ML20044G544

Procedures for Conduct of Human Irradiations W/Mit Medical Therapy Facility

ML20044G544
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	05/28/1993
From:	MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE
To:
Shared Package
ML20044G535	List: ML20044G534 ML20044G544
References
PROC-930528, NUDOCS 9306030281
Download: ML20044G544 (190)

Text

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e i PM 3.14 Page 1 of 2 g Procedure Authorization Qg 3.14 MedicalThempy Facility Procedures 3.14.1 Test and Calibrations 3.14.1.1 Test of Requimments Listed in MITR Technical Specification No. 6.5 SR#-0-93-5 05/28/93 3.14.1.2 Calibmtion of Medical Therapy Facility Radiarian Monitor SR#-0-93-5 05/28/93 3.14.1.3 Soume Check and Alarm Operability Test SR#-0-93-5 05/28/93 of Medical Herapy Facility Radiation Monitor .14 1.4 Test of Patient Positioning System SR#-0-93-5 05/28/93

s. %.5 Verification of Neutmn Beam Geometric SR#-0-93-5 05/28/93 Center 3.14.1.6 Sensitivity Test of the Medical Therapy Room Beam Monitors SR#-0-93-5 05/28/93 3.14.1.7 Activation Test of Patient Positioning System SR#-0-93-5 05/28/93 3.14.1.8 Surveillance Schedule for Medical l (]

Therapy Facility Procedures SR#-0-93-5 05/28/93 Lj 3.14.2 Beam Evaluation 3.14.2.1 Functional Check of the Medical Therapy Facility Beam Monitors SR#-0-93-5 05/28/93 3.14.2.2A Calibration Check of the Medical Therapy Beam via Chamber Measurements SR#-0-93-5 05/28/93 t 3.14.2.2B Calibration Check of Medical Therapy Facility Beam via Foil Activation SR#-0-93-5 05/28/93 3.14.2.2C Calibration Check of Medical Therapy Facility Beam via the Dual Ion Chamber Technique SR#-0-93-5 05/28/93 3.14.2.3 Beam Monitor Plateau and Discrimmator Setpoint Tests S R#-0-93-5 05/28/93 3.14.2.4 Characterization of the Medical herapy Facility Beam SR#-0-93-5 05/28/93 3.14.2.5 Cross-Calibration of Electrometers SR#-0-93-5 05/28/93 l o 'O SR#-0-93-5 MAY 281993 i k

i PM 3.14 Page 2 of 2 1 Procedure Authorintion Dag i t' i 3.14.2.6 Calibration and Stability Check of l Ionization Chambers and Electrometers S R#-0-93-5 05/28/93 3.14.2.7 Determination of High Purity _Ge or Ge(Li) DetectorEfficiency - S R#-0-93-5 05/28/93 l 3.14.3 Performance of Therapy 3.14.3.1 General Preparations for Use of i the MedicalHerapy Facility Beam for Human Therapy SR#-0-93-5 05/28/93 3.14.3.2 Use of Prompt-Gamma Facility for Boron Assay SR#-0-93-5 05/28/93 t 3.14.3.3 Conduct of Human Therapy Using the Medicalherapy Facility Beam SR#-0-93-5 05/28/93 3.14.3.4 Beam Monitor System Setpoints SR#-0-93-5 05/28/93 3.14.4 Posted Instructions 4 3.14.4.1 Searching and Securing of the Medical Therapy Facility SR#-0-93-5 05/28/93 3.14.4.2 Corrective Action for Shutter Failure to Close or Other Malfunction SR#-0-93-5 05/28/93 j 3.14.4.3 FDA Notice Requirements SR#-0-93-5 05/28/93 3.14.4.4 Emergency Evacuation of a Patient from the Medica 1 Therapy Facility Room SR#4)-93-5 05/28/93 l l 3.14.4.5 Emergency Entry with Pb and Boral Shutters Open SR#-0-93-5 05/28/93 3.14.5 Training 3.14.5.1 Non-Licensed Medical Personnel Quahfication Program for Use of the MITR MedicalTherapy Facility SR#-0-93-5 ' 05/28/93 3.14.5.2 Test of Emergency Evacuation of a Patient i from the Medical'Iherapy Facility Room SR#-0-93-5 05/28/93 l i l-SR#-0-93-5 MAY 281993

I ' PM 3.14.1.1 ' Page 1 of 7 ps PM 3.14.1.1 Test of Reauirements Listed in MITR' Technical Snecification No. 6.5 i l l' Purnose: These tests verify the operability of the components and interlocks required under MITR Technical Specification No. #6.5. (Note: All tests are required monthly except that for provision #9 which is a semi-annur.l.) Prerequisites: 1. Reactor shutdown. 2. Medical Therapy Facility clear of all non-essential personnel. 3. 5 Ci Cs-137 and 25 mci (nominal) Co-60 sources available. 4. Provision #7 of this procedure should either be done by orin conjunction with personnel fmm the Reactor Radiation Protection Office. 5. All tests are to be conducted in accordance with the ALARA principle. l Procedure: O The provision numbers listed below refer to the individual clauses in Technical Specification No. 6.5. (Nete: Unless stated otherwise, the H O and D O shutters 2 2 need only be partially opened (drain time of ~ one minute) for these tests.) 1. Provision #1 No Test Required l I 2. Provision #2 No Test Reauired i l 3. Provision #3 Ooerational Test of Minor Scram Turn the medical facility control panel's ' power' and 'D 0' key switches to ) 2 their 'on' positions. j i i Reactor shutdown. i Obtain reactor start and reset rundown relays. Test the medical room minor scram.~ Check that the rundown relays drop - out. { a l 4. Pmvision #4 No Test Required i l SR#-0-93-5 MAY 281993 1 i 1.

PM 3.14.1.1 Page 2 of 7 l 5. Provision #5 Ooerational Test ofInterlocks olC Reactor shutdown and no work in progress in the medical therapy facility. 1 Depress the ' lamp-test' push button and verify that all shutter and door I position-status lights are energized. Verify that the position-status lights for the shutters that control beam delivery (Pb, Boral, and H O) and the D 0 shutter indicate closed. 2 2 Observe that the position-status light for the medical therapy facility's shield door indicates closed. Open the medical therapy facility's shield door. Observe that the position-status light for the medical therapy facility's shield door indicates open and that the ' Medical Door Open' scam alarm activates. Depress sequentially the open buttons for the lead, boral, and H O shutters. 2 Observe that they do NOT open. This verifies pmvision (a). Verify all personnel clear of medical therapy facility room. Close the medical therapy facility's shield door. Open the lead, boral, and H O shutters. 2 Open the medical therapy facility's shield door by using the electrical switch S(b at the medical therapy control panel. Observe that the lead, boral, and H O 2 shutters close. Close the medical therapy facility's shield door. Open the lead, boral, and H O shutters. 2 Open the medical therapy facility's shield door by using the electrical switch at the door. Observe that the lead, boral, and H O shutters close. This 2 verifies provision (b) for the case where the door is operated electrically. Mechanically bypass the shield door's position limit switch. Open the lead, boral, and H O shutters. 2 Remove the mechanical bypass on the shield door's position limit switch. Verify that the lead, boral, and H O shutters close. 2 Close the medical therapy facility's shield door. Open the ind, boral, and H O shutters. 2 Secure electric power to the Pb, Boral, and H O shutters by deenergizing 2 the medical therapy facility's control panel (i.e., turn the ' power' key switch to the 'off' position). im SR#-0-93-5 MAY 281993 m

PM 3.14.1.1 Page 3 of 7 Observe that the lead, boral, and H O shutters close. This verifies the first 2 p pan of provision (c). (Eqte: This determination must be made visually because the position-status lights are deenergized during this test.) Reenergize the medical therapy facility's control panel. Open the lead and boral shutters. Secure air pressure to these shutters by closing valve CV-69. Bleed air via the accumulator drain valve. (Eple: There may be some condensed moisture in the system. If so, drain it.) Observe that the lead and boral shutters close and that the yellow ' air pressure normal' light goes out. This may take one to two minutes depending on the time required for the air pressure to decrease sufficiently to operate the interlock. This verifies the second part of pmvision (c). Close the drain valve. Open valve CV-69. Open the lead and boral shutters. Operate the manual control air release valve. This action closes off the air supply and bleeds off trapped air. Close the lead and boral shutters manually. This verifies provision (d). Reset the manual control hir release valve. Activate the medical therapy facility's intercom #2. Open the medical therapy facility door and admit a person qualified in use of the medical therapy facility to the room. This person should stay in the vicinity of the therapy facility window. t Close the medical therapy facility's shield door and verify operability of the intercom. The following sequence of shutter manipulations verifies provision (e). Depress the ' lamp-test' pusi. _ utton and verify that all interior position-status lights are energized. Open the lead shutter. ) Close the lead shutter fmm within the medical therapy facility. Open the boral shutter. Close the boral shutter from within the facility. Open the H O shutter. 2 t^) o SR#-0-93-5 MAY 281993

i ) PM 3.14.1.1 i 1 Page 4 of 7 Close the H O shutter from within the facility. 2 Verify that all interior position-status lights functioned properly. Open the medical therapy facility's shield door and clear the room of personnel. Close the medical therapy facility's shield door. 6. Provision #6 Functional Check of Exterior Shutter Indicator Lights Eqic: Testing of the interior lights is done under Section 5 of this procedure. f Verify that all four lights, one for each shutter, that indicate status of a shutter, indicate closed. Fully open the lead, boral, H 0, and D O shutters. (Neln: Both the 'open' 2 2 and ' closed' position indicator lights are on whenever a shutter is in transition.) .i t Verify that the H 0, and D 0 level gauges indicate that each shutter is fully : 2 2 open. Verify that all four lights, one for each shutter, that indicate status of a shutterindicate open. Close the lead, boral, H 0, and D O shutters. 1 2 2 O 7. Pmvision #7 Operational Test of Radiation Monitor Alarm Open the medical therapy facility's shield door. Raise the setpoint of the audible alarm to an actuation value that corresponds to an exposure rate in excess of 100 mR/hr. Verify operability (i.e., that the unit responds to radiation) of the medical i therapy facility's radiation monitor using a check source. l Secure normal electrical power to the monitor._ Verify that the monitor has transferred to its backup power; supply by usmg the check source to verify operability again. This verifies provision (a). ~ Notify the control room operator that the medical therapy facility's radiation - i alarm is to be tested. i _ Position the 5 Ci Cs-137 source and/or the 25 mci Co-60 source so as to i create an exposure rate of 50 mR/hr at the detector. - Reduce the alarm setpoint until the alarm actuates. Reconi actuation level: mR/hr. Verify that both the interior and remote alarms have - actuated. This verifies provision (b). O SR#-0-93-5 ~MAY 281993 a + ,-o-- r. 1,e

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j 4 PM 3.14.1.1 Page 5 of 7 j Close the medical therapy facility's shield door and verify that both the interior and exterior alanns are deactivated. V Open the medical therapy facility's shield door and verify that both the interior and remote alarms actuate. Remove the 5 Ci Cs-137 and 25 mci Co-60 sources. 8. Provision #8 Operability Check ofIntercoms Verify operability of the medical therapy facility's intercom #1 by conducting a two-way conversation with the reactor control room. Admit a person qualified in use of the medical therapy facility to the room. Verify operability of the medical therapy facility's intercom #2 by conducting a two-way conversation from the facility's control panel. Verify passive operation of intercom #2 by leaving it in the monitor position while listening to low-level voices from the area of the patient couch. 9. Pmvidon #9 Functional Check of Manual Operation of Shield Door Unlatch the shield door fmm its linkage by pulling down the door's exterior unlatching mechanism and securing it. This action allows free movement of the door. U Open the medical therapy facility's shield door manually using the exterior winch. (Caution: Do HQI open the door past its normal full-open position.) Latch the shield door to its linkage by first releasing the door's exterior unlatching mechanism, and then electrically driving the chain to the open position so that the latch engages. Admit a person qualified on use of the medical therapy facility to the room. Mount the interior winch. Close the medical thempy facility's shield door electrically. Unlatch the shield door from its linkage by pulling down the door's interior unlatching mechanism and securing it. This action allows free movement of the door. Open the medical therapy facility's shield door ~1.5 ft. manually using the interior winch. Latch the shield door to its linkage by first releasing the door's interior unlatching mechanism and then electrically driving the chain to the open position so that the latch engages. D SR#-0-93-5 MAY 281993

PM 3.14.1.1 . Page 6 of 7 1 L Store the interior winch. Verify proper electrical operation of the shield door by opening it fully and then closing it using either the local or remote pushbuttons. i 10. Pmvision #10 - Ooerability Check of Patient Viewing Canability Verify operability of the viewing port. 1 Install and verify operability of the medical therapy facility's closed-cucmt

i TV camera including quality of picture, area of coverage, and focus.

Verify operability of all lights in medical therapy facility. i Verify operability of the battery-operated units that provide lighting on loss. l of off-site electrical power by depressing the test button for each unit and - 1 observing that the light energizes. Remove the TV camera and place it in storage _if not scheduled for near-term use. n f 11. Provision #11 - #15 No Test Reauired - ~ .l 12. Provision #16 - Postine ofInstructions O Verify that the following instructions are posted at the Medical Therapy i Facility: j a) PM 3.14.4.1, " Searching and Securing of the Medical Therapy i Facility." b) PM 3.14.4.2, " Corrective Action for a Shutter Failure to Close or Other Malfunction." c) PM 3.14.4.3,"FDA Notice Requirements." { d) PM 3.14.4.4, " Emergency Evacuation of a Patient from the Medical. l Therapy Facility Room." e) PM 3.14.4.5., " Emergency Entry with Pb and Boral Shutters open." 1 Verify that the following instruction is posted at the entrace to the l containment building: ~ a) PM 3.14.4.3, "FDA Notice Requirements." Close the medical therapy facility's shield' door. Turn the medical facility control panel's ' power' and 'D 0' key switches to 2 their 'off' positions. OO \\ SR#-0-93-5 MAY 281993

.. PM 3.14.1.1-Page 7 of 7 ' u 13. Provision #17 -#18 : - No Test Reauimd ' .1 ~ J i ~; o 1 'i i -.i a ~j j. The above tests wem completed satisfactorily. 4 i a' I i 3 i i i .,I c ? ReactorOperator '. Date - 1 1 J. i .? Senior Reactor Operator.' Dae ' o-i t y 'i i 1 er i v h'! -5 q 1 i

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l' .PM 3.14.1.2 l Page 1 of 4 PM 3.14.1.2 Calibration of Medical Thernov Fscility Radiation Monitor Pumose: ] l This procedure establishes a standard method for the calibration of the medical J therapy facility's radiation monitor. (Holt: There am two radiation monitors in the medical therapy facility. The second one is part of the MIT Research Reactor's original area monitor system and it does not fulfill the requirements of MITR Technical Specification No. 6.5.7. Its calibration is addressed elsewhere.) Acceotance Criteria: 1. The percent deviations between the expected and final dose rates for the electronic calibration are less than SE 2. The percent deviations between the measured and source-generated dose rates for. l the radiological calibration are less than 10% l 3. The soume check is satisfactory. 4. The local and remote audible alarms are operable. Backcround: l This monitor satisfies the requirements of MITR Technical Specification No. 6.5.7. O The unit consists of a Ludlum model 144-50 alarm ratemeter coupled to a model 133-6 GM detector. The ratemeter has a five decade log scale with a range of 0.02 to 20 R/h. The maximum pulse input rate is 1,000,000 per second. Pulse calibrations are therefore performed with a conversion of 0.3 pps per mR/h (20 cpm = 1 mR/h). The ratemeter is located outside the medical therapy facility and the detector is located inside the facility in close proximity to therapy room door. A local alarm is t provided with the ratemeter. In addition, the unit has been modified to provide a remote alamiinside the medical therapy room. This alarm is deactivated upon closing the medical therapy room's shield door. A limit switch located near the medical therapy room shield door reactivates it upon opening of that door. (Holg This action only occurs if the medical therapy facility's control panel is energized. The model 144-50 alarm ratemeter contains an internal battery which maintains a continuous trickle charge. In the event of loss of a power, the ratemeter and alarm-functions will continue to operate without intermption. Prereonicites: 1. Pulser and sources (5 Ci Cs-137 and 25 mci (nominal) Co-60) available. I 2. The ALARA principle is to be observed. 3. Standard electrical safety measures are to be observed because the unit operates at high voltage. SR#-0-93-5 MAY 281993 E i

PM 3.14.1.2 Page 2 of 4 i Electronic Calibration 1. Deenergize the umt. 2. Disconnect the detector fmm the ratemeter at the ratemeter connection. 3. Connect the pulser to the ratemeter using a type C to type C or other appropriate cable. 4. Energize the ratemeter. 5. Measure the voltage as indicated on the pulser / voltmeter: volts. 6. Verify that the voltage is set in accordance with the manufacturer's specifications (550 volts). If not, adjust as required and record the final value of the voltage: volts. 7. Compute the expected dose rates for pulse rates of 400; 4000; 40,000; and i 400,000 cpm. Record these on the attached data sheet. 8. Set the pulse rate at 400 cpm and record the resulting electronically-generated dose rate on the attached data sheet. Repeat for 4000; 40,000;- and 400,000 cpm. ~ 1 9. Adjust the ratemeter calibration potentiometer settings as needed so as to minimize the difference between the expected and electronically-generated dose rates. f' 10. Repeat steps (8) and (9) until the agreement between the expected and observed dose rates is optimized. Record the final values of the observed dose rates and compute the percent deviation. All values should be within 5%. i 11. Check the calibration of the remote meter (the one inside the medical therapy facility) at 400,000 cpm. Adjust if necessary, Radiological Calibration 1. Reconnect the detector to the ratemeter using the original cable. 2. Position the 5 Ci Cs-137 source and the 25 mci Co-60 source to generate a field of 0.02 mR/hr. at the detector. Record the detector reading on the i attached data sheet. 3. Repeat step (2) for fields of 0.2,2.0, and 20.0 mR/hr. _._ 4. Compute the percent deviations between the observed readings and the. source-generated radiation fields. These should not exceed 10%. i 5. If the calibration criteria is met, affix and date a calibration sticker. Otherwise, notify the Reactor Radiation Protection Officer and Reactor Superintendent. O SR#-0-93-5 MAY 281993 i

I PM 3.14.1.2 Page 3 of 4 Source Check and Alarm Onerability Test [V 1. Raise the setpoint of the audible alarm to an activation value that corresponds to an exposure rate in excess of 100 mR/hr. 2. Notify the control room operator that the medical therapy facility's radiation alann is to be tested. l 3. Position the 5 Ci Cs-137 source and 25 mci Co-60 source so as to create an exposure rate of 50 mR/hr at the detector. 4. Reduce the alarm setpoint until the alarm actuates. Record actuation level: mR/hr. Verify that both the local and remote alarms have actuated and are audible. 5. Verify that both the local and remote radiation meters indicate 50 mR/hr. l l l Calibration performed by: l Reactor Radiation Date Protection Technician Calibration verified by: ' ("3 Assistant Reactor Date V Radiation Protection Officer i Calibration reviewed by: Reactor Radiation Date Protection Officer

References:

1. Ludlum Model 177-50 Alarm Ratemeter Technical Manual 2. Ludlum Model 500 Pulser / voltmeter rm SR#-0-93-5 ' MAY 281993

] PM 3.14.1.2 : Page 4 of 4 i Medical Thernov' Room Radiation Monitor Calibration Form O A. Electmnic Calibration: Dose Rate (mR/hr) Pulse Rate (cpm) Exoected Imtial Eglal % Difference 400 4,000 40,000. 400,000 B. Radiological Calibration: Dose Rate (mR/hr). Source-Generated - Measured- % Difference 0.2 2.0 20.0 C. Source Check Response: ' m R h-1 D. Alarm Ooerability Check: Local Audible ' Remote Audible Visual Visual AcceptanceCriteria met: Yes 0-No O Performed by: Reactor Radiation Protection Technician ' .Dae-Verified by: Assistant Reactor Radiation Protection - Dae ' Officer Reviewed by: Reactor Radiation Protection Officer - Dae SR#-0-93-5 MAY 281993

i i PM 3.14.1.3 Page1of1 PM 3.14.1.3 Source Check and Alarm Operability Test of ""d'""""'"""""""'""d'"""""""""' C'J Puroose: This procedure establishes a standard method for source-checking the medical therapy facility's radiation monitor. Acceptance Criteria: The medical therapy facility's radiation monitor alarms at the 50 mR/hr setpoint specified in MITR Technical Specification No. 6.5.7. Prereonisites: 1. 5 Ci Cs-137 and 25 mci (nominal) Co-60 sources available. 2. The ALARA principle is to be observed. Procedure: 1. Raise the setpoint of the audible alarm to an actuation value that corresponds to an exposure rate in excess of 100 mR/hr. l 2. Notify the control room operator that the medical therapy facility's radiation-alarm is to be tested. O' 3. Position the 5 Ci Cs-137 source and the 25 mci Co-60 source so as to create an exposun: rate of 50 mR/hr at the detector. 4. Reduce the alarm setpoint until the alarm actuates. Record actuation level: mR/hr. Verify that both the local and remote alarms have actuated. AcceptanceCriteria met: Yes O No O Check performed by: i Reactor Radiation Protection Date Technician Check reviewed by: ReactorRadiation Protection Officer Date r . SR#-0-93-5 MAY 281993 l

PM 3.14.1.4 - Page 1 of 7 PM 3.14.1.4 Test of Patient Positionine System 0 o Pumose: Rese tests ensure that the patient positioning system can safely handle the working loads and torques and can position the patient with acceptable accuracy. Pmmauisite: The shutters that control beam delivery and the D O shutter are closed. 2 Liftine Canacity of Medical Therany Room Hydraulic System Purnose: This test ensures that the medical therapy room's hydraulic system is capable of lifung the platform, surgical couch, and patient (~ 1,000 lbs). Acceptance Criteria: The medical therapy room's hydraulic system is capable of lifting 2,000 lbs. (N_tta: As described in PM 3.14.3.3 the hydraulic system is not used to hold - the patient in position. Should this ever be considered, then the acceptance criteria should be modified to include a requirement to hold the weight at constant position for 1.5 hours.) pQ Procedure: t _ 1. Stack lead bricks or other equivalent material so that the weight on the lift is [ ~2,000 lbs. (Refer to Figure One) 2. Raise the lift via the hydraulic system to a height of one meter or more. Record height: meters. 3. Observe that the hydraulic system holds the weight at one meter for at least one minute. i i j SR#-0-93-5 MAY 281993 ) )

PM 3.14.1.4 Page 2 of 7 - Absence of Bendine of Hydraulic Piston Under Toraue ^ Puroose: This test ensures that the horizontal deflection of the ram is not excessive with the patient and couch (~825 lbs. maximum) loaded to create a moment arm of 90 cm or more. Acceptance Criterion: The maximum horizontal deflection of the ram is less than 0.5 cm. Procedure: 1. Raise the hydraulic system's piston to 100 cm. 2. Bolt a steelI-beam to the piston. _ 3. Place a load of ~825 lb's. on the I-beam so that it is 90 cm or more from the center. (Refer to Figure Two) ' 4. Measure the deflection of the piston fmm vertical. Ficasured deflection: cm. - l Liftine Canacity of Oneratine Couch ; l Pumose: This test ensures that the operating couch's lifting capacity is sufficient to raise a patient and to hold that patient in position for the duration of a therapy. l Acceptance Criterion: The operating couch's lifting capacity is capable of raising 400 lbs. a l distance of 10 cm and holding that weight at constant height for 1.5 hours. Procedure: i 1. Place a 400 lb. load on the couch. 2. Use the couch's lift to raise the load 10 cm or more. Record height: cm. 3. Observe that the couch's lift holds the weight at 10 cm for at least one hour. l i 1 px.) SR#-0-93-5 MAY 281993 1 L

I PM 3.14.1.4 l Page 3 of 7 gm Absen~ce of Horizontal Motion of Couch Durine Vertical Liftine ) ) ^# Pumose: 'Ihis test ensures that the patient is raised venically by the couch lift mechanism. Acceptance Criterion: The horizontal deviation of the couch is less than 0.5 cm during the final 10 cm oflifting the patient. (Note Any prior deviation is easily corrected thmugh use l of the plumb-bob line-of-sight to the geometric center of the lead shutter.) l Procedure: 1. Suspend a plumb bob so that it is centered on the top plate of the couch. Place graph paper below the plumb bob so as to facilitate recording its l position. (Refer to Figure Three) i 2. Raise the couch and plumb bob in increments of ~ 2 cm and record any deviation of the plumb-bob from its initial position on the attached sheet. I

Reference:

lp 1. S. Yam, " Design of Patient Positioning System, Body Phantom, and Patient Shielding 'g for the Boron neutron Capture Therapy Project at the MITR-II," M.S. Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA (Dec.1992). Tests performed by: NCT Research Scientist Date Supervisor: Senior ReactorOperator Date Results reviewed by: NRL Director Date () L) S R#-0-93-5 MAY 281993

PM 3.14.1.4 ~ Page 4 of.7 Vertical Lift Test of Couch Distance (cm) Deviation - (cm) - 0 2 4 6 8 f O 10 i Acceptance Criteda (deviation 50.5 cm) Met: Yes O ~No O Test performed by: NCF Research Scientist Date - i l Supervisor: Senior Reactor Operator Date SR#-0-93-5 MAY 281993 - 1 i ]

PM 3.14.1.4 Page 5 of 7 O Lead bricks (weights) Hydraulic system A Hydraulic jxk an Foot Peddle xcm N Q V Floor V M Friction lock I Piston b H crank Figure One Lifting capacity test of the hydraulic system O O SR#-0-93-5 MAY 281993 i

i PM 3.14.1.4 i Page 6 of 7 ] GCL I dx l I I I I Lead 1 I bdeks il i 14 LX E Steel If I-beam 1/4" 4x1 II \\y Ii 1( lI i i# I N Il Dial-Indicator A i,, il 100 cm Hx ll ll V 82.5 lb i g x stool ){ ){ g lg I Steeljack ram Fdetion lock l Piston I I I The weight of 825 lbs represents the' weight of the patient and the operating couch. Operating couch: 625 lbs Patient: 200 lbs Figure Two Bending test of the steel piston ram O SR#-0-93-5 MAY 281993

L PM 3.14.1.4 Page 7 of 7 i O Ceiling outside the medical n>om Position of the plumbob was recorded every 2 cm Final position > r _ _; -(l-------a A A Plumb bob Stan position 4 40 cm 69 cm 1tsnasailma y Graph paper Top Plate f l / A point was marked at the center to represent a reference position Figure Three Vertical movement test of the operating couch ] SR#-0-93-5 MAY 281993 \\

PM 3.14.1.5 i Page 1 of 6 PM 3.14.1.5 Verification of Neutron Beam Geometric Center tL. Pumose: This test ensures that the geometric center of the neutron beam is identifiable with the shutters that control beam delivery in the closed position. This is necessary because patients will be aligned relative to the beam with the shutters closed. Backcround: The diameter of the bismuth collimator that admits the neutron beam is twelve inches. It is desired that the patient be positioned so that the treatment site is at the point of peak flux within this beam. A cross-mark (x) has been etched onto the underside of the sulphur / bismuth collimator at the point of peak flux as detemlined by foil irradiations. This ' mark is, of course, not visible during patient positioning because the shutters that control beam delivery are closed. It has been determined that the cross mark corresponds to the geometric center of the lead shutter and provisions have been made to attach a screw and - L plumb-bob at this location [1]. Patient treatment sites can be aligned directly under this geometric center. This procedure provides assurance that (1) the lead shutter position does ' not vany despite repeated cycling of the shutters and that (2) the geometric center of the' r l shutter remains aligned with the cross-mark. Lead Shutter Position Variability Test - i p Puroose: Ensure that, upon opening, the lead shutter moves to the same position despite () repeated cycling. Acceptance Criteria: The position of the lead shutter when opened is repeatable to within l t 1 mm. t Pre-Condition: The reactor is shut down and the lead shutter is open. Procedure: 1. Direct pointers to indicate both the edge of the lead shutter and the center of i the bismuth collimator. The latter is best done by aiming a laser at the collimator center because it is not on the same level as the shutter. (See Fig.

1) Place graph paper with a 1 mm grid on the surfaces above the pointers so as to facilitate the recording of deviations.

2. Cycle the s,hutter (close/open) ten times while recording deviations in the pomter posinons. 3. Report any deviation in pointer position that exceeds 1 'mm. (Note: Use of the shutter is still acceptable, provided that fine-positioning is done' l manually as described in [1].) i SR#-0-93-5 MAY 281993

PM 3.14.1.5 Page 2 of 6 Geometrie Center Position Variability Test Puroose: I e Ensure that the geometric center of the lead shutter lines up with the cross-mark on the collimator despite cycling of the shutter. Acceptance Criteria: The geometric center of the lead shutter is aligned directly under the cross-mark on the collimator to within i 3 mm. Pre-Condition: The reactor is shut down and the lead shutter is closed. Procedure: 1. Align a laser so that it shines on the geometric center of the shutter. Place graph paper with a 1 mm grid on the surface above the pointer so as to facilitate the recording of deviations. 2. Open the lead shutter and check that it is in the correct position using the fine-indicating micro-switch. 3. Observe that the laser shines on the cross-mark of the underside of the i collimator. 4. Repeat steps (2)- (3) ten times while recording the variation. 5. Report any variation in excess of 3 mm. (Note: Use of the shutter is still acceptable provided that fine-positioning is done manually as described in [1].) ) Reference 1. S. Yam, " Design of Patient Position System, Body Phantom, and Patient Shielding for the Boron Neutron Capture Thera Department of Nuclear Engineering,py Project at the MITR-II," M.S. Thesis, Massachusetts Institute of Technology, Cambridge, MA (Dec.1992). Procedure performed by: NC1'Research Scientist Date Procedure checked by: NCT Research Scientist Date Results reviewed by: NRL Director Date 1 SR#-0-93-5 MAY 281993

PM 3.14.1.5 2 Page 3 of 6 Lead Shutter Position. Variability Test Deviation (mm)- Cycle # Pointer #1 Pointer #2 1 i 2 3 - I 4 5 6 l. 7 8 i 9 f 10 t l i Acceptance Criteria (deviation s Imm)i Yes O No-O-i Test performed by: l NCF Research Scientist Date - Test checked by NCF Research Scientist - Date - - q. SR#-0-93-5 MAY 2'81993 l r w p T-@ =- T1 yI1 $T'W grh r wvpwy

{ PM 3.14.1.5 Page 4.of 6 Geometric Center Position Variability Test Cycle # Deva. ion (mm) at 1 2 3 4 5 6 7 8 ) 9 10 Acceptance Criteria (deviation s 3 mm): Yes O No O Test performed by: NCTResearch Scientist Date Test checked by: NCT Research Scientist Date I SR#-0-93-5 MAY 281993

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PM 3.14.1.5 i Page 6 of 6 i !\\ ) (1) Shine the laser onto the alignment screw d 1 ! l l 6:; a:. l 4 1 4 Alignment semw (2) Open the lead shutter I 8 7 4 S l

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g f PM 3.14.1.6 l Page 1 of 4 'i T i .i PM 3.14.1.6 ' Sensitivity' Test of the Medical Thernov Room O ne - u e i or-Pumose: l t The purpose of this sensitivity test is to verify the capability of the beam monitoring - system to detect misalignments in the configuration of both the shutters that control beam. delivery and the D O shutter. There are four shutters and hence twenty-four possible -l 2 configurations. The correct alignment is for all shutters to be full open.- Of the twenty-three possible misalignments, many would have such a major impact on the beam as to be jl obvious. These include most cases where only one or two shutters are open.- Accordingly, l testing is specified for eight possible misalignments and for the cases where a water shutter (H O or D 0)is not completely drained. j 2 2 Accentance Criteria: O This procedure does not have a definitive ' assessment criteria. Rather, the objective - is to determine if the outputs of the beam monitoring system would, upon normalization to a common reactor neutronic power level, be sufficiently inconsistent with the values measured during the most recent beam characterization so as to permit identification of a - shutter misalignment. Such a capability is a desirable backup to the shutter status lights and - limit switches that are the primary means for determining shutter position. O Prerequisites: 1. Reactor available for operation at a power level in excess of 1 MW. 2. Beam delimiterinstalled. j Procedure: 1. Obtain copy of reference data from the most recent beam characterization. 2. Verify the following: a) . Beam rnonitor components installed and connected for proper- . operation.1 b) Amplifiers, single-channel analyzers (SCAs), picoammeter values,- and computer settings the same as those during the most recent 4 charactenzation. c) To the maximum extent possible, replicate the conditions that existed during the most recent characterization including use of the same . phantom, phantom location and orientation to the beam, placement - O SR#-0-93-5 .MAY 281993 1 1 J, ~.. -,,.L J

i PM 3.14.1.6 j Page 2 of 4 .) l of the beam delimiter, and detector arrangement about the beam' aperture. Note any deviations: i 3. Turn on all beam monitor electronics. .l 4. Record the followinginformation: -f a) Time: Date: i b) ~ Ch. 7 a ; Ch. 9 - a; Nominal Power MW l i 5. Obtain the following information from the most recent reference beam-characterization: l 1 a). Date of characterization: l b) 'Ch.7 pa ; Ch. 9 ' a; Nominal Power MW 6. Initiate beam monitor data acquisition system. F6r each of the tests f specified below, record the time for the detector to attain the maximum i average stable count rate and the average counts per 5-second interval once - l . the count rate has stabilized. Open the D O shutter and recorGata. f 7. 2 8. Open the H O shutter and mcord data. 2 9. Open the lead and boral shutters. Record data. 1 10. Close the boral shutter and record data.:. I i 11. Open the boral shutter and close the lead shutter. Record data. i t 12. ~ Open the lead shutter and close the H O shutter. Record data. 2 I 13. Open the H O shutter and close the D O shutter. Record data. 2 2 Partially open the D O shutter. Record data and also the levelin the D O 14. 2 2 l shutter: Open the D O shutter fully. Adjust the level of the H O shutter so that it is i 15. 2 2 partially open. Record data and 'also the level in the H O shutter: 2 16. Close all shutters. lO SR#-0-93-5 MAY 281993

i PM 3.14.1.6 Page 3 of 4 b 17. Secure the beam monitor data acquisition system. r' I 8. Secure the beam monitoring system's electronics. 19. Normalize all counts to the power level utilized during the most recent beam characterization. 20. Review data to determine if the beam monitoring system is sufficiently sensitive to detect the various shutter misalignments. If not, note that fact here: Acceptance Criteria : Not Applicable p I (s Check performed by: NCT Research Scientist Date Check verified by: NCF Research Scientist Date Results reviewed by: NRL Director Date 1 1 l (~') m SR#-0-93-5 MAY 281993 i

i t PM 3.14.1.6-Page 4 of 4 1 r Detector Epitheraul Epithermal Themul Thermal l Configuration

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2. 2
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D0 Tune 2 l Counts Normalized D 0,H O Tune 2 2 l Counts Nonnalized D 0, H 0, Tune 2 2 Pb, Boral Counts Normalized D 0, H 0, Tune 2 2 i Pb Counts e l Nonnalized D 0, H 0, Tune r 2 2 Boral Counts Normalized O D 0, Boral, Tune 2 Pb Counts-Normalized H 0, Boral, Time 2 Pb Counts Nonmlimi D 0, Pb, Boral Tune 2 l H O Partial Counts l 2 l Nonmli7ed l l H 0, Pb, Boral Tune l 2 D O Partial Counts 2 Norrmlived Tests performed by: NCF Research Scientist Date Tests checked by: NCT Research Scientist Dare s. SR#-0-93-5 MAY 281993 i

i i PM 3.14.1.7 Page 1 of 2 -j PM' 3.14.1.7 Activation' Test of Patient Positionine System. O i i Puroose: t i This test ensures that the patient positioning system does not become activated - I during a human therapy to the point where it poses a radiation hazard i Prereauisite: Reactor available for operation at normal operating power levels. Accentance Criterion: All components read less than 100 mR/hr on contact after a therapeutic irradiation. I L Procedure: 1. Perform a standard 1.5 hour irradiation for human therapy with the reactor at nominal full power and with the alpha cradle positioned under the leg of a wax phantom. 2. Upon completion of the irradiation, record the background-corrected dos: 1 i ( rates on all major components. l t f i i l [ l l i L 'O SR#-0-93-5 ' MAY 281993 i i l

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Page 2 of 2

? r i i \\ Dose Rate (mR/hr) -l Component Gamma Beta .l 1. Floor - 2. Couch i ' ~ 3. Platform 4. Safety Belts j t 5. Laser Mounts i I 6. TV Camera I 7. Foam Padding 1 -i i l

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i .I Acceptance Criteria (< 100 mR/hr) Met: .. Yes O No -l 1 Test performed by: NCT Research Scientist Date Test checked by: NCT Research Scientist Date - 1 Results reviewed by: NRL Director Date 'l i SR#-0-93-5 MAY 281993 - j s i I

PM 3.14.1.8 Page 1 of 3-PM 3.14.1.8 Surveillance Schedule for Medical Therany O Facility Procedures Purnose: This procedure establishes a schedule for the performance of procedures required to implement MITR Technical Specification No. 6.5 and its associated Quality Management Program. Surveillances listed in this procedure are only required if human therapy is 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 human therapy during the interval in question. Acceptance Criterion: i Procedures are perfonned at the specified fn:quency subject to the following: a) A maximum allowable extension not to exceed 25% of the specified surveillance interval, unless otherwise stated in this procedure; b) A total maximum combined interval time for any three consecutive surveillance intervals not to exceed 3.25 times the specified surveillance 3 interval. b l ~ ) l ' O I SR#-0-93-5 MAY 281993 l s f

PM 3.14.1.8 4 Page 2 of 3 J i i i Surveillance Sched.ule l Itlle Frecuency Months { i 3.14.1.1 Test of Requirements Listed in MITR Monthly All Technical Specification No. 6.5 3.14.1.2 Calibration of Medical 1herapy Facility Quarterly Mar, June, Radiation Monitor Sept., Dec. ) 1 3.14.1.3 Source Check and Alarm Operability Test Therapy only* of Medical Therapy Facility Radianon t Monitor 3.14.1.4 Test of Patient Positioning System Annual -Jan. 3.14.1.5 Verification of Neutron Beam Geometric Preop Only** s Center j 3.14.1.6 Sensitivity Test of the Medical Therapy _ Pmop Only** Room Beam Monitors 3.14.1.7 Activation Test of Patient Positioning Pmop Only** i System

q 3.14.1.8 Surveillance Schedule for Medical Therapy N/A N/A' l

Q Facility Procedums 5 3.14.2.1 Functional Check'of the Medical Therapy Weekly - Facility Beam Monitors 3.14.2.2 Calibration Check of Medical Weekly **

• Therapy Facility Beam 3.14.2.3 Beam Monitor Plateau and Discriminator Semi-Annual Jan., July j

Setpoint Tests 3.14.2.4 Characterization of the Medical Therapy Semi-Annual Jan., July Facility Beam 1 3.14.2.5 Cmss-Calibration of Electmmeters . Biennial Jan. 3.14.2.6 Calibration and Stability Check of ' Semi-Annual Jan., July Ionizanon Chambers and Electrometers 3.14.2.7 Determination of High Purity Ge or Ge(Li) Semi-Annual Jan., July DetectorEfficiency 3.14.3.1 General Preparations for Use of Therapy only* the MedicalTherapy Facility Beam for Human Therapy-1 SR#-0-93-5 MAY 281993 i

I* I PM 3.14.1.8. i l Page 3 of 3 i 1 Igle Frecuency Months 3.14.3.2 Use of Prompt-Gamma Facility for Thempy only* 1 Boron Assay - i 3.14.3.3 Conduct of Human Therapy Using the Iterapy only* MedicalTherapy Facility Beam 3.14.3.4 Beam Monitor System Serpoints Therapy only* j 3.14.5.1-Non-Licensed Medical Personnel - As Required ~N/A-jl Qualification Program for Use of the MITR MedicalTherapy Facility 3.14.5.2 Test of Emergency Evacuation of a Patient Therapy only* from the Medical Therapy Facility Room t i A walk-through of these procedures shall be conducted prior to a patient therapy if l there has been no patient therapy for the past twelve months. (- Also mquired following any design modification.

• • • Performance of PM 3.14.2.2A or PM 3.14.2.2B or PM 3.14.2.2C satisfies the requirement. In addition, either PM 3.14.2.2B or PM 3.14.2.2C is to be done l

quarterly. l I i i l l 1 k -l O SR#-0-93-5 MAY 281993

PM 3.14.2.1 l Page 1 of 3 PM 3.14.2.1 Functional Check of the Medical Theraov Room O i ae - m e iters 4 Pumose: The purpose of this functional check is to ensure that the outputs of the beam monitors are consistent (i 10%) with pn:viously measured values upon normalization to a common neutronic powerlevel. Acceptance Criteria: The output of each beam monitor is, upon normalization to a common reactor neutronic power level, consistent (i 10%) with the value measured during the most recent 'j beam characterization. Prereouisites: 1. Reactor available for operation at a power level in excess of 1 MW. 2. Beam delimiterinstalled. Procedure: 1. Obtain copy of reference data fmm the most recent beam characterization and record the following: a) Beam designation: b) Date installed: 2. Verify the following: a) Beam monitor components installed and connected for proper operation. b) To the maximum extent possible, replicate the conditions that existed during the most recent characterization including use of the same phantom, phantom location and orientation to the beam, placement of the beam delimiter, and detector arrangement about the beam aperture. Note any deviations: i 3. Activate the beam monitor system's electronics. O SR#-0-93-5 MAY 281993 r .m,,.

t PM 3.14.2.1 H Page 2 of 3 - l 4. Use PM 3.14.3.4," Beam Monitor System Setpoints," to verify the settings 4 O of all beam monitor system parameters (gains, discriminator setpoints, etc.). 5. Open the D O shutter. ll 2 6. Open the' shutters that contml beam delivery (H 0, Pb, Boml). 2 7. Record the. output of each monitor (average counts per 5-second interval) once count rates have stabilized. 8. Normalize the recorded data to the powerlevel utilized during the most recent beam characterization. r 9. Determine if the output of each beam monitor is consistent with the value - obtained during the most recent beam characterization using the relation: ~ Current Reading - Reference' Cons.istency = 100 Reference 10. Close all shutters. 11. Secure the beam monitor data acquisition system and the beam monitoring system's electronics. I O i Check performed by: NCT Research Scientist Date- -l Check verified by: i ' NCT Research Scientist Date Results reviewed by: NRL Director Date i l SR#-0-93-5 MAY 281993. u l l E

i 1 PM 3.14.2.1 Page 3 of 3 l.' 4 i .E Benm Monitor Functional Check /~3 , kJ l 1 l. Time /Date: /~ 2, Reactor Power: ' Ch. 7 - a ; Ch. 9 a ; Nominal Power MW l l 3. Beam Designation: Date Installed: l t l 4. Date of benm reference characteri7ation: l r 5. Reactor neutronic nower durin g characterivation-l Ch. 7 a ; Ch. 9 a; Nominal Power MW i (Holt: - A characterization can take several days. The power listed should be that which existed when the beam monitor reference counts were taken.). 6. Functional Check Data: Normalimi - Reference Detector Counts /5 s Counts /5 s Counts /5 s Deviation Epithermal #1 Epithermal #2 Thermal #1 Thermal #2 Gamma i Acceptance Criteria (deviation < 10%) met: Yes No O i l Check performed by: NCF Research Scientist Date Check verified by: NCF Research Scientist Date LO SR#-0-93-5 MAY 281993 1 - ~

tr PM 3.14.2.2A Page 1 of 5 PM 3.14.2.2A Calibration Check of the Medical Theraov ,3Q Facility Beam via Chamber Measurements l Purnose: The purpose of this calibration check is to ensum that the beam has not changed in a significant way (e.g., energy spectrum or intensity) from the beam that was characterized. Background-A beam calibration check can be accomplished via any one of the following: foil activation; use of a fission chamber, use of an ion chamber, or an equivalent process. The procedure for checking beam intensity and spectrum via chamber measurements is given here. Additional information on the procedure as applied to the MIT Research Reactor's Medical Therapy Room Beam is given by Rogus [1]. Acceptance Criteria: The outputs of the beam monitors are, upon normalization to a common reactor power, consistent (i 10%) with the values measured during the most recent beam characterization and the ratio of the epithermal to thermal counts is consistent (i 10%) with that obtained during the most recent characterization. Prereauisites: p) 1. Reactor operating at a power level in excess of 1 MW. u 2. Beam delimiter and whole body shields are installed. These shields should be in the same position ( 2 mm side-to-side, 2 mm frorit-to-back, and 2 mm up-and-down) as that used in the most recent characterization of the beam. 3. A standard phantom is available. This phantom is a right circular cylinder that is l made of polyethylene and which is 18 cm in diameter and 20 cm long. Beam monitoring system is available. As a minimum, one epithermal and one thermal neutron detector shall be available. (Haic: Other phantoms with equivalent capability for positioning the foils may be used provided that there is a measured correlation between them and the standard phantom.) 4. Standard radiological procedures for use of the medical therapy facility are to be observed. Procedure: l l 1. Obtain copy of reference data from the most recent beam characterization l and record the following: l a) Beam designation: l l b) Date installed: \\,) SR#-0-93-5 MAY281993

I PM 3.14.2.2A Page 2 0f 5 2. Check the beam monitor system to ensure that it is operating properly. Each counter or ion chamber shall be checked by: a) For the fission chambers, connect the output of each detector's amplifier to an oscilloscope and examine the pulse for correct shape and low noise level. t b) Test operation of the counter-scalers by connecting them to a pulse generator and verifying that 600 pulses are generated for a 60 Hz. signalin 10 s. 3. Verify that PM 3.14.2.3, " Beam Monitor Plateau' and Discriminator' Setpoint Tests" has been completed satisfactory within the past six months. Date performed: 4. Perform PM 3.14.3.4, " Beam Monitor System Setpoints," to verify the. settings of all beam monitor system parameters (gains, discriminator setpoints, etc.). 5. To the maximum extent possible, replicate the conditions that existed during the most recent characterization including use of the same phantom, phantom location and orientation to the beam, placement of the beam delimiter, and detector arrangement about the beam aperture. Note any deviations: O 6. Activate the beam monitor system's electronics. 7. Open the D O shutter. 2 8. Open the shutters that control beam delivery (H 0, Pb, Boral). 2 9. Record the output of each monitor (average counts per 5-second interval) once count rates have stabilized.- 10. Normalize the recorded data to the power level utilized during the most recent beam chameterization. 11. Average the thermal neutron and epithermal neutron counts. 12. Verify that beam intensity has not changed by determining if the output of each beam monitor is consistent with the value obtained during the most recent characterization. 13. Verify that beam spectrum has not changed by determining if the ratio of the. epithermal to thermal neutron counts is consistent with the value obtained during the most recent chameterization. SR#-0-93-5 MAY 281993 i

1 l . PM 3.14.2.2A-- L -Page 3 of 5. Il ;- b.. 14. Close all shutters. ] 15. Secure the beam monitor data acqsisition system and the beam monitoring -1 system's electronics. i 1 I i Check performed by: Date.. i; - NCT Research Scientist.. Check verified by: NCF Research Scientist Date i l. l Results. reviewed by: - NRL Director - Date l l I l i ,t i

Reference:

1. Rogus, R., " Protocol for Mixed-Field Dosimetry of Epithermal Neutron Beams for ' I Boron Neutron Capture Therapy at the MITR-II Research Reactor," MITNRL-054, October 1992. I i l I - ) i O 1 - SR#-0-93-5 .MAY 281993 - e -9 T-g r t -w*< --y 94--+@-- g-y g =--tm v-, i ee- ,g-w-4,- - + ,,-%+--,w- -ew-g-rw v e--* c-3-- e-

i e PM 3.14.2.2A i Page 4 of 5 4 Calibration Check via Chamber Measurements 1. Tune /Date: -/ 2. Reactor Power: Ch. 7 pa ; Ch. 9 a ; Nominal Power MW 3. Beam Designation: Date Installed: l 4. Date of beam reference characterirntiDD: i 5. Reactor neutronic nower during characteri7ation: Ch.7 a ; Ch. 9. pa; Nominal Power' MW (Hole: A characterization can take several days. He power listed should be that which existed when the beam monitor reference counts were taken.) 6. Check 'of Beam Monitor System: Detector Pulse Shape Scaler Epithermal #1 Epithermal #2 Thennal#1 l l Hermal#2 N/A 1 Gamma N/A i 7. Consistency Check on Beam Intensity: j Normali7ed Reference Detector Counts /5 s Counts /5 s Counts /5 s Deviation Epithermal #1 Epithermal #2 hermal#1 Thermal #2 Gamma l r\\ '%) SR#-0-93-5 MAY 281993

t. ' PM 3.14.2.2A Page 5 of 5 ( 8. Conduency Check on Beam Snectrum-(', a) Average thermal counts: counts /5 s b) Average epithermal counts: counts /5 s. l c) Ratio of epithermal to thermal counts: d) Refennce value for ratio of epithermalto thermal counts: e) Pement deviation of ratio obtained during this l calibration check to that - obtained during the most. recent chancterization i i i i i Acceptance Criteria (deviation in intensity and spectrum < 10%) met: Yes O No O i O a Check performed by: NCF Rescamh Scientist - Date Check verified by: NCF Rescamh Scientist . Date - i i i l { 1 E . SR#-0-93-5 MAY 281993 -i ) ,-m...

? PM 3.14.2.2B Page 1 of 8 t PM 3.14.2.2B Calibration Check of the Medical Theraov Beam via Foil Activation p) (V Pumose: The pugose of this 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. Backcround: A beam calibration check can be accomplished via any one of the following: foil activation; use of a fission chamber, use of an ion chamber, or an equivalent process. The procedure for checking beam intensity and spectrum via the determination of thermal and epithermal fluxes from gold foil activation analysis is given here. Additional information on the procedure as applied to the MIT Reseamh Reactor's Medical Therapy Room Beam is given by Rogus [1]. Acceptance Criteria: The thermal and epithermal fluxes are, upon normalization to a common reactor power, consistent (i 10%) with the values measured during the most recent beam characterization. Prercouisites: 1. Reactor operating at a power level in excess of 1 MW. 2. Beam delimiter and whole body shields are installed. These shields should be in (A) the same position (i 2 mm side-to-side, i 2 mm front-to-back, and i 2 mm up-and-down) as that used in the most recent characterization of the beam. 3. A standard phantom is available. This phantom is a right circular cylinder that is made of polyethylene and which is 18 cm in diameter and 20 cm long. This phantom is cut into ten layers so as to allow foils to be positioned at various depths. (Ente Other phantoms with equivalent capability for positioning the foils may be used provided that there is a measured correlation between them and the standard phantom.) 4. Standard radiological procedures for use of the medical therapy facility are to be observed. Procedure: 1. Weigh two gold foils (5-10 mg, ~0.002" thick) on a calibrated balance (Mettler AT 201 or equivalent) that has an absolute accuracy and repeatability of less than 1%. Place a small piece of pressure-sensitive polyester film tape on the top and bottom of each foil, pinch the sticky sides together, and then trim the tape. The foils can be marked with a number written with a permanent marker on the tape. ]iqtt: Gold foils that have been previously irradiated may be used provided that the residual activity is less than 0.3 % of the initial amount. This corresponds to a decay interval of three weeks.) Record foils #s and weight: p / mg; / mg. V SR#-0-93-5 MAY 281993

l* PM 3.14.2.2B i Page 2 of 8 l 2. Place one of the gold foils in the phantom at a depth of 2 cm.- Designate this foil as the ' bare' foil. Weight of foil: mg. l O l V 3. Position the phantom so that it is under the centerline of the bismuth l collimator (its centerline when the lead shutter is open) using the fiduciary ) marks on the bottom of the delimiter. The top of the phantom should be l immediately below the bottom of the delimiter. l 4. Commence the foil irradiation using the following sequence for opening of the D O shutter and the shutters that control beam delivery: i 2 a) Record time and date: Tune Date b) Record reactorpowerlevel: Ch.7 pa : Ch. 9 a ; Nominal Power MW c) Clear the medical therapy facility room of personnel and close the shield door. d) Open the D O shutter. (This usually requires three minutes.) 2 e) Depress the open button for the H O shutter and observe that it is 2 draining. Wait forty seconds and then open the lead and boral shutters. The ' irradiation start time' is the moment when the lead shutterindicates open. (') f) Record irradiation start time: V Tune Date g) Record readings of reactor power indicators once all shutters are open: Ch.7 pa ; Ch. 9 a 5. Irradiate the foil for approximately sixty minutes. (N_qig: Shorter irradiations are acceptable. The consideration is that a long irradiation minimizes both the effect of the shutter cycle times and the required counting time.) 6. Monitor reactor power channels No. 7 and 9 during the irradiation. The drift should be less than 1 E 7. Terminate the foil irradiation using the following sequence for closing the D O shutter and the shutters that control beam delivery: 2 a) Specify time at which irradiation is to be terminated: Tune Date b) Ten seconds prior to the specified termination time, depress the close button for the H O shutter. 2 SR#-0-93-5 MAY 281993

PM 3.14.2.2B - Page 3 of 8 ,t c) Close the lead and boral shutters at the official termination time and []) then close the D 0 shutter. 2 d) Record time at which the lead shutter was closed: ) Tune Date 8. Enter the medical therapy room facility, survey, and remove the bare foil from the phantom. 9. Fold a 0.020 inch thick, half-inch diameter cadmium disc in half and use it to cover the second gold foil. This is the ' covered' foil. Weight of foil: mg. l 10. Place the covered foil in the phantom at a depth of 2 cm. Use one of the phantom slices that has a counterbore on the centerline. The cadmium should fit into the counterbore so that the phantom slice above it is flush with the slice below it. 11. Position the phantom so that it is under the centerline of the bismuth collimator (its centerline when the lead shutter is open) using the fiduciary l marks on the bottom of the delimiter. The top of the phantom should be immediately below the bottom of the delimiter. 12. Commence the foilirradiation using the following sequence for opening of the D O shutter and the shutters that control beam delivery: g-2 i' a) Record time and date: Tune Date b) Record reactor powerlevel: Ch.7 pa ; Ch. 9 a ; Nominal Power MW c) Clear the medical therapy facility room of personnel and close the shield door. ( d) Open the D 0 shutter. (This usually requires three minutes.) 2 l e) Depress the open button for the H O shutter and observe that it is 2 draining. Wait forty seconds and then open the lead and boral shutters. The ' irradiation start time'is the moment when the lead shutterindicates open. f) Record irradiation start time: Tune Date ( f l l l SR#-0-93-5 MAY 281993

I. PM 3.14.2.2B Page 4 of 8 g) Record readings of reactor power indicators once all shutters are open: 73 Ch.7 a ; Ch. 9 pa l] 13. Irradiate the foil for approximately sixty minutes. (Note: Shorter irradiations are acceptable. The consideration is that a long irradiation minimizes both the effect of the shutter cycle time and the required counting time.) 14. Monitor reactor power channels No. 7 and 9 during the irradiation. The drift should be less than 1 %. 15. Terminate the foil irradiation using the following sequence for closing the D O shutter and the shutters that control beam delivery. 2 a) Specify time at which imidiation is to be tenninated: Tune Date b) Ten seconds prior to the specified termination time, depress the close button for the H O shutter. 2 c) Close the lead and boral shutters at the official termination time and then close the D 0 shutter. 2 d) Record time at which the lead shutter was closed: ,n\\ Time Date 16. Enter the medical therapy room facility, survey, and remove the covered foil from the phantom. 17. Obtain the efficiency of the detector (a high purity Ge, Ge(Li), or equivalent) that is to be used for counting the foils from the most recent calibration of the detector (PM 3.14.2.7). Record the following: Detector Type: , Serial No.: Distance between detector face and source: inches Efficiency at 411 kev where the source was counted: 18. Remove the cadmium cover from the covered foil. i 19. Count the foils. Details are again given in [1] with the principal j considerations summarized here. l a) Place the one bare and the one covered foil in specially-prepared cardboard holders (similar to 35 mm projector slides). 'Ihen place each sequentially in the counting position that was used for the ,m standan! source and count. i ) ix m SR#-0-93-5 MAY 281993 l

PM 3.14.2.2B Page 5 of 8

i b)

For each foil record the following: -q Bme Covered V (i) Position relative to detector: l (ii) Time count started: l l (iii) Counting time (live time): 1 (iv) Net area under the Au-198: Peak @ 411 kev l 20. Calculate the thermal and epithermal neutron fluxes using the procedure summarized in Appendix A to this procedure. 2 Thermal Flux: neutrons /cm.s, 2 Epithermal Flux: neutrons /cm.s. 21. Normalize the themial and epithermal fluxes calculated in step (20) above to the neutronic power.that existed during the most recent beam characterization. To do this, use the ratio of the channel #7 readings that exist with all shutters closed. Fluxes normalized for comparison with those obtained during beam characterization: a) Thermal Flux: neutrons /cm2 3, /m 2 ' Q b) Epithermal Flux: neutrons /cm -s. 22. Normalize the fluxes to 5 MWt by using channel #7 data obtained under conditions of thermal equilibrium. Fluxes normalized to 5 MWt: 2 a) Thermal Flux: neutrons /cm.s. b) Epithermal Flux: neutrons /cm2-s. 23. Obtain flux data from the most recent beam characterization and compare the i values from step (21) above to these values: 2 a) Thermal Flux from Characterization: neutrons /cm -s. b) Epithermal Flux from Characterization: neutrons /cm2-s. c) Deviation in ThermalFlux: d) Deviation in EpithermalFlux: 1 (~) v l SR#-0-93-5 MAY 281993 l l i 1

PM 3.14.2.2B Page 6 of 8 24. Record the following: 7(O Beam Designation: Date Installed: 25. Secure medical room facility and equipment or continue with'other scheduled procedures as appropriate. The acceptance criteria is a deviation of less than 10% in flux. Acceptance Criteria Met-Yes O No O Check performed by: NCT Research Scientist Date Check verified by: NCT Research Scientist Date Results reviewed by: NRL Director Date

Reference:

1. Rogus, R., " Protocol for Mixed-Field Dosimetry of Epithermal Neutron Beams for Boron Neutron Capture Therapy at the MITR-II Research Reactor," MITNRL-054, October 1992. 'O (v SR#-0-93-5 MAY 281993

PM 3.14.2.2B Page 7 of 8 Annendix A q Calculation of Thermal and Eoithermal Neutron Fluxes i The method for calculating the thermal and epithermal fluxes for the MITR Medical l Therapy Room Beam is described in detail by Rogus [1]. A summary is given here. The equation numbers used here correspond to those in Reference One and are therefore not Consecutive. ~ The saturated activity for an infinitely-long irradiation and the 2200 m/s flux are given by the relations: i i AC A"I = (36) t cl1_e4 Ve-Att_e42 i a i A s i ^ Sal -FCd (37) 42200 = Ayc2200, mb, m g e s. where A is the saturated activity (disintegrations /s); mt A is the decay constant (s-1 in' the numerator and inverse days in the denominator); C is the net counts under the 411 kev Au-198 peak (total counts minus background counts); i 1 e is the overall counting efficiency, which accounts for self-absorption (c ). a detector efficiency (ed), and abundance of the detected radiation (c ) with all r efficiencies given as numbers, not percents; [ i t is theirradiation time (days); o 3 i ti is the count start time (days); t2 is the count end time (days); 2 $2200 is the 2200 m/s absorption cross-section for gold-197 (cm / atom); mb is the bare foil mass (mg); m is the covered foil mass (mg); and e Fe is the cadmium correction factor. All times are referenced to the start of the irradiation which is considered zero. Upon substitution of known constants, the following are obtained: SR#-0-93-5 MAY 281993 ~

l PM 3.14.2.2B Page 8 of 81 Soecific Saturated Activity of the Bare Foil: 'Ag 2.975 E-6 x (C/mb) 0.989 x 0.955 x cd x (1-e-o.257to,- o.25712 [ cms where t, t, and 1 are in days. I o i 2 ~ Soecific Activity of the Covered Foil: fag 2.97 E-6 x (C/ m ) e 0.989 x 0.955 x ed x (1-e-U"7'Ohe-0.257ti _ e-0.257:2[ t ms where t, t, and 1 are in' days. f o i 2 Neutron Flux at 2200 m/s: i ~ 196.7 x 1000 ' A j - 1.02 ^21-2200, _6.02 E+23 x 98.8E-24,, m.,b m e s e, where the factor of 1000 in the numerator of the last equation is to convert grams to i milligrams. Also,it has been assumed that the correction for self-absorption of 411 kev l photons in the gold foil is 0.989, that the 411 kev photon abundance is 0.955, and that the cadmium correction factor is 1.02. The latter quantity is a function of foil thickness. -{ O Eoithermal Neutron Flux: i The epithermal neutron flux can now be found. It is given by the mlation: i 10.1(Fed)(Asat /m)c(W) 1 $ epi = (50) (Au)(RI)(Fres) i where $ep; is the epithennal neutron flux (n/cm2.s); l RI is the resonance integral for an ideal, infinitely dilute _ gold foil (em2); and .j F is the resonance self-shielding factor. 1 res Upon substitution of known constants, the following is obtained-' l /m)c x 196.97. x 1000 i 10.1 x 1.02(Asat $ cpi = 6.02E+23 + 1560E-24 x 0.28 where the resonance integral is taken as 1560 barns, and the resonance self-shielding factor is 0.28. O SR#-0-93-5 MAY 281993

PM 3.14.2.2C Page 1 of 8 PM 3.14.2.2C Calibration Check of the Medical Thernov Beam via the Dual Ion Chamber Technione-l Purnose: The purpose of this 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. i Backemund: A beam calibration check can be accomplished via any one of the following: foil i activation; use of a fission chamber, use of an ion chamber, or an equivalent process. The procedure for checking beam intensity and spectrum via the determination of the photon and fast neutron dose rates via the dual ion chamber technique is given here. Additional i information on the procedure as applied to the MIT Research Reactor's Medical Therapy i' Room Beam is given by Rogus [1]. Accentance Criteria: The photon and fast neutron dose rates are, upon normalization to a common reactor power, consistent ( 10%) with the values measured during the most recent beam characterization. Prereauisites: 1. Reactor operating at a power level in excess of 1 MW. ~ 2. Beam delimiter and whole body shields are installed. These shields should be in the same position ( i 2 mm side-to-side, i 2 mm front-to-back, and i 2 mm up-and-down) as that used for previous characterizations of the beam. 3. A standard phantom is available. This phantom is a right circular cylinder that is l made of polyethylene and which is 18 cm in diameter and 20 cm long. This l phantom is cut into ten layers so as to allow foils to be positioned at various depths. l This phantom is also used for the calibration checks and beam monitor functional checks. Other phantoms may be used provided that there is consistency with these checks. These include the Wax-130 leg phantom and the paraffin half-body phantom. 4. Instruments required for the measurements of the beam's fast neutron and photon - components are available including: a) Tissue-equivalent chamber (Far West IC-18), b) Graphite-wall ionization chamber (Far West IC-18G), l c) Two electrometers (Keithley 616 or 617). O SR#-0-93-5 MAY 281993 l

PM 3.14.2.2C Page 2 of 8 The tissue-equivalent and graphite-wall chambers as well as one of the g, electrometers shall have been calibrated by a Secondary Calibration Laboratory within the last two years. The electrometer for which this is done is designated here \\ as the ' calibrated' instrument (Keithley 617) while the other is referred to as the ' field' insaument (Keithley 616). The latter is calibrated against the former using PM 3.14.2.5, " Cross-Calibration of Electrometers." The ' field' instrument is the - one used for the characterization. Each electrometer can be calibrated by itself or the electrometer and each chamber can be calibrated as an electrometer-chamber patr. 5. Low-noise signal cables, a high voltage power supply (Canberra HV Supply

1. 2816A or equivalent), high-voltage cables, and a stop watch with an accuracy and resolution of 0.1 s. (Caution: The signal cables should be handled gently. In particular, they should not be bent to radii of less than 30 cm.)

6. Standard radiological procedures for use of the medical therapy facility are to be observed. Ouality Assurance: 1. Record the following for the instruments that are used to measure the beam's fast neutron and photon components: Instrument Serial # Calibration Date Secondary Lab a) Tissue-Equivalent (3 b) Graphite-Wall c) Keithley 617 d) Keithley 616 PM 3.14.2.5 2. Verify that the following were done during the instrument calibrations: a) Tissue-equivalent chamber was flushed with a methane-based tissue-equivalent gas at 5 cc/ minute; b) Graphite-wall chamber was flushed with CO at 5 cc/ minute. 2 Verified: NCT Resean:h Scientist Date Enic: If flows of 5 cc/ minute were not used, then corrections to the calibrations may be necessary. In that case, record the flow rates that were actually used on the attached data sheet. I m l l SR#-0-93-5 MAY 281993 l l

PM 3.14.2.2C Page 3 of 8 Procedure: f-w (. 1. Energize the field electrometer and adjust the high voltage or the HV power supply to + 250 V. Check the HV cable to be certain that the chamber would be at 250 i 10 V. The background current, with the voltage applied to the chambers but with no radiation field, should be less than 5E-15 Amperes. 2. Allow the field electrometer to wami up for one hour. 3. Purge the CO line for 20 minutes at ~100 cc/ minutes. (CAUTION: The 2 next step is to connect the graphite-wall chamber to the electrometer. When doing so, the electrometer should be in the zero position and the high voltage should be off.) 4. Connect the graphite-wall ionization chamber to the CO line, snap on the 2 Lucite tube, and insert it into the phantom at the I cm position for the head phantom or the 0 cm position for the other phantoms. Position the phantom in the beam so that the area in which the measurement 5. will be made is under the center line of the bismuth collimator (its center line when the lead shutter is open) using the fiduciary marks on the bottom of the delimiter. The top of the phantom should be immediately below the bottom of the delimiter. 6. Reduce the CO flow rate to 5 cc/ minute. (Note: Higher flow rates, up to 2 20 cc/ minute are acceptable provided that a cormction factor is applied to the c) ( chamber current.) Record the CO flow rate on the attached data sheet or 2 '~ enter it on the appropriate spreadsheet. 7. Measure the temperature of the CO flush gas with a thermometer and the 2 barometric pressure with the barometer in the reactor control room Record data on the attached sheet or enter it on the appropriate sheadsheet. 8. Commence the measurement using the sequence given below. Infonnation may either be recorded on the attached data sheet or, as an alternadve, a spread