ML20206S059

Proposed Tech Specs Reflecting Change in Facility Operating Status as Possession Only License

ML20206S059
Person / Time
Site:	University of Iowa
Issue date:	01/22/1999
From:	IOWA STATE UNIV., AMES, IA
To:
Shared Package
ML20206S056	List: ML20206S050 ML20206S059
References
NUDOCS 9901280055
Download: ML20206S059 (36)

Text

TECHNICAL SPECIFICATIONS for the UTR-10 REACTOR FACILITY at IOWA STATE UNIVERSITY Docket No. 50-116 ,

License No. R-59 j Possession Only License l Amendment #13 i

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1 Technical Specifications l

Table ofContents -

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1.0 Defim. .tions.............................................................................................1-1 2.0 Safety Limits & Limiting Safety System Settings.......... . . ....... ...... .... .. .... 2-1 4 2.1 Safet y Li mit s . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1i 2.2 Limiting Safety System Settings ..... ....... ................ ............. ......... .. ..... 2-2

. 3.0 Limiting Conditions for Operations ........ ........... ........ .......... . . ..... ............ 3-1 3.1

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Reactor Core Parameters .......... . ..............................................31 l 3.2 Reactor Control & Safety Systems.. .......................... ... .. . ...... ........... 3-2 1 3.3 Coolant Systems ............... .........................................................3-3 i

3.4 - Confinement . . . . . . . . . .. . . . . . ... . . .. .. . . .. . . . . . . . . .. . . . .. . . .... .........................3-4 3.5 Ventilation Systems . . . . ..... . . . . . . ... . . . . . . . . . .. . . . .. . .. . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . 3 -5 l

3.6 Emergency Power. . . . .. . . . . . . . .. . .. . . . . . .. . . . . . . . . . . . . . . .. . . .. . ... . .. . . . . . . . . . . . . . . . . . .. . . 3 -6 3.7 Radiation Monitoring. .... .... . . . . . ..... . .. . .. . ...... .... ...... ..... ...... .. . . . . . . . . . . . 3 -7 3

3.8 Experiment s. . . . . . . . . . . . .. .. . ... . ... ... . . . . . . . . . . . . . . . . . . . . . . .. . . ................ . . . . . . . . . . . . . .3 -9 4.0 Surveillance Requirements .................... ... ......... ............... . ............. . ..... . 4-1 '

4.1 Reactor Core Parameters .... ...... ... ... . . . ............. . .... ..... ...... . .. .. . . . .. ... .. .. 4- 1 4.2 Reactor Control & Safety Systems...... . .. . .. .. .. ..... ...... ..... ... . ....... .. 4-2

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4.3 - Coolant Systems . .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . .. . . . . .. . . . . . . .. . . 4-3 4.4 C onfinement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4 ;

4.5 Ventilation Systems .. .. .. .... . ... . . ... ... .... ......... .. . . .... .. ........ . . . . . . . . . . . . . 4-5 l

.4.6 Emergency Power.. . . . . . . .. . . . . . . . . .. . .... . . . . ... . ... .. . . . .. . . ... . . .. . . . . . . . . . . . . . . . . . . . 4 -6 4.7 Radiation Monitoring... . ... . ... . . .... .. . .. ........ ... .. .. .. .. . ... . . . ... .. .. . . . . .. . . . . .. 4-7 4.8 Experime nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -. . . . . . . . . . . . . . . . . 4-8 5.0 Design Feat ures .. . . . .. . . . . . ... .. . .. . . . . . . . .. . . . . . . . . . .. . . . . . .. . . . . . . .. . . . . . . . . . . .. . . 5- 1 5.1 Site & Facility Description .......... .. . ........ .. ... ....... ... . . . .. .... . ..... . 5-1 5.2 - Fissionable Material Storage........... .............. ... ..... . .... . . .. ........ . ... . . 5-2 6.0 Administrative Controls . ... ..................... .... . .. .. ..... ....~.. ... . . . .. . . . 6- 1 6.1 _ Organizat ion . .. . . . .. . .. . . . . . . . . . . . . . . . . . .. . . . . . . . ~ . . . . . . . . . . . . . . . .. . . - . . . . - . - . . 6- 1 6.2' Review & Audit. . .. . . . . .. . . . ... . . . .. . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . 6-3 6.3 Procedures . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.4 Experiment Review & Approval. . .. ..............................................6-6 i 6.5 Required Actions. ....... ... . .. . ..................................................6-7 6.6 -Reports.......................................................................... ... .. 6-8 6.7 Records.................................................................................. . . ... . 6- 10 i Figure 6.1 Organizational Structure ... ................... ..... ........... .... ...... .... 6-11 i

