ML20216E743

Amend 16 to License R-76,adding Requirements to TSs for Use of Washington State Univ Research Reactor Boron Neutron Capture Facility for Experimental Purposes Not to Involve Irradiation of Human Beings

ML20216E743
Person / Time
Site:	Washington State University
Issue date:	04/13/1998
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216E734	List: ML20216E729 ML20216E743 ML20216E760
References
R-76-A-016, R-76-A-16, NUDOCS 9804160288
Download: ML20216E743 (15)

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,- o E NUCLEAR REGULATOR) COMMISSION f WASHINGTON, D.C. 200.MMIO1

. . . . . ,o WASHINGTON STATE UNIVERSITY DOCKET NO. 50-27 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. R-76 I

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

A. The application for amendment to Facility Operating License No R-76 filed by the Washington State University (the licensee), dated September 25,1995, as supplemented on January 8,1996, February 23,1996, May 15,1997, and February 20,1998 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; )

l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized 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 Commission's regulations; D. The issuance of this amendment wili '1ot be inimical to the common defense and security or to the health and safet

• of the public; E. The issuance of this amendment is in acct.-dance with 10 CFR Part 51 of the Commission's regulations and all applicable ;'quirements have been satisfied; and F. Prior notice of this amendment was not required ) y 10 CFR Part 2.105 and publication of notice for this amendment is not aquired by 10 CFR Part 2.106.

2. Accordingly, the license is amended by changev to the Technical Specifications as indicated in the enclosure to this license amendment. Section 2.C.(2) of Facility Operating License No. R-76 is hereby amended to read as follows:

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2 4 (2) Technical Scecifications ,

l The Technical Specifications contained in Appendix A, as revised l through Amendment No.16, are hereby incorporated in the license.

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

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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l Marvin M. Mendonca, Acting Director

! Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management l Office of Nuclear Reactor Regulation l

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Enclosure:

j Appendix A Technical l Specifications Changes l Date of issuance:

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[ ENCLOSURE TO LICENSE AMENDMENT NO.16 FACILITY OPERATING LICENSE NO. R-76 DOCKET NO. 50-27 l

l l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.

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3.15 GENERATION OF BORON NEUTRON CA5'TURE FACILITY BEAM

Definitions:

1. For the purpose of this technical specification, the term 'BNC facility' shall refer to the

, boron neutron capture facility which includes the beam, bridge moving system, beam l 1

l monitoring equipment, beam shielding room, access gate and experimental area viewing equipment. The experimental bench, positioning equipment, and other equipment used for i

the beam targets are not considered pan of the BNC facility for purposes of this provision, l

except insofar as radiation safety (i.e., activation and/or contamination) is concemed. I l

2. The term 'BNC experiment'shall refer to a baron neutron capture experiment involving the neutron irradiation of biological cells enriched with boron.

3. The term ' calibration check' refers to the process of checking the beam intensity and quality i via one or more of the following: foil activation; use of a fission chamber, use of an ion chamber, or an equivalent process. The pugose of a calibration check is to ensure that the beam has not changed in a significant way (e.g., energy spectrum or intensity) from the beam that was characterized.

4. The term ' functional check of the beam monitors' shall consist of verifying that system I output is consistent (i 10%) with previously measured values upon normalization to a common reactor neutronic power level.

5. The term ' characterization' refers to the process of obtaining the dose-versus-depth profile in phantoms. The dose-versus depth profile from the surface of the phantom to a depth at least equivalent to the total thickness of the target volume to be irradiated on a central axis is deemed adequate for a characterization. Fast neutron, thermal neutron, and gamma ray components are determined in a characterization and monitors are normalized by this characterization.

6. The term ' calibration of the beam monitors' refers to the process whereby the beam monitors are calibrated against instruments that measure dose including a tissue equivalent I

chamber and a graphite or magnesium wall ionization chamber ( or the equivalent to any of these three) that have in turn been calibrated by a secondary calibration laboratory.

