ML102440118

University of Maryland Reply to a Notice of Violation

ML102440118
Person / Time
Site:	University of Maryland
Issue date:	08/26/2010
From:	Al-Sheikhly M Univ of Maryland - College Park
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML102440118 (34)

Text

• UNIVERSITY OF MARYLAND Building 090 College Park, Maryland 20742-2115 301.405.5207 TEL 301.314.2029 FAX www..mse.umd.edu GLENN L. MARTIN INSTITUTE OF TECHNOLOGY A. JAMES CLARK SCHOOL OF ENGINEERING Department qfMatcnals Science and E0i&eering August 26, 2010 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001

REFERENCE:

REPLY TO A NOTICE OF VIOLATION University of Maryland -NRC ROUTINE INSPECTION REPORT NO. 50-166/2010 AND NOTICE OF VIOLATION The enclosed document, "Requalification/

Training Program for the Maryland University Training Reactor" (the "Modified Plan") is submitted as a partial response to the Notice of Violation identified above for License No. R-70 (Docket No. 50-166).I declare under penalty of perjury that the foregoing response and Modified Plan are true and correct.Sincerely, Mohamad AI-Sheikhly Professor and Director.Maryland University Training Reactor Enclosure cc: Robert Briber 0(4C REQUALIFICATION/TRAINING PROGRAM FOR THE MARYLAND UNIVERSITY TRAINING REACTOR License No. R-70 Docket No. 50-166 80 w n 21 MAR 00 16 AUG 2010 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program 1.0 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 (MJUTR), in accordance with the Code of Federal Regulations, Title 10, Part 50.54, Condition of Licenses and 1OCFR 55.59, Requalification.

2.0 SCHEDULE The operator Requalification Program cycle will last a period of two years, beginning on 1 January of the biennial year. A 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.

3.0 REACTOR OPERATION The operator will be required to perform, as either a Reactor Operator or Senior Reactor Operator, a minimum of five reactor startups, significant

(>10%) power changes, and shutdowns per year (ten during the two year requalification cycle).4.0 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 continuing basis throughout the requalification cycle in those areas where biennial operator and senior operator written examinations indicate that emphasis in scope and depth of coverage is needed in the following subjects: 1. Theory and principle of operation 2. General and specific operating characteristics

3. Reactor instrument and control systems 4. Reactor protection systems 5. Engineered safety systems 6: Normal, abnormal, and emergency operating procedures

7. Radiation safety and control 8. Technical Specifications

9. Applicable portions of Code of Federal Regulations Title 10, Chapters 1 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 trainees.

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 determined by the Reactor Director) by the licensed operator's participation in the instruction and/or training of students for the NRC license, or both.March 21, 2000 (Revised)August 16, 2010 (Revised)1 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program 5.0 EVALUATION The evaluation of each licensee's knowledge and performance of the requirements set forth in the requalification program will be accomplished bya written and an operating examination at the reactor console. The operating examination will also include an oral examination.

The written examination will be administered biennially, in the fourth quarter of the second year of the two year requalificatiori cycle, and the operating/oral examinations will be administered annually in the fourth quarter of each calendar year.The written and operating examinations for each licensed operator will be prepared and administered in accordance with NUREG-1478, Revision 2 (June 2007), ES601N -Requalification Examination.

Administration.

The written examination will sample items specified in 1OCFR55.41 and 10CFR55.43 as applicable to the facility.

The operating examination will sample items specified in IOCFR55.45 as applicable to the facility.

The Reactor Director or his designee will prepare the written examination and also administer the oral examination and console performance evaluation.

If a license holder scores less than 70% on any section of the biennial written examination, the licensee will attend a makeup session on-that section topic and will be retested on that section. An overall grade of 80%will be required as a passing score.If an individual receives a grade of less than 80% overall, it will be mandatory that he/she be relieved of his/her 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/her licensed duties.An unsatisfactory evaluation on the annual operation/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.6.0 ACCELERATED REQUALIFICATION PROGRAM The additional training that a licensee may require (as indicated by his/her examination) will consist of additional written exams, console performance, and/or oral facility examination.