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l.0 DEFINITIONS h terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50.36 of 10 CFR Part 50.

CHANNEL TEST - h introduction of a signal into the channel for verification that it is operable. ,

t CHANNEL CALIBRATION - h adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment  ;

actuation, alarm, or trip and shall be deemed to include a Channel Test.  ;

CHANNEL CHECK - A qualitative verification of acceptable performance by l observation of channel behavior. This verification, where possible, shall include the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEMENT BOUNDARY - The surface surrounding the reactor facility defined by the interior panition walls of offices and laboratories on the north, east and south sides of the building and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from the central bay.

CONFINEMENT SECURED - The confinement shall be considered secured when:

a. Doors 1-2, CC 102,101,114,113-1, CX112,112,111-1, CX111, CS107, CEI17-2, CC201B,112A-4 are closed or are attended by a person with the ability to close the door in the event of an emergency, and

b. Windows on the nonh, south, east and west sides of the penthouse, on the west l wall of room 112A, on the south wall of room 101, on the east wall above door '

CX112, on the south wall of corridor CC201, on the west wall of corridor l CC212, on the nonh wall of corridor CC211 are unbroken and closed or are attended by a person with the ability to close the window in the event of an emergency, and

c. The interior panitioned walls of the first floor offices and laboratories on the north, south, and east sides of the building; and the west interior wall which isolates the basement and first floor offices on the west side of the building i from the central bay area; and the second floor north, south, east and west interior walls which isolate the second floor from the central bay area are intact  !

and capable of performing as a non-pressure tight boundary, and

- d. W roof covering the central bay area is intact and capable of performing as a non-pressure tight boundary MEASURED VALUE - The value of a parameter as it appears on the output of a channel.

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1.0 DEFINITIONS (Continued)

MEASURING CHANNEL - The combination of sensor, line, amplifier and output devices which are connected for the purpose of measuring the value of a parameter.

OPERABLE - A component or system is capable ofperforming its intended function.

OPERATING - A component or system is performing its intended function.

l REACTOR OPERATOR (RO) - An individual who is licensed to manipulate the controls of a reactor..

REACTOR SHUTDOWN - The reactor is considered to be shutdown as long as it contains no fuel.

READILY AVAILABLE ON CALL - Applies to an individual who:

(1) Has been specifically designated and the designation known to the operator on duty, and j l

(2) Keeps the operator on duty informed of where he or she maybe rapidly contacted (e.g., by phone, etc.), and (3) Is capable of getting to the reactor facility within a reasonable time under j normal conditions (e.g., 30 minutes). '

SENIOR REACTOR OPERATOR (SRO) - An individual who is licensed to direct the activities of a Reactor Operator (RO) and to manipulate the controls or a reactor.

SHALL, SHOULD, AND MAY - The word "shall" is used to denote a requirement, the word "should" to denote a recommendation, and the word "may" to denote permission, neither a requirement nor a recommendation.

. SURVEILLANCE TIME IN1ERVALS - The average over any extended period for each surveillance time interval shall be closer to the identified surveillance time than to the maximum allowed time, e.g., for the annual interval the average shall be closer to 12 months than to 13 months.