7. The tenn

• design modification' as applied to the BNC facility beam refers (a) to a change l, that is shown to alter the dose-versus-depth profile of the fast neutir,ns, thermal neutrons, or gamma rays in the beam as sensed by the calibration check and (b) to a change that has l

the potential to increase significantly the amount of activation products in de BNC facility.

8. The tenn ' radiation fluence' means the total fluence of neutrons and gamma radiation that is emitted in the BNC facility beam. The determination of the ratios of gamma, fast neutron, and thermal neutron fluences is part of the beam characterization. Knowledge of these ratios allows the total radiation fluence to be monitored by de on-line detectors, which are neutron sensitive. Compliance with the limits specified on radiation fluence by this specification is detennined by reference to the fluence monitored by these detectors.

Annlienhility:

This specification applies solely to the generation of the BNC facility beam for BNC experiments. It does not apply to any other use of the BNC facility and/or its beam. Surveillances listed in this specification are required only if BNC experiments are planned for the interval of the surveillance. However,in the event of a hiatus in the scheduled performance of any given surveillance, that surveillance shall be performed prior to the initiation of BNC experiments during the intervalin question.

Ob#tive:

To acquire testing and operational experience in use of a facility developed specifically for Boron Neutron Capture Technology.

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.i Specificatione

1. It shall be possibi sto initiate a scram of the reactor from a control panel located in the BNC '

facility arer. In the event that the BNC facility scram is inoperable, it'shall be acceptable to use c e of the control room scrams via communication with the reactor operator as a teingereiy means of satisfying this provision.' Une of this temporary pmvision is limited to l

seven consecutive working days.

2. Access to the BNC facility shall be controlled by means of the access gate located at its l

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3. - The following features and/or interlocks shall be operable:

l (a) - An interlock shall prevent moving the bridge fmm the retracted position unless the BNC facility's access gate is closed.

(b) The reactor shall scram and the bridge shall move to the retracted position l automatically upon opening the treatment room's access gate.

l _(c) The bridge shall be designed to move to the retracted position automatically upon i

L failure of facility electric power or low voltage on the backup batteries that power the bridge motor.

l (d) Bridge movement that contmls beam delivery shall be designed for manual

(_ movement to the retracted position.

(e) It shall be possible to move the bridge to the retracted position from within the BNC facility.

(f) A BNC facility lockdown near the access gate shall inhibit blade withdrawal when l the key is not inserted and tumed to the locked position.

l 4.. Bridge shall be equipped with a position readout that indicates the status of the bridge. A bridge position readout shall be visible at the BNC facility's local control panel. In the event of a bridge position readout malfunction,it shall be acceptable to use an alternate means of verifying position such as a video camera in the pool room providing a signal to a l

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monitor at the BNC facility's local control panel. Use of this alternate means of bridge position verification is limited to seven consecutive working days.

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5. De BNC facility shall be equipped with a read out display of the reactor log-power and the linear power on the BNC facility control console just outside of the shielding.

6. The BNC facility shall be equipped with a monitor that provides a visual indication of the -

radiation level within the facility, that indicates both within the facility and at the local control panel, and that provides an audible alarm both within the facility and at the local l contml panel. I' l (a) This radiation monitor shall be equipped with a backup power supply such as the L reactor emergency power system or a battery. J (b) This radiation monitor shall be checked for proper operation by means of a check source on the calendar day of and prior to any BNC experimentation.

(c) This radiation monitor shall be calibrated quarterly.

(d) The audible alarm shall be set at or below 50 mR/hr. This monitor and/or its alarm

, may be disabled once the BNC room has been searched and secured, such as is done l

immediately prior to initiation of BNC experimentation. If this is done, the monitor and/or its alann shall be interlocked so that they become funcuonal upon opening of the BNC facility access gate.

