '

verified to be accurate for this energy in accordance with the general l guidance in ANSI /ANS-15.11. Liquid effluent releases are usually reactor l dependent and can include isotopes of aluminum and silver, as well as, l isotopes of cobalt and iron. Analysis of liquid effluent releases should be able to detect such isotopes that are expected for the specific reactor. :

g. No guidance needed.

l

h. Areas which should be posted include radiation areas, high radiation f areas, areas where radioactive materials are used, areas where there is In addition, airborne contamination,' and general access control areas. i if the licensee has sealed sources or devices that produce ionizing '

radiation under the reactor license, these should be posted as well.

licensee should provide guidance for protective clothing in the l

i. The f procedur es or on precautions posted at the entrance to controlled areas. is not l See 10 CFR 19.12. Such protective clothing may include, but ;

limited to, gloves, booties, lab coats, coveralls, and plastic or rubber aprons for use with liquids. ,

j. Particular attention should be given to experimenters, including college students, who may not be familiar with radiation control techniques related to their experiment or project. The licenseeThis should assure may include

acceptable instruction and control of their activities.and testing, where i

" dry runs", demonstrations, formal lectures, films,It should also include training on i required by the licensee procedures. " Instructions Concerning ;

the provisions of Regul atory Guide 8.13 !

Prenatal Radiation Exposure. See 10 CFR 19.12.

k. The inspector should discuss with licensee management considerations that 40750 Issue Date: 08/07/92 e-- + - -- - - - m -e -w--- r-- - - ' - w ur

L T .

l have been taken to reduce radiological dose for a specific activity whic ;

provides a significant contribution See to the personnel, public 10 CFR 20.l(c).

l mental dose. ,

experiment section of this inspection procedure.

i

1. Selected discussions with the Radiation Safety l l

sample for this inspection requirement. involved and aware of th l and effects radiation protection activities. i !

only the radiation protection program,audit occurrences, but also the review findings, of exper -

committee i incidents, unusual The RSO should l ments, !

activities, and radiation protection procedurechang'es.

have independent responsibilities and lines of com ;

requirements. ;

The inspector should conduct a general review of the l 03.08 Desian Chances. l design changes since orthe last public safetyinspection

.in another manner.to determ_

safety '~ analyses or effect personnel Additional ~ guidance.may be found in 10n view CFR 50.

20 CFR.50.59, and.in. Inspection Procedure 40745 " Class I Non-Power i and Audit, and Design Change Functions.' ;

l

a. ~ Any facility change or modification which will re]

' and approved by NRR before making the change.

b. The requirements for testing should be in the licensee's design change package, and may require acceptance and preope The test records should ;

requirements in the SAR, SER, and the TS.

provide evidence of approval and acceptance by the appropriate as required by respective licensee procedures. )

maintenance, surveillance testing and

c. Changes may involve operating,The licensee should assure that the procedures radiological procedures.

for the revised system can continue to be used to pe function.

l design change to verify it can be used to perfom its intended function.

This may use the guidance and can be substituted for one of the proce- !

dures reviewed for Inspection Requirement 02.03.c. I l

d. Prepared sketches or engineering drawings used to perfom design ,

modifications should be compared with the actual system co ;

the updated as-built drawings.

accordante with licensee procedural requirements.

f The requirements for comittee's should 03.09 Committees. Audits and Reviews.The T5 at older facilities may not requi be in the TS. Where audits and reviews are required, the inspector should review the reviews. In some

, i associated reports to verify that they have been co idance because of the limited size of' the staff. assure that the selected in to perform a critical review of the functions examined in Issue Date: 08/07/92 an7en I i

.. =~. . ._. ._. .- - _ - - - ..

licensee procedures. The inspector should pay particular attention to committee.

actions and recommendations on audits and facility events, and Thisthe related inspection follow-up actions by the committee and line management.

requirement is to determine if the licensee's committee, audit that andis, has review the processes assure that license and TS requirements are met, licen regulatory requirements are satisfied.

l

a. The observation of a safety review committee meeting or the review of 50 l percent of the - safety review committee meeting minutes since thelast acceptable sample for this inspection inspections should provide an !

requirement. Rcquirements for meetings should be in the administrative l The safety review group or committee should be technical-section of TS. !

ly competent and should review and approve all significant activities, '

including procedures and changes to procedures, designmay The committee changesreviewand and !

experiments that may involve 10 CFR 50.59.

approve collectively all repetitive experiments that , share safety considerations.

Controls for visitor access to the reactor facility for !

the purpose of performing experiments should be reviewed by the commit-tee.

Training for the qualifications for personnel who will perform r safety functions at the reactor facility should also be reviewed by the >

committee. If the functionsor designof thechange review committee sections ofwere reviewed in' the this inspection l procedure, ~ experiment !

procedure, this review need not be repeated here.

The review of two audit reports should provide an acceptable sample for

b. Audit recuirements are generally in the j

, this inspection requirement. administrative controls section of the TS, and the; These requirements may include audit checklists and plans to assure that l license and TS recuirements are satisfied.

uniform and may not be l However, the requirements for audits are not

specified in the TS or the licensee's If a safetyadministrative or non-compliance controls, issue particu-raises ,

larly at older facilities.the need for NRC recuired audits, the inspector This should regional management and NRR project manager to resolve the issue. l resolution process should strongly consider indicating to the licensee that other licensees have cooperated in peer reviews to evaluate their programs, and that this may be useful for this licensee.

j If the licensee's audit function is identifying and resolving problems, .

the inspector should recognize this point with licensee management, and I the inspector should assure that the inspection activity does not stifle a functional audit system. For example, even if the audit identifies j problems or violations, ensure that the licensee's management is informed i that an audit system that functions properly will have many safety i benefits and the use should be encouraged. Upon the review of the safety ,

significance of the issue, the NRC should strongly consider the use of '

enforcement discretion as allowed by 10 CFR Part 2, Appendix C, to not penalize the licensee for discrepancies identified in an audit system l

that functions well.