Biennial - once every 2 years (interval not to exceed 25 months)

Annual - once every 12 months (interval not to exceed 13 months)

Bi-annual- once every 6 months (interval not to exceed 7 months)

Quarterly - once every 3 months (interval not to exceed 4 months)

Monthly - once every 30 days (interval not to exceed 6 weeks)

Any extension of these intervals shall be occasional and for a valid reason and shall not affect the average as defined.

TRUE VALUE - The actual value of a parameter or variable.

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1 2 0 SAFETY LIMITS AND SAFETY SYSTEM SETTINGS I 2.1 Safety Limits ,

t l 2.1.1 Applicability i

These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license (POL) status.  ;

Fuel handling operations are the only licensed activity allowed. Reactor operations are not authorized.

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1.0 DEFINITIONS (Continued) 2.2 Limitina Safety System Settinas 2.2.1 Applicability These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license (POL) status.

Fuel handling operations are the only licensed activity allowed. Reactor operations are not authorized. '

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3.0 LIMITING CONDITIONS FOR OPERATIONS i 3.1 Reactor Core Parameters 3.1.1 Applicability i

These specifications are not applicable.  !

f The UTR-10 reactor has been permanently de-fueled and is in possession only license  ;

(POL) status.

i Fuel handling operations are the only licensed activity allowed, Reactor operations are i not authorized. i l

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3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) 3.2 Reactor Control and Safety System 3.2.1 Applicability These specifications are not applicable.

I The UTR-10 reactor has been permanently de-fueled and is in possession only license I (POL) status.

Fuel handling operations are the only licensed activity allowed. Reactor operations are !

not authorized.

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1 3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) l 3.3 Coolant SystemE - 1 1

3.3.1 Applicability l These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license (POL) status.

Fuel handling operations are the only licensed activity allowed. Reactor operations are i not authorized.

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3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) 3.4 Confinement 3.4.1 Applicability l l

This specification applies to the operations that require confinement and to the equipment needed to achieve confinement. i 3.4.2 Objective ,

l To ensure that the confinement boundary can be secured when needed.

3.4.3 Specifications A. The reactor confinement boundary shall be secured during fuel transfer operations.

3.4.4 Bases a

l Specification A is based on the hypothetical accident (SAR: 6.4) that occurs during movement of a fuel assembly and the importance of having the confinement boundary

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1 secured prior to the fuel transfer operation.

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I i 3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued)  :

3.5 Ventilation Systems >

There is no forced-air circulation system in the reactor room or the building housing it.

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3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) i 3.6 Emeraency Power l

l l 3.6.1 Applicability [

i These specifications apply to the emergency power supply for the radiation monitoring j system.

3.6.2 Objective To specify the source of emergency electrical power and the minimum operating time.

3.6.3 Specifications Fuel transfer operations shall not be performed unless the following conditions exist:

A. The battery-powered standby AC power supply for the radiation monitoring system shall be operable and shall have the following operating time capabilities:

(1) Operating time without the radiation-evacuation hom being activated shall be 'l' not less than eight hours.

(2) Operating time with the radiation-evacuation horn being activated shall be not less than two hours.

l 3.6.4 Bases Specification A requires that the standby AC power system, which consists of at least two lead-acid storage batteries, a charger transfer unit, and an inverter, be capable of providing a tripless switchover for supplying AC power to the radiation monitoring system, and that the power source be able to sustain operation for the specified intervals.

There are no systems, other than radiation monitoring, that need emergency power. The radiation evacuation horn imposes a large incremental load on the power source and severely reduces the operating time; however, the evacuation signal, if needed, would be of sufficient duration to accomplish its intended purpose.

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3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) 3.7 P=*= dan Monitorine Symama and Effluents f i

3.7.1 Applicability l

These specifications apply to the radiation monitoring systems and to the limits on l effluent releases.  !