The additional training and the examination that the licensee receives will depend upon the weaknesses exhibited on previous examinations.

Either the Reactor Director or his designee will determine the number of lectures and examinations that a licensee will receive. The licensee must obtain a rating of at least 80% on the re-evaluation in order to be reassigned to his/her licensed duties.March 21, 2000 (Revised)August 16, 2010 (Revised)2 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program 7.0 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)2. Technical Specifications

3. MUTR Operating and Emergency Procedures

4. Code of Federal Regulations, Title 10, Chapter 1, Sections 19, 20, 50.54, 50.59, 55 8.0 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.9.0 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 3.0 and the review of documents set forth in Section 6.0.March 21, 2000 (Revised)August 16, 2010 (Revised)3 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program Attachment 1 OPERATOR REQUALIFICATION PROGRAM PROGRESS CHECKLIST Used as a means of monitoring qualification progress.

Each licensed operator will have this checklist placed in his/her personnel file. It will be the responsibility of each individual to ensure his/her checklist is kept current.March 21, 2000 (Revised)August 16, 2010 (Revised)4 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program Attachment 1 OPERATOR REQUALIFICATION PROGRAM PROGRESS CHECKLIST License #: Name: License Type: License Issue Date: Annual requalification cycle: through: 1.0 REACTOR OPERATIONS Operator must complete at least 5 reactor operations (startups, significant

(> 10% power changes), and shutdowns) per calendar year during the requalification cycle. List the dates and operation numbers of the ten reactor operations during the cycle: Operation Number Date 2.3.4.5.6.7.8.9.10.2.0 DOCUMENT REVIEW Sign and date on the line corresponding to the following documents after the licensee has reviewed them.1.2.3.4.5.6.7.8.9.10.ll.12.Document Facility License Tech Specs 10 CFR Part 19 10 CFR Part 20 10 CFR Part 50.54 10 CFR Part 50.59 10 CFR Part 55 MUTR OP Series MUTR SP Series MUTR MP Series MUTR EP Series MUTR AP Series Signature Date March 21, 2000 (Revised)August 16, 2010 (Revised)5 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program 3.0 BIENNIAL WRITTEN EXAMINATION Section 1. Reactor theory, thermodynamics, facility operating characteristics Section 2. Normal and emergency procedures, radiological controls Section 3. Facility and radiation monitoring systems Score: Score: Score: Aggregate Score: 4.0 ANNUAL OPERATIONAL/ORAL EXAM Operational exam administered:

date: by: Comments: Oral exam administered:

Comments: Reactor Director's Approval: March 21, 2000 (Revised)August 16, 2010 (Revised)date: by: date: 6 MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program APPENDIX A: TRAINING TOPIC LESSON PLANS The following pages are the lesson outlines for the various topics to be discussed in the lecture/seminar program of the requalification cycle. Included in these outlines are the applicable reference materials.

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 I Startup and Shutdown Checklists Topic 2 Reactor Startup Topic 3 Reactor Operations Topic 4 Reportable Occurrences Topic 5 EP -Evacuation and Organization Topic 6 EP -Primary Coolant Leak Topic 7 EP -Release of Radioactivity Topic 8 Emergency Plan Topic 9 Power Calibration Topic 10 Control Rod Drop Time and Withdrawal Time Topic 11 Control Rod Poison Section Inspection Topic 12 Control Rod Drive Mechanism Inspection Topic 13 Control Rod Calibration Topic 14 Radiation Area Monitor Calibration Topic 15 Pool Water and Effluent Release Topic 16 Administration Topic 17 Primary Water System Topic 18 Secondary and Make-up Water System Topic 19 Sump Systems Topic 20 Reactor Core Topic 21 Control Rod Drive Mechanism Topic 22 Reactor Instrumentation Topic 23 Experiments Topic 24 Reactor Facility Topic 25 Hazardous Materials March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 1: STARTUP AND SHUTDOWN CHECKLISTS 1.0 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.

