ML20244D249

Amend 7 to License R-114,converting License to Possession Only Status

ML20244D249
Person / Time
Site:	05000294
Issue date:	06/07/1989
From:	Holahan G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20244D245	List: ML20244D243 ML20244D249 ML20244D258
References
R-114-A-007, R-114-A-7, NUDOCS 8906160185
Download: ML20244D249 (24)

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MICHIGAN STATE UNIVERSITY DOCKET NO. 50-294 AMENDMENT TO FACILITY LICENSE Amendment No. 7 License No. R-114

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment filed by the Michigan State University (the licensee), dated Decen.ber 1,1988, as supple-1988, complies with the standards and mented onofDecember requirements the At 14,6mic Energy Act of 1954, as amended (th and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is renonable assurance: (1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common 1 defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CFR Part 51  !

of the Commission's regulations and all applicable requirements have  ;

been satisfied; and  !

F. Publication of notice of this amendment is not required since it does 1

i not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).

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2. Facility License No. R-114 is hereby amended in its entirety to read as follows:

A. The license applies to the TRIGA Mark I type nuclear reactor (hereinafter referred to as the facility) which is owned by the Michigan State University and located on the campus in East Lansing, Michigan and described in the application for conversion dated December 1,1988, as supplemented on December 14, 1988.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Michigar> State University:

1. Pursuant to Section 104c of the Act and 10 CFR Part 50,

" Domestic Licensing of Production and Utilization Facilities,"

to possess, but not operate, the facility in accordance with procedures and limitations set forth in this license;

2. Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to possess up to 2 grams of contained uranium 235 in connection with reactor instrumen-tation (fission chamber).

3. Pursuant to the Act and 10 CFR 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material,"

to possess for stprage only a 3 curie sealed americium-beryllium neutron' source, and to possess, but not to separate, such byproduct material as may have been produced by operation of the reactor.

C. The license shall be deemed to contain and is subject to the condi-tions specified in Parts 20, 30, 50, 51, 55, 70 and 73 of 10 CFR Chaptcr 1, to all applicable provisions of the Act, and to the rules, regulations, and orders of the Commission now or hereafter in effect and to the additional conditions specified below:

1. Operation The licensee shall not operate the reactor nor install fuel or experiments within the reactor core or core area.

2. Technical Specifications l

l The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, are hereby incorporated in the license.

The licensee shall maintain the facility in accordance with the Technical Specifications.

D. This ifcense amendment is effective as of the'date of issuance and shall expire on February 15, 1998._  !

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- FOR THE NUCLEAR REGULATORY COMMISSION Yay?^f l Gary M. Holahan,' Acting Director Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Date of Issuance: June 7, 1989 i

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1 APPENDIX A -

1' FACILITY LICENSE NO. R-114 -i TECHNICAL SPECIFICATIONS FOR THE MICHIGAN STATE UNIVERSITY l- TRIGA REACTOR REVISION 3 JANUARY 1989 l~

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.c TABLE OF CONTENTS

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I n t ro d u c t i on . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1; -j

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1.0' Definitions...............................................'.. 1-1 l

2.0 , Safety Limits and Limiting Safety System Settings........... . 2-1" 3.0 Li mi ti ng Condi tions for. 0perati on. . . . . . . . . . . . . . . . . . . . . . . . . . . .3-1 -

.i 4.0 , Surveillance Requirements-.................................. 1:

4.1 Genera 1...............................................; 4-1

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4.2 Limi ting Condi tions for Posses sion Only. . . . . . . . . . . . . . . ' 4-2'.- 1 l

5.0 Design Features.............................................. 5-1 J 5.1 Radi ation Moni tori ng . System. . . . . . . . . . . . . . . . . . . . . . . . . . . ;5-1 5.2 Reactor Building and Ventilation' System............... 5-2 .i O 5.3 Reactor P m water Systems............................ 5-3 6.0 Administrative Controls..................................... 6-1 6.1 Organization......................................... 6-l '

6.2 Review and Aud1t..................................... 6-2 i 6.3 Facility Operating Records........................... 6-4 6.4 Operating Procedures................................. 6-5 i

6.5 Reporting Requirements................................ 6-6.  ;

1 l 6.6 Facility Access Contro1.............................. 6-6 j l

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t' Included'in this document are the. Technical Specifications and the " Bases" for-the Technical Specifications. These bases, which provide the technical  !

support for the individual technical specifications, are included for information purposes only. They are not part of the Technical Specifications, j

.j and they do not constitute limitations or requirements to which the licensee 1

must adhere.

l l The dimensions, measurements and other numerical values given in these f specifications may differ from measured values owing to normal construction and manufacturing tolerances, or normal accuracy of instrumentation.