3.7.2 Objective  !

j To specify the minimum number of acceptable components or the lowest acceptable level  !

of performance for the radiation monitoring systems and the limits for release of l effluents. '

3.7.3 Specifications Fuel transfer operations shall not be performed ur.less the following conditions exist:

A. The radiation monitoring channels and components shall be operable in accordance .

with Table 3-3, including the minimum number of channels or components, and i their setpoints.

3.7.4 Bases l

Specification A provides assurance that the required radiation monitors are operable. j e The air-particulate monitor is placed in service and operated continuously whenever l fuel transfer operations are being performed which could produce airborne radioactivity.' The alarm setpoint is influenced by the normal background reading.

• The radiation area monitors are placed on the walls adjacent to the fuel storage pit.

The south and west units initiate an evacuation alarm at or above the radiation-evacuation setpoint of 5 mR/h. The 5 mR/h limit is based on the minimum value permitted for monitoring SNM in storage and applies when the area is unattended.

• The doorway radiation monitor serves as a frisker to detect abnormal levels of i radiation when a person passes the detector. The increasing aural signal alerts the j reactor operator and the affected individual that further assessment must be initiated. I e The radiation film badge (or its equivalent) provides radiation dose information at i the perimeter wall of the reactor room and serves as a control for the film badges used by personnel in the restricted area.

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I 3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) i i

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i. . Table 3 3. Required Radiation Monitoring Channels or Components.  !

L Channel Setpoint Min. Operable - Function  !

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Air. Particulate unit (a) As required 1 Alarm  !

Area units 5 mR/h 2 Alarm i

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Doorway monitor -

1 Warn of abnormal  !

radiation level.

I i Environmental film -

1 Integrated dose in i restricted area. -l i

. (a) This unit is activated whenever fuel transfer operations are being performed. l l

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l l 3.0 LIMITING CONDITIONS FOR OPERATIONS (Continued) l l ,

i 3.8 Experiments l

l l 3.8.1 Applicability These specifications are not applicable.

! t l The UTR-10 reactor has been permanently de-fueled and is in possession only license l

(POL) status. .

i Fuel handling operations are the only licensed activity allowed. Reactor operations are ,

not authorized.  !

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4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Core Parameters 4.1.1 Applicability ,

l These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license l

(POL) status.  ;

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Fuel handling operations are the only licensed activity allowed. Reactor operations are not authorized.

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I 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.2 Reactor Control and Safety System 4.2.1 Applicability l These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license (POL) status.

Fuel handling operations are the only licensed activity allowed. Reactor operations are not authorized.

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1 4.0 SURVEILLANCE REQUIREMENTS (Continued) i i

4.3 Coolant Systems l

4.3.1 Applicability ,

l These specifications are not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license j (POL) status. l l

1 Fuel handling operations are the only licensed activity allowed. Reactor operations are l not authorized. l l

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l 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.4 Confinement 4.4.1 Applicability This specification applies to the surveillance activities required for the reactor confinement.

4.4.2 Objective To specify the frequency and type of testing to assure that the reactor confinement confomis to the specifications of section 3 of these Specifications.

4.4.3 Specification A. The doors and windows in the confmement boundary shall undergo testing for normal closure at least once every quarter.

4.4.4 Bases This specification requires that the doors and windows in the confinement boundary be tested to verify that they can be closed when needed. The testing interval is adequate to verify operability based on experience at this facility.

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' 4.0 SURVEILLANCE REQUIREMENTS (Continued) -

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4.5 Vantilatian Synema 1

This specification does not apply to this facility. I l

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t 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.6 Emergency Power 4.6.1 Applicability These specifications apply to the surveillance activities required for the emergency power system.

4.6.2 Objective l

To specify the frequency and type of testing to assure that the emergency power system conforms to the specifications of section 3 of these Specifications.

4.6.3 Specifications These surveillance activities are required for safety when the reactor is not being operated.

A. The battery-operated AC standby power. supply shall be tested for switchover action, and for voltage and specific gravity characteristics at least quanerly.

l B. The batteries shall be tested for full discharge at lear,e every three years.