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

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

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

2.0 REFERENCES

1. Technical Specifications, Section 1.0: Definitions

2. Operating Procedure 101: Reactor Startup Checkout.3. Operating Procedure 102: Reactor Shutdown Checkout.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 2: REACTOR STARTUP 1.0 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."

2.0 REFERENCES

1. Technical Specifications, Section 1.0: Definitions.

2. Operating Procedure 103: Reactor Startup.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 3: REACTOR OPERATIONS 1.0 LEARNING OBJECTIVES I. 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.

2.0 REFERENCES

I. Technical Specifications, Section 2.0: Safety Limits and Limiting safety System Settings.2. Technical Specifications, Section 3.0: Limiting Conditions for Operation.

3. Operating Procedure 104: Reactor Operations 3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 4: REPORTABLE OCCURRENCE 1.0 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.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.

2.0 REFERENCES

1. Technical Specifications, Section 1.0: Definitions

2. Technical Specifications, Section 6.0: Administration

3. Emergency Procedure 403: Response to Reportable Occurrences.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 5: EMERGENCY PROCEDURES

-EVACUATION AND ORGANIZATION 1.0 LEARNING OBJECTIVES

1. Review the Emergency Procedures for evacuation.

Discuss the various assembly areas, where emergency phones are located, and review the Calldown list.2. Discuss the Reactor Operator'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.

2.0 REFERENCES

I. Technical Specifications, Section 6.0: Administration

2. Emergency Procedure 401: Reactor Building Evacuation.

3. Emergency Procedure 406: MUTR Emergency Organization.

4. Emergency Procedure 407: Nuclear Reactor Emergency Call List.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 6: EMERGENCY PROCEDURES

-PRIMARY COOLANT LEAKS 1.0 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.2. Discuss the Reactor Operator's response and responsibilities during a Primary Coolant leak.3. Discuss the Department's response and responsibilities during an evacuation.

2.0 REFERENCES

1. Technical Specifications, Section 5.2: Reactor Coolant System 2. Emergency Procedure 401: Reactor Building Evacuation.

3. Emergency Procedure 402: Primary Coolant System Leaks.4. FSAR, Section 5.0: Reactor Coolant Systems.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 7: EMERGENCY PROCEDURES

-RELEASE OF RADIOACTIVITY 1.0 LEARNING OBJECTIVES

1. Review the Emergency Procedure for Release of Radioactivity.

Discuss the exposure limits for personnel as set forth by 10 CFR Part 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.

2.0 REFERENCES

I. Emergency Procedure 401: Reactor Building Evacuation.

2. Emergency Procedure 404: Release of Radioactivity.

3. Emergency Procedure 406: MUTR Emergency Organization.

4. 10 CFR Part 20: Standards for Protection Against Radiation 3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 8: EMERGENCY PLAN 1.0 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 MIUTR during an emergency event.

2.0 REFERENCES

1. Emergency Preparedness Plan 2. Emergency Procedure 406: MUTR Emergency Organization.

3. Emergency Procedure 407: Nuclear Reactor Emergency Call List.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21,2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 9: POWER CALIBRATION 1.0 LEARNING OBJECTIVES

1. Review the procedure for a power calibration.

Identify the precautions and prerequisites that must be 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 2%.

2.0 REFERENCES

I. FSAR, Section 4.0: Reactor Description.

2. Surveillance Procedure 202: Reactor Power Calibration.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 10: CONTROL ROD DROP TIME AND WITHDRAWAL TIME 1.0 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 performed.

2. Review the Control Rod Drop Time Data Sheet.3. Discuss the actions taken when control rod drop times are greater than 1 second.4. Review the procedure to determine the control rod withdrawal times. Give the frequency that this surveillance procedure is required to be performed.