1.0 DEFINITIONS 1.1 Abnormal-Occurrence An " Abnormal Occurrence" is defined for the purposes of the reporting j

,g requirements of Section 208 of the Energy Reorganization Act of 1974 ]

O (P.L.93-438) as an unscheduled incident or event which the Nuclear l Regulatory Commission det. ermines is significant from the standpoint of 1 public health or safety. ,

i Reactor Comoonents The following definitions pertain to the various components that are 1

part of the operational Reactor. Since the Reactor fuel has been removed from the Facility, the function of these components with respect to Reactor Operations / Safety is no longer applicable. These definitions have been retained in order to support information represented in the specifications that follow.

1.2 Shim Rod A shim rod is a control rod having an electric motor drive and scram capability.

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1.3 Safetv-Transient Rod

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The safety-transient rod is a control rod with scram capability that can be rapidly ejected from the reactor core to produce a pulse.

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1.4 Reculatino Rod T,he regulating rod is a low worth control rod having an electric motor drive and scram capability.

1.5 Fuel Element A fuel element is a single TRIGA fuel rod of. standard type.

1.6 Instrumented Element s An instrumented element is a special fuel element in which a sheathed chromel-alumel or equivalent thermocouple is embedded in the fuel at the vertical center plane of the fuel element. More than one thermocouple may be located in each element.

REACTOR INSTRUMENTATION

'1.7 Safety Limit Safety limits are limits on important process variables which are found to be necessary to reasonably protect the integrity of certain of the physical barriers which guard against the uncontrolled release of i

radioactivity.

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. 1.8 Limitina Safety System Settina l

Limiting safety systems setting is the setting for automatic protective devices related to those variables having significant safety functions.

1.9 Ooerable A system, device, or component shall be considered operable when it is capable of performing its intended functions in a normal . manner.

1.10 Measured Value The measured value is the magnitude of that variable as'it appears on the output of a measuring channel.

1.11 Heasurina Channel A measuring channel is the combination of sensor, interconnecting e cables or lines, amplifiers, and output device which are connected for the purpose of measuring ,the value of a variable.

1.12 Safety Channel A safety channel is a measuring channel in the reactor safety system.

1.13 Channel Check A channel check is a qualitative verification of acceptable performance by observation of channel behavior.

1.14 Channel Test 1 A channel test is the introduction of a signal into the channel to verify that it is operable.

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1.15 Channel Calibration A channel calibration consists of comparing a measured value from the measuring channel with a corresponding known value of the parameter so that the measuring channel output can be adjusted to respond with acceptable accuracy to known values of the measured variable.

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I 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINfa5 .)

This Section has been deleted in its entirety from the Technical )

I Specifications. It previously contained specifications that pertained only to Reactor Operations (e.g. fuel element temperature limit (s), f etc.) Since all Reactor fuel has been permanently removed from the' ]

site, these specifications are no longer applicable.

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l 3.0 LIMITING CONDITIONS FOR OPERATION

's Anolicability 1 i

This' specification applies to the operational status of the Reactor..

Obiective The objective is to ensure that the Reactor;is no longer operated under the " Possession Only" license status.

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- Specifications Receipt and/or handling of Reactor fuel is no longer authorized under .i

-l the conditions of License R-114.

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l Basis It has been decided that the Reactor is to.be shutdown pemanently and the Facility decommissioned. Hence, the fuel has been shipped off-site l

i to a qualified recipient and the license modified to a " Possession' Only" status. This current license status no longer allows the receipt, handling or use of fuel in the Reactor Facility.

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l 4.0 SURVEILLANCE REQUIREMENTS 4

4.1 General q 1

1 Anolicability This specification ~ applies to the surveillance requirement's of the l

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systems related to safety at.the Reactor Facility.- )

I Obiectivt.

The objective is to verify the proper operation of the systems related ]

to safety at the Reactor Facility.

J Specifications u

'i Any additions, modifications, or maintenance to the ventilation' system,

.3 the core and its associated support structure, the pool or its

,J penetrations, the pool coolant system, the rod drive mechanism, or the- .,

reactor safety system shall be made and tested in accordance with the $

1 specifications to which the systems were originally designed and 1 i

l fabricated or to specifications approved by the Reactor Safety -

Committee. A system shall not be considered operable until after it is successfully tested.

Bases 4 c

This specification relates to changes in reactor systems which could directly affect safety at the Reactor Facility. As long as changes or l

replacements to these systems continue to meet the original design specifications, then it can be assuened that they meet the presently accepted operating criteria.