(e) In the event that this monitor is inoperable, personnel entering the BNC facility shall use either portable survey instruments or audible alarm personal dosimeters as a L temporary means of satisfying this provision. These instruments / dosimeters shall be in calibration as defined by the .WSU Researth Reactor's, radiation protection program and shall be source-checked daily prior to use on any day that they are used to satisfy this provision. Use of these instruments / dosimeters as a temporary means of satisfying tFs provision is limited to seven consecutive working days.

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7. An intercom or other means of two-way communication shall be operable both between the BNC facility control panel and the reactor control room, and also between the BNC facility control panel and the interior of the BNC facility shielding.

8. It shall be possible for personnel monitoring a BNC experiment to open the BNC facility access gate manually.

9. It shall be possible to observe the BNC experiment by means of two independent closed-circuit TV cameras. Both cameras providing visualization shall be operable at the outset of any BNC experiment. Should either fail during the irradiation, the experiment may be continued at the discretion of the experimenter. Adequate lighting to permit such vier bg shall be assured by the provision of emergency lighting and backup power for one TV camera and mocor.

10. The following interlocks or channels shall be tested at least monthly and prior to a BNC experiment if the interlock or channel has been repaired or dcenergized:

interlock or Channel Surveillance a) The tractor scrams and the bridge Scram test retracts upon BNC facility scram b) Bridge will not move from the retracted Operational test position unless access gate is closed c) Upon opening the BNC room's access Operational test gate the reactor scrams and the bridge moves to the retracted position d) Upon opening only the bridge retraction Operational test switch on the access gate of the bridge retracts e) The bridge moves toward the retracted Operationd test position on loss of electrical power and low voltage on the bridge motor batteries

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l f) Manual movement of bridge Operational test g) Bridge can be moved manually Operational test by someone standing on the reactor bridge h) Bridge position indicator and status Operational test lights i) Radiation monitor alarm Opentional test j Radiation monitor and/or alarm Opemtional test enabled upon opening of shield door k) Interroms Opemtional test

1) BNC facility TV cameras, monitors and Operational test its power backup m) BNC facility emergency lighting Operational test n) BNC facility lockdown blade inhibit Operational test In addition to the above, the BNC facility scram shall be tested prior to reactor startup if the reactor has been shut down for more than sixteen hours.

I 1. Manual operation of the BNC facility's access gate in which the door is opened fully shall be verified semi-annually.

12. Use of the BNC facility beam shall be subject to the following:

a) A calibration check of the beam and a functional check of the beam monitors shall be made weekly for any week that the beam will be used for BNC experiments. .

These checks shall be made prior to any BNC experiment for a given week. . In addition, a calibration check shall be performed prior to any BNC experiment in the j event that any component of a given beam design has been replaced. Finally, a calibration and a functional check shall be perfoimed prior to any BNC experiment in the event of a design modification.

I b) A characterization of the beam shall be performed every six montris for any six-month interval that the beam will be used for BNC experiments. This six-month

! characterization shall be made prior to any BNC experiment for a given six-month interval. A characterization shall also be pedormed prior to any BNC experiment in the event of a design modification. As part of the characterization process, the proper response of the beam monitors shall be verified.

c) A calibration of the beam monitors shall be performed at least once every two years for any two-year interval that the beam will be used for BNC experimentation. The two-year calibration shall be made prior to any BNC experimentation during any given two-year interval.

d) A scram from full power initiated when the reactor is positioned against the BNC facility filter shall be performed every six months or in the event of a design modification. The BNC room radiation monitor reading shall not exceed 50 mR/hr, 30 seconds after the initiation of the scram and bridge retraction.

13. Maintenance, repair, and modification of the BNC facility shall be performed under the supervision of a senior reactor operator who is licensed by the U.S. Nuclear Regulatory Commission to operate the WSU Research Reactor. All modifications will be reviewed pursuant to the requirements of 10 CFR 50.59.