4.6.4 Bases Specification A requires verification of operability of the standby power supply to l complete the switch-over from normal AC power to the batteries at an interval which is  ;

appropriate based on experience at this facility. The measured values of voltage and i

. specific gravity give adequate warning of reduced batter performance within the testing interval.

1 A full discharge test of the batteries every three years, as required in specification B, is appropriate for the type of battery used in the power supply; the interval is well within the normal 4-5 year warranted life for conditions much more severe than those encountered l in this application.

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4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.7 Padi=+ian Monitorina Svetem and Effluents 4.7.1 Applicability l

These specifications apply to the suiveillance activities required for the radiation monitoring system and effluents released from the facility.

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4.7.2 Objective To specify the frequency and type of testing to assure that the radiation monitoring  !

system and effluent releases conform to the specifications of section 3 of these Specifications.

4.7.3 Specifications  !

These surveillance activities are required for safety when the reactor is not being operated.

A. A calibration of the channels listed in Table 3-3 that can be calibrated shall be performed at least annually and whenever any maintenance on a channel which i may aff'ect its performance is completed.  !

B. An operability test, including source checks, of the radiation monitoring channels listed in Table 3-3 shall be performed at least monthly.

C. The environmental film badge cited in Table 3-3 and smear surveys in and  !

- around the reactor enclosure shall be analyzed at least quaderly. l 4.7.4 Bases  ;

Based on experience at this facility and the average usage pattern of the reactor, '

specification A-C are adequate to verify that the operations conform to the specifications of3.7.3 4-7

4.0 SURVEILLANCE REQUIREMENTS (Continued)  !

1 4.8 Experiments 4.8.1 Applicability These specifications are not applicable. ,

i The UTR-10 reactor has been permanently de-fueled and is in possession only license *

(POL) status.  !

Fuel handling operations are the only licensed activity allowed. Reactor operations are not authorized.

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5.0 DESIGN FEATURES 5.1 Site and Facility Description The reactor is housed in the Nuclear Engineering Laboratory, which is located on the west edge of the campus ofIowa State University, in Ames, Iowa. The Nuclear Engineering Laboratory is a two-story, three-level building of brick construction, built in 1934. The reactor, a model UTR-10, was installed and first operated in 1959. The reactor is located on the ground floor level, central bay area, of the Laboratory structure.

The central bay is approximately 34 feet high and has a floor area of 37 feet by 56 feet of which a space approximately 37 feet by 38 feet is allocated to the reactor. A wall surrounding this area is constructed of standard concrete block and reaches a height of 10 l feet 4 inches on the nonh, east and south sides; the west boundary is a wall that reaches from the floor to the ceiling of the central bay region. The purpose of these walls is to limit access ofunauthorized personnel to the immediate vicinity of the reactor and to l define the outer perimeter of the restricted area.

l The enclosure surrounding the reactor includes the central section of the building as defined by the interior panition walls of offices and laboratories on the nonh, east and l south sides of the building, and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from the central bay. The purpose of the enclosure is to act as a confinement volume and to help limit the release of radioactive materials to the environment. The enclosure volume is slightly less than 2500 cubic meters, and the average infiltration rate for the building is estimated to result in two changes per hour. There is no central forced-air circulation system in the building.

The enclosure has two outside doors, one in the east wall and a large overhead door opening to the south. All interior doors leading into the enclosure are of a standard type used in interior construction. Other significant penetrations into the enclosure consist of roof-level windows on the nonh and south sides which can be manually opened or closed, as a group per side, in less than one minute per group.

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~ 5.0 DESIGN FEATURES (Continued) l 5.2 Fi==toamble Matarial Stornoa l

Fuel not in the reactor is stored in a dry fuel storage pit monitored by radiation and  ;

intrusion detectors (Ref: Drawing R1-E-194 and Physical Security Plan). The fuel  ;

. storage array, under all conditions of moderation and reflection with light water, has an effective multiplication factor less than 0.9.  !