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- 4.2 Limitina Conditions for " Possession Only"

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4.2.1 Radiation Monitorina' System Anolicability This specification applies to the surveillance requirements for the area radiation monitoring equipment and the continuous air

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monitoring system.

Obiective The objective is to assure that the radiation monitoring equip-ment is operating and to verify the appropriate alarm settings.

Specifications The area radiation monitoring system and .the continuous air. ,

monitoring system shall be' calibrated annually but at intervals not to exceed 14 months and shall be verified to be operable at monthly intervals.

Bases The current inventory of radioactive material is made up of only the neutron activated reactor components and bio-shield, fission chamber, and neutron start-up source (the fuel has been shipped off-site). ~ Therefore, monthly verification of area radiation and air monitoring system set points in conjunction with annual' calibration is adequate to correct for any variation in the system due to a change of operating characteristics over a'long time span.

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4'.2.2 Ventilation System

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Aeolicability 1

This specification. applies to the Reactor Facility ~ ventilation.~

system.

l Obiettive l

The objective is to assure the proper operation of the l

ventilation system in controlling releases of radioactive :

material to the uncontrolled environment and to provide adequate-building climate control to minimize deterioration of electronic monitoring and/or other equipment located within.the Facility.

. Specification .,

l It shall be verified monthly that the ventilation system is operating properly. l l1 Basis 1

-t Experience accumulated over several years of operation indicate that monthly operational tests of this system are sufficient.to provide assurance that~this system is operating properly in meeting the objective of this specification.

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5.0 DESIGN FEATURES t

5.1 Radiation Monitorina System Aeolicability This specification describes the functions and essential components of the area radiation monitoring equipment and the system for continuously monitoring airborne radioactivity.

Obiettive The objective is to describe the' radiation monitoring equipment that is available to monitoring personnel to assure safe storage of the radioactive components / materials contained in the Reactor Faciltiy.

Specifications i

h The radiation monitoring equipment listed in the following table will be available at the React.or Facility Radiation Monitorino Channel And Function Area Radiation Monitor (gamma sensitive instruments)

Function-Monitor radiation fields in key locations, alarm and readout at control console.

Continuous Air Radiation Monitor (Beta, Gamma sensitive detector with air collection capability)

Function - Honitor concentration of radioactive particulate activity in building, alarm and readout at control console.

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flaiti The radiation monitoring system is intended to provide information to monitoring personnel of any impending or existing danger from radiation so that there will be sufficient time to take necessary steps to prevent the spread of radioactivity to the surroundings.

5.2 Reactor Buildino and Ventilation System i Aeolicability This specification applies to the building which houses the reactor.

Obiettive The objective is to assure that provisions are made to minimize the release of radioactivity into the environment.

Specifications .

a, The reactor shall be housed in a facility designed to restrict leakage. The minimum free volume in the facility shall be 2 x 108 cubic centimeters. .

b. The reactor laboratory shall be equipped with a ventilation system designed to filter and exhaust air or other gases from the reactor laboratory and release them from a stack at a minimum of 13.7 meters from ground level. The filter shall be used during emergency situation specified by the continuous air monitor or by the operator.

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c. Emergency filtering controls for the ventilation system shall be located in the control room and the system shall be designed to filter in the event of a substantial release of fission products.

Illiti The facility is designed such that the ventilation system will normally maintain a negative pressure with respect to the atmosphere so that there will be no uncontrolled leakage to the environment. The free air volume within the reactor laboratory is confined when emergency

) - filtering is being performed. Controls for emergency filtering and normal operation of the ventilation system are located in the control room. Proper handling of airborne radioactive materials (in emergency situation) can be conducted from the control room with a minimum of exposure to operating personnel.

5.3 Reactor Pool Water SysterU ADD 11cability

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This specification applies to the pool containing the reactor components.

Obiettive The objective is to assure that water shall be available to provide adequate radiation shielding.

Specifications

a. The pool water level shall be maintained at least 5.48 meters above the top grid plate of the core.

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i- b. The pool water shall be. sampled for conductivity at least monthly. Conductivity shall not exceed'5 micromhos per centimeter.

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a. This specification assures that adequate shielding of the activated Reactor components and materials is provided by the pool water.

b. The water conductivity is an indicator of the water purity and can be used to monitor for the leakage of ground water into t'he tank. Maintaining low conductivity readings should allow early detection of leaks of this type.