5. Review the Control Rod Drop Time Data Sheet.6. Discuss the actions taken when the reactivity insertion rate is greater than $0.30/s.

2.0 REFERENCES

1. FSAR, Section 4.0: Reactor Description.

2. Surveillance Procedure 203: Control Rod Drop Times.3. Surveillance Procedure 213: Control Rod Withdrawal Rate.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 (Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 11: CONTROL ROD POISON SECTION INSPECTION 1.0 LEARNING OBJECTIVES

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

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.

2.0 REFERENCES

1. Technical Specifications, Section 4.0: Surveillance Requirements

2. FSAR, Section 4.0: Reactor Description.

.3. Surveillance Procedure 201: Control Rod Poison Section Inspection.

4. Maintenance Procedure 303: Fuel Movement.5. Maintenance Procedure 304: Control Rod Drive and Control Rod Removal.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 12: CONTROL ROD DRIVE MECHANISM INSPECTION 1.0 LEARNING OBJECTIVES

1. Review the procedure for inspection of the CRDMs. Give the frequency that this surveillance procedure is required to be performed.

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

2.0 REFERENCES

1. Technical Specifications, Section 4.0: Surveillance Requirements

2. FSAR, Section 4.0: Reactor Description.

3. Surveillance Procedure 212: Control Rod Drive Mechanism Inspection.

4. Maintenance Procedure 304: Control Rod Drive and Control Rod Removal.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 13: CONTROL ROD CALIBRATION 1.0 LEARNING OBJECTIVES I. Review the procedure for calibration of control rods. Give the frequency that this surveillance procedure is required to be performed.

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.

2.0 REFERENCES

Technical Specifications, Section 4.0: Surveillance Requirements.

FSAR, Section 4.0: Reactor Description.

Surveillance Procedure 204: Control Rod Inspection.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 14:RADIATION AREA MONITOR CALIBRATION 1.0 LEARNING OBJECTIVES

1. Review the procedure for radiation monitor calibration.

Give the frequency that this surveillance procedure is required to be performed.

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.

2.0 REFERENCES

1. Technical Specifications, Section 3.4: Radiation Monitoring System.2. Technical Specifications, Section 4.0: Surveillance Requirements.

3. FSAR, Section 7.7: Radiation Monitoring Systems.4. Surveillance Procedure 205: Eberline Radiation Area Monitor Calibration.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 15: POOL WATER AND EFFLUENT RELEASE 1.0 LEARNING OBJECTIVES

1. Review the procedure for pool water sampling.

Give the frequency that this surveillance procedure is required to be performed.

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 10 CFR Part 20 Appendix B, activity limits for effluent.4. Discuss how gaseous effluent is produced at MUTR (Ar-41), and how this gaseous effluent is released to the environment.

2.0 REFERENCES

1. Technical Specifications, Section 3.3: Primary Coolant Condition 2. Technical Specifications, Section 4.0: Surveillance Requirements.

3. Surveillance Procedure 206: Pool Water Conductivity Determination.

4. Surveillance Procedure 207: Gamma Ray Spectroscopy of Pool Water.5. Surveillance Procedure 208: Sump Operation.

6. FSAR Section 11.0: Radiation Protection Program and Waste Management.

7. 10 CFR Part 20 Appendix B: Annual Limits.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 16: ADMINISTRATION 1.0 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.

2.0 REFERENCES

1. Technical Specifications, Section 1.0: Definitions.

2. Technical Specifications, Section 6.0: Administration.

3. 10 CFR Part 55: Operators'Licenses.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 17: PRIMARY WATER SYSTEM 1.0 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.

2.0 REFERENCES

1. Technical Specifications, Section 3.3: Primary Coolant Condition.

2. Technical Specifications, Section 4.3: Reactor Coolant System.3. Technical Specifications, Section 5.1: Reactor Coolant System.4. FSAR, Section 5.0: Reactor Coolant Systems.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 18: SECONDARY AND MAKE-UP WATER SYSTEM 1.0 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.