The licensee may use there own personnel to conduct TS Regardless required auditsof who or may use personnel from different non-power reactors. conducts th These concerns or problems how concerns from the audits were resolved.

should be prioritized, assignments made, and corrective actions taken in accordance with licensee procedures.

40750 Issue Date: 08/07/92

- ~

1'. .

and on one event

c. The review of the licensee's followup on one audit requirement. '

should provide an acceptable sample for this inspection

^ The safety review committee (or equivalent) should review audit results :

and events, and make root cause assessments and corrective action Licensee recomendations in accordance with licensee procedures. i management should address the audits and events,and Requiredconsider reviews safety review should committee assessments include safety and recommendations.

review committee and licensee management reviews of If this function was procedures, experiments, and design changes.

reviewed in the precedure, experiment or design change sections of this inspection procedure, this review need not be repeated here. :

03.10 _Emercency planning

a. The verification of two ' implementing proceduresThe should provide procedures an should t

acceptable sample for this inspection requirement.be revie' plan and licensee administrative procedures.available for use by key implementing procedures should be readily emergency response personnel, such as, operators, senior operators, the The proce-facility emergency director, and health phys.ics _ personnel.

~

dures are generally found either in the control room.and in the adjacent facility director's office which se'rve as emergency response facilities.

- 1

b. The types of exerci'ses and driTls and sthe frequencies are specified in !

the emergency plan. The inspector should check the exercise and drill '

records to ensure that they were conducted, and that appropriate .

individuals participated in the exercises and drills as required.

c. Verification of t a'ing for two key emergency response personnel and one l individual authorized access to the facility (e.g., experimenter) should This may !

provide an acceptable sample for this inspection requirement.

be accomplished by record review, and discussi'ons with respective Authorized personnel in the immediate areas of the incident personnel.

should be able to recognize the indicators of the emergency and know the imediate actions to take to minimize the hazard to themselves a untrained persons in the area. l

d. The inspector should discuss an event scenario that is credible Observation for the of an ;

facility with key emergency response personnel.

exercise or drill could also provide an acceptable sample for this inspection requirement. The discussions or observations should demon-strate the following:

1. Key facilities, supplies, equipment, and instrument ;

l administrative control requirements.

2. The noti.fication rosters and comunications systems should mobilize the licensee's organization to respond as stated in the emergency plan.

3.

The licensee's key emergency response personnel should implement the requirements of the emergency plan and implementing procedures.

4.

Related offsite support (such as offsite medical or police support) I i

should be available in accordance with the emergency plan.

Issue Date: 08/07/92 40750

I *,

I

5. The alarm system should function as required by the emergency plan.

This could be verified either by initiating an alarm (coordinated test, not a drill) or by discussing the calibration or test methods used by the facility to verify operability.

6. The licensee should have appropriate plans in the event of. a power failure as required by the emergency plan and licensee administra- l l

tive controis. i 03.11 Naintenance Loos and Records,_ Selected maintenance logs and records should be reviewed.

a. The logs from several time intervals after the previous inspection should be briefly reviewed to identify if there were problems that have not been .

A review of about 50 percent of .the maintenance identified elsewhere.

logs and records since the last inspection should provide an acceptable 4

sample for this inspection requirement.

b. Credit in this area may be taken to satisfy the requirements Problems in the should j review and audit portion of this inspection procedure. l be resolved in accordance with licensee procedural requirements.

c. A review of one maintenance activity should. provide an acceptable sample for this inspection requirement. ;Tagouts, jumper controls, and authori-

ations for maintenance should be examined. ~ The licensee should specify !

the level of authority and review required to conduct maintenance on the various systems and conditions. These records should be compared with the radiation protection records to ensure that the licensee has acceptably implemented radiation control requirements for maintenance ,

activities. >

An actual observation of fuel handling '

03.12 Fuel Handlino loos and Records.

or review of about 50 percent of the fuel handling logs since the last inspection should provide an acceptable sample for this inspection requirement.

The inspector would have to coordinate the inspection schedule with Theplanned licenseefuel I movement activities if actual fuel handling is to be observed. f should not change planned schedule of fuel movement to accommodate the inspection ;

schedule. :

l Fuel handling record may be entries in the operator logs, separate drawings and and locations, or combinations of these type of l listings documents.

of fuel movementThe records should indicate that the licensee moved fuel to loca:

designed to prevent inadvertent criticality, e.g., storage locations specified in SAR. The final, actual location of the fuel should be consistent with that The fuel handling logs should also provide verification l recorded in the records. ;

that the licensee accomplished any fuel or control rod inspection required by the

~

TS. i

< 40750-04 RESOURCE ESTIMATE For planning purposes, the direct inspection effort to complete this inspection procedure is estimated to be 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . I 1

40750 Issue Date: 08/07/92

3 b,

40750-05 REFERENCES References may be found in the Appendix A for Regulatory Guides and Appendix B for industry standards. ,

END ,

d 3

4 i

4 Issue Date: 03/07/92 an7en

ML20045G145

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SUMMARY

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