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4 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization The facility shall be under the direct control of the Reactor Supervisor or a qualified individual designated by him to be in direct control. The Supervisor shall be responsible to the Dean of the College of Engineering and the Assos:iate Dean for Graduate Studies and

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Research for safe operation and maintenance of the reactor and its associated equipment. The Supervisor or his appointee shall enforce rules for the protection of personnr1 against radiation.

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,- 6.2 Review and Audit I.

a. A Reactor Safety Committee (RSC) of at least three (3) members knowledgeable in fields which relate to Nuclear Safety shall review, evaluate, and approve safety standards associated with use of the facility.' The University Radiation Safety Officer and the Reactor Supervisor shall be members of the Reactor Safety Comittee. The jurisdiction of the RSC shall include all nuclear operations in the facility and general safety standards.

b. The operations of the Reactor Safety Committee shall be in accordance with a written charter, including provisions for:

(1) Meeting frequency, (2) Voting ruies, (3) Quorums, j (4) Hethod of submission and content of presentation to the Comittee, and (5) Use of subcommittees. ,

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c. The RSC or a Subcommittee thereof shall review reactor Facility J status at least quarterly, but at intervals not to exceed four '

months.

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.' REACTOR SAFETY COMMITTEE ORGANIZATIQH PRESIDENT PROVOST AND V.P. roR 1 ACADEMIC AFFAIRS I

I I V.P. FOR RESEARCH ~

l DEAN OF ENGINEERING AND --

1 GRADUATE STUDIES I I I I

REACTOR SAFETY l COMMITTEE OFFICE OF RADIATION, I CH.EMICAL AND - -l i BIOLOGICAL SAFETY l 1 I l

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DIRECTOR - D.E.R. I I I .

I ADVISORY l  !

I DIv. ENGINEERING RESEARCH I COMMITTEE FOR --

1 I RADIATION,  !

l I CHEMICAL AND i I l BIOLOGICAL i 1 SAFETY l---. REACTOR SUPERVISOR --

l 1 NUCLEAR REACTOR LABORATORY i

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ADVISORY  !

DIRECT i

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i d. The responsibilities of the committee or designated I, Sub-committee thereof include, but are not limited to, the following:

(1) Review and approval of all proposed changes to the facility -

procedures, and Technical Specifications; (2) Review of unusual or abnormal occurrences and incidents which are reportable under 10 CFR Part 20 and 10 CFR Part 50; (3) Review of abnormal performance of facility equipment.~

6.3 Facility Operatina Records In addition to the requirements of applicable regulations, and in no way substituting therefor, records and logs shall be prepared for at least the following items and retained for a period of at least five years for items a thru c and indefinitely for items d through g.

a. Principal maintenance activities,

b. Equipment and component surveillance activities required by the Technical Specifications, t

c. Gaseous and liquid radioactive effluents released to the environs,

d. Offsite environmental monitoring surveys,

e. Facility radiation and contamination surveys,

f. Radiation exposures for all personnel, and

g. Updated, corrected, and as-built drawings of the facility.

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( 6.4 Qperatina Procedures Written operating procedures shall be adequate to assure the safety of operation of the reactor, but shall not preclude the use of independent judgment and action should the situation require such. Operating procedures shall be in effect for the following items;

a. Testing and calibration of area radiation monitors and air particulate monitors;

b. Radiation safety procedures and emergency situations. l

c. Civil disturbances on or near the facility site.. Substantive changes to the above procedures shall be made only with the approval of the Reactor Safety Committee. Temporary changes to the procedures that do not change their original intent may be made by i the Supervisor or his designated alternate. All such temporary l h changes shall be documented and subsequently reviewed by the Reactor Safety Committee. .

l 6.5 Reoortina Requirements l

In addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC Region III, Regional Administrator as follows:

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph.

Any accidental release of radioactivity above permissible limits in unrestricted areas whether or not the release resulted in property damage, personal injury, or exposure. In addition, a report shall be filed for any exposure of personnel in excess of approved NRC levels.

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( b. A report within 10 days in writing of:

Any accidental release of radioactivity above permissible limits-in unrestricted areas whether or not the release resulted in property damage, personal injurf or exposure; and, any exposure of personnel in excess of approved NRC levels.. The written report (and, to the extent possible, the preliminary telephone or telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event; ,

c. A report within 30 days in writing of:

1. Any changes in facility organization; and

2. Any observed inadequacies in the implementation of administrative or procedural controls.

l 6.6 facility Access Control , ,

Access to the HSU TRIGA Reactor Facility shall be controlled by the Reactor Supervisor and the Reactor Supervisor's designees. The Facility shall be kept locked before and after normal working hours. I I

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