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i' 6.0 ADMINISTRATIVE CONTROLS l

6.1 Organization i 6.1.1 Structurs i

The organization for the management of the reactor facility shall be structured as  !

> indicated in Figure 6-1. Job titles are shown for illustration and may vary. Levels of l authority indicated divide responsibility as follows l

1evel 1: Responsible for the facility license and site administration. i Level 2: Responsible for the reactor facility operation and management.

level 3: Responsible for daily operations.  :

The Reactor Use Committee is appointed by, and shall report to the University Radiation l

Safety Committee. Radiation safety personnel shall report to Level 2 or higher through an l

independent organizational channel.

l 6.1.2 Responsibility l The Facility Director shall be responsible for the facility license and site administration. l The dean, College ofEngineering, shall appoint persons, qualified in accordance with l paragraph 6.1.4, to the Facility Director and Reactor Manager positions.  !

1 Individuals at the various management levels shown m Figure 6-1, ~in addition to having -!

responsibility for the policies and operation of the facility, shall be responsible for i safeguarding the public and facility personnel from undue radiation exposures and for  !

adhering to all requirements of the Operating License and the Technical Specifications.

In all instances, responsibilities of one level may be assumed by designed alternates, or  !

by higher levels, conditional upon appropriate qualifications.  !

I' 6.1.3 Staffing ,

(1) The minimum staffing during fuel transfer operations shall be:

a. A licensed senior reactor operator in the control room. i

b. A health physics-qualified individual in the control room. i

c. A qualified fuel transfer equipment operator.

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6.0 ADMINISTRATIVE CONTROLS (Continued)

(2) Events requiring the direction of a senior reactor operator:

a. Fuel transfer operations.

(3) Events requiring the presence of a health physics-qualified individual:

a. Fuel transfer operations.

b. Any activity that involves removal of a shield plug or closure.

c. Any activity that could cause an abnormal release of radioactive materials.

6.1.4 Selection and Training of Personnel The selection, training and requalification of operations personnel shall meet or exceed the requirements of American National Standard for Selection and Training of Personnel for Research Reactors, ANSI /ANS-15.4-1988, or its successor, meet or exceed the requirements set forth in 10 CFR 55, and be in accordance with the Requalification Plan approved by the Nuclear Regulatory Commission.

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6.0 ADMINISTRATIVE CONTROLS (Continued) l 6.2 Review and Audit  !

The Reactor Use Committee (RUC) shall perform the independent review and audit of the safety aspects of reactor facility operations. f i

6.2.1 Composition and Qualifications i

r The Reactor Use Committee shall be composed of the Reactor Manager and radiation l health physicist, both ex officio (voting), and at least three other members having  !

expertise in reactor technology. Committee members shall be appointed by the University Radiation Safety Committee. (The Radiation Safety Committee is composed of a j representative from each of the colleges in the university in which research in the physical and life sciences and in engineering is conducted, plus three members with specific expertise in radiation protection. At least one of these members shall also represent university management. One of the three other members shall be the University Radiation Safety Officer (RSO). The chair of the committee shall be appointed by the ,

Provost. The terms on the committee for the RSO and chair are indefinite. All others are for three years with reappointments being determined by the Provost.)

6.2.2 Charter and Rules (1) The Reactor Use Committee shall meet at least semiannually and more frequently as circumstances warrant, consistent with effective monitoring of facility activities.

Written records ofits meetings shall be kept and copies forwarded, in a timely manner, to the University Radiation Safety Committee.

(2) A quorum shall be three members. Members of the operations staff shall not be a voting majority. Phone polling of members is allowed for final approval ofitems discussed at a meeting or for approval of other items deemed " routine" by the Reactor Manager or the committee chair. Any member can veto the use of the phone poll and request a meeting of the committee.