2.0 REFERENCES

1. FSAR, Section 5.0: Reactor Coolant Systems.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 19: SUMP SYSTEM 1.0 LEARNING OBJECTIVES

1. Draw the sump, identifying major components.

Give the purpose for each component.

2. Review the different modes of operation for the sump.3. Describe the process for taking a sample of the sump contents.4. Discuss the requirements to release the sump contents to the sanitary sewer system.

2.0 REFERENCES

1. FSAR, Section 5.7: Reactor Sump.2. FSAR, Section 11.0: Radiation Protection Program and Waste Management

2. Surveillance Procedure 12: Sump Operation 3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 20: REACTOR CORE 1.0 LEARNING OBJECTIVES I. 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.

2.0 REFERENCES

1. Technical Specifications, Section 5.0: Reactor Fuel 2. FSAR, Section 4.0: Reactor Description.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 21: CONTROL ROD DRIVE MECHANISM 1.0 LEARNING OBJECTIVES

1. Identify the major components of a control rod drive mechanism (CRDM). Distinguish between the three micro-switches, and how each is physically linked to a control rod.2. Describe the operation of the logic circuit, and the various indicating lights available to the operator.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 scram.

2.0 REFERENCES

I. Technical Specifications, Section 3.2: Reactor Control and Safety Control.2. FSAR, Section 4.0: Reactor Description.

3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 22: REACTOR INSTRUMENTATION 1.0 LEARNING OBJECTIVES

1. List the three types 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 uncompensated ion chamber, and list which instruments this detector provides a signal to.

2.0 REFERENCES

1. FSAR, Section 7.0: Instrumentation and Control Systems.2. ENNU-320 Manual: Volume II.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 23: EXPERIMENTS 1.0 LEARNING OBJECTIVES

1. List the three types 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.

2.0 REFERENCES

1. Technical Specifications, Section 1.0: Definitions.

2. Technical Specifications, Section 3.5: Limitations on Experiments.

3. FSAR, Section 10.0: Experimental Facilities and Utilization.

4. ENNU-320 Manual: Volume Ii.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 24: REACTOR FACILITY 1.0 LEARNING OBJECTIVES

1. Describe the construction of the reactor pool tank, giving 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.3. Explain where potential Radiation Areas are in the facility (Hot Room, bridge, etc.), and the importance of maintaining security.

Locate the fuel storage pit, and discuss importance of maintaining kff less 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.

2.0 REFERENCES

I. Technical Specifications, Section 4.5: Ventilation System.2. Technical Specifications, Section 5.4: Fissionable Material Storage.3. FSAR, Section 4.0: Reactor Description.

4. FSAR, Section 6.0: Engineered Safety Features.5. FSAR, Section 9.1: Heating, Ventilation, and Air Conditioning Systems.6. FSAR, Section 9.4: Communication Systems.7. FSAR, Section 9.2: Handling and Storage of Reactor Fuel.3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)

MARYLAND UNIVERSITY TRAINING REACTOR Requalification/Training Program TOPIC 25: HAZARDOUS MATERIALS 1.0 LEARNING OBJECTIVES

1. Define what a Hazardous Material is. What is the official University policy on the use of hazardous materials.

2. Describe the some of the precautions to be taken with the various hazardous materials used throughout the facilities (with particular emphasis to the handling of lead).3. Describe all the resources available to the individual for obtaining information and guidance concerning hazardous material.4. Outline the responsibilities and rights of individuals who will use, or generally be exposed to, hazardous materials in the performance of their duties on campus.

2.0 REFERENCES

1. UMCP Policy VI- 13.00(A)2. OSHA Regulatory Standards

-29CFR 3. http://www.osha-slc.gov/OshStdtoc/OSHAStd-toc.html 3.0 ATTENDANCE RECORD Printed Name Signature Date Training Conducted by: March 21, 2000 Revised)August 16, 2010 (Revised)