14. Personnel who are not licensed to operate the WSU Research Reactor but who are responsible for either the BNC or the beam's design including construction and/or modification may operate the controls for the BNC facility beam provided that:

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(a) Training has been provided and proficiency satisfactorily demonstrated on the j design of the facility,its controls, and the use of those controls. Proficiency shall be demonstrated annually.

(b) Instmetions are posted at the BNC facility's local control panel that specify the procedure to be followed:

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(i) to ensure that only the appropriate target is in the irradiation facility before tuming the primary beam of radiation on to begin an irradiation; (ii) if the operatoris unable to turn the primary beam of radiation off with controls outside the BNC facility, or if any other abnormal condition occurs. A directive shall be included with these instructions to notify the reactor console operator in the event of any abnormality.

l (c) In the event that bridge movement affects reactivity, personnel who are not licensed on the WSU Research Reactor but who have been trained under this provision may initiate bridge movement provided that verbal permission is requested and received from the reactor console operator immediately prior to such action. Emergency  !

scrams causing a bridge retraction are an exception and may be made without first requesting permission.

Records of the training provided under subparagraph (a) above shall be retained in accordance with the WSU Researth Reactor's training program or at least for three years.

A list of personnel so qualified shall be maintained in the reactor control room.

Basis The requirement that it be possible to initiate a scram from a control panel located in the BNC facility area assures the experimenter of the capability to terminate the irradiation immediately should the need arise. The provision that access to the BNC facility be limited to a single gate ensures that there will be no inadvertent entries. The various interlocks for the bridge movement system that controls beam delivery ensure that exposure levels in the BNC facility will be minimal prior to entry by personnel. He bridge position indicator and status lights serve to notify personnel of the beam's status. The provision for a radiation monitor ensures that personnel will have information available on radiation levels in the BNC facility prior to entry. The purpose of i

this monitor's audible alarm is to alert personnel to the presence of elevated radiation levels. This  !

l monitor and/or its alarm may be disabled once the BNC facility has been searched and secured so l

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that it will not distract attending personnel. De monitor and/or its alann are interlocked with the access gate so that they are made functional upon opening that gate, and hence prior to any possible entry to the BNC facility. One intercom provides a means for the prompt exchange ofinformation between the experimenter (s) and the reactor operator (s).

he provision for manual operation of the BNC facility's access gate ensures access to the experimental area in the event of a loss of electrical power. De presence of the closed-circuit TV cameras provide the experimenter (s) with the opportunity to monitor the target area visually as well as through the use of various instruments. The emergency lighting and the backup power for a TV camera and monitor will pennit visual surveillance of the target area in the event of a power failure.

he surveillance requirements for beam calibration checks and characterizations provide a mechanism for ensuring that the BNC facility and its beam will perform as originally designed.

Similarly, the surveillance requirements on the bean monitors ensure that these instruments are calibrated by a means traceable to the National Institute of Standards and Technology. The chambers specified (tissue-equivalent, and graphite or magnesium-wall) were chosen because they measure dose as opposed to fluence.

De specifications on maintenance and repair of the BNC facility ensures that all such activities are performed under the supervision of personnel cognizant of quality assurance and l

other requirements such as radiation safety. The provision on the training and proficiency of non- l I

licensed personnel ensures that all such personnel will receive instruction equivalent to that given to l licensed reactor operators as regards use of the BNC facility beam. (Note: Licensed reactor operators may, of course, operate the BNC facility beam.) Also, this provision provides for the posting ofinstructions to be followed in the event of an abnormality.  ;

References 6.5-1 MITR Staff," Safety Analysis Report for the MIT Research Reactor (MITR-II)," Report No. MITNE-115,22 Oct.1970, Section 10.1.3.

4 6.5-2 Choi, R.J.," Development and Characterization of an Epithermal Beam for Boron Neutron Capture Therapy at the MITR-II Research Reactor," Ph.D. 'Ihesis, Nuclear Engineering Department, Massachusetts Institute of Technology, April 1991.

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