(3) Any action recommended by the Reactor Use Committee that may adversely affect the operations and/or safety of the University community shall be reported by the RUC chairman to the University Radiation Safety Committee which shall have veto power over such a recommendation.

(4) The Reactor Use Committee may appoint one or more qualified individuals to perform the audit function.

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6.0 ADMINISTRATIVE CONTROLS (Continued) ,

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l 6.2.3 Review Function  !

j The following items shall be reviewed l

[ (1) Determinations that proposed changes in equipment, systems, tests, or procedures j do not involve an unreviewed safety question.- [

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(2) All new procedures and major revisions thereto have safety significance and i proposed changes in reactor facility equipment, or systems having safety l' significance.

(3) Proposed changes in the Technical Specifications or the Operating License.

j (4) Violations of the Technical Specifications or the Operating License. Violations of l

internal procedures or instructions having safety significance. l i (5) Reportable occurrences listed in 6.6.2. t (6) Audit reports. )

6.2.4 Audit Function I

The audit function shall include selective (but comprehensive) examination of operating records, logs, and other documents. Discussions with cognizant personnel and 3 observation of operations should also be used as appropriate. In no case shall the d

individual immediately responsible for tne area, audit in that area. Deficiencies 1 uncovered that affect reactor safety shall be reported immediately to the University {

l Radiation Safety Committee. A written report of the findings of the audit shall be

submitted to the Reactor Use Committee within 30 days after completion of the audit.

! The following items shall be audited.

(1) Facility operations for conformance to the Technical Specifications and applicable Operating License conditions, at least once per calendar year (interval between audits not to exceed 15 months).

(2) The retraining and requalification program for the operating staff, at least once every other calendar year (interval between audits not to exceed 30 months).

(3) The results of action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operations that affect safety, at least once per calendar year (interval between audits not to exceed 15 months). l

. I (4) The reactor facility Emergency and Physical Security Plans and implementing i procedures at least once every other calendar year (interval not to exceed 30 i months).

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i 6-4

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.3 Procedures ,

I Written procedures shall be prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures shall be reviewed by the Reactor Use Committee (see 6.2.3) and approved by the Reactor Manager or a designated alternate. .

These reviews and approvals shall be documented in a timely manner. Substantive changes to the procedures shall be made effective only after documented review by the Reactor Use Committee and approval by the Reactor Manger or a designated alternate. l' Minor modifications to the original procedure which do no change their original intent may be made, but the modification must be approved by the Reactor Manager or a designed alternate within 14 days. Temporary deviations from the procedures may be

- made by the on-duty SRO in order to deal with special or unusual circumstances or conditions. Such deviations shall be documented and reported to the Reactor Manger or a designated alternate. Several of the following activities may be included in a single manual or set of procedures or divided among various manuals or procedures:

5 (1) Fuel element manipulations.

(2) Surveillance tests and calibrations required by the Technical Specifications c r those that may have an effect on safety. ,

(3) Personnel radiation protection consistent with applicable regulations.

i (4) Administrative controls for operations and maintenance and for the conduct of irradiation and experiments that could affect safety.

(5) Implementation of the Emergency and Physical Security Plans.

4 6-5

I 6.0 ADMINISTRATIVE CONTROLS (Continued) l 6.4 Exneriment Review and Approval l L This section is not applicable.

l The UTR-10 reactor has been permanently de-fueled and is in possession only license  !

(POL) status.  !

Fuel handling operations are the only licensed activity allowed. Experiments are not authorized. j l l i

6-6

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.5 Required Actions 6.5.1 Action to be Taken in Case of Safety Limit Violation This section is not applicable.

The UTR-10 reactor has been permanently de-fueled and is in possession only license (POL) status.

Fuel handling operations are the only licensed activity allowed. Reactor operation is not authorized.

6.5.2 Action to be Taken in the Event of an Occurrence of the Type Identified in 6.6.2(1)a and 6.6.2(1)b.

(1) Occurrence shall be reported to the Reactor Manager or a designated alternate and to the NRC.

(2) Occurrence shall be reviewed by the Reactor Use Committee at its next scheduled meeting.

i 6-7 e

6.0 ADMINISTRATIVE CONTROLS (Continued) 6.6 Reports 6.6.1 Operating Reports A routine operating report providing the following information shall be submitted to the Nuclear Regulatory Commission in accordance with the provisions of 10 CFR 50.59 at the end ofeach 12-month period:

(1) Tabulation of major preventive and corrective maintenance operations having safety significance.

(2) Tabulation of major changes in the reactor facility and procedures that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were involved.

(3) A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the owner-operator as determined at or before the point of such release or discharge. The summary shall include to the extent practicable an estimate ofindividual radionuclides present in the effluent.

(4) A summarized result of any environmental surveys performed outside the facility.

(5) A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed or recommended.

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l 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.6.2 Special Reports  !

l (1) There shall be a report no later than the following working day by telephone to i the appropriate NRC Regional Office and confirmed in writing by telegraph or j similar conveyance to the Nuclear Regulatory Commission, in accordance with l

instructions in 10 CFR 50.4, to be followed by a written report that describes the i circumstances of the event within 14 days of any of the following-i

a. Release of radioactivity from the site above allowed limits (see 6.5.2),

b. Any of the following (see 6.5.2):

(i) Abnormal and significant degradation in reactor fuel, or cladding, or both, '

or coolant boundary which could result in exceeding prescribed radiation I exposure limits of personnel or environment, or both.

l (ii) An observed inadequacy in the implementation of administrative or  :

procedural controls such that the inadequacy causes or could have caused  :

the existence or development of an unsafe condition with regard to fuel transfer operations. l 6

(2) A written report within 30 days to the Nuclear Regulatory Commission m j accordance with instmetions in 10 CFR 50.4, concerning the following: -

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a. Permanent changes in the organization involving the Facility Director,  !

Reactor Manager, or Radiation Safety Officer.  !

b. Significant changes in the transient or accident analysis as described in the  ;

Safety Analysis Report. l t

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L 6.0 ADMINISTRATIVE CONTROLS (Continued) l 6.7 Records 6.7.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component ifLess than Five Years j_ (1) Normal reactor facility operation (but not including supporting documents such as checklists, log sheets, etc., which shall be maintained for a period of at least one year).

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(2) Principal maintenance operations.

(3) Reportable occurrences.

l (4) Surveillance activities required by the Technical Specifications.

(5) Reactor facility radiation and contamination surveys where required by applicable regulations.

(6) Experiments performed with the reactor.

(7) Fuel inventories, receipts, and shipments.

(8) Approved changes in operating procedures.

(9) Records of meetings and audit reports of the Reactor Use Committee. t 6.7.2 Records to be Retained for at Least One Training Cycle Retraining and requalification oflicensed operators: Records of the most recent complete cycle shall be maintained at all times the individual is employed.

6.7.3 Records to be Retained for the Lifetime of the Reactor Facility Applicable annual reports, if they contain all of the required information, may bc used as ,

records in this section.

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(1) Gaseous and liquid radioactive effluents released to the environs.

(2) Off-site environmental monitoring surveys required by the Technical Specifications.

(3) Radiation exposure for all personnel monitored.

(4) Drawings of the reactor facility.

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6.0 ADMINISTRATIVE CONTROLS (Continued)

I LEVEL 1 University President V  !

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Provost Vice President Business & Finance if if if Dean of Radiation Safety Director of Engineering Committee Environmental Health & Safety V V Facility Reactor Use 4 Director Committee V V LEVEL 2 Radiation Reactor Safety Officer Manager V i LEVEL 3 y l Reactor Health Physics i Operations Staff Staff Committee membership i Ii 1

Figure 6-1. Organization Structure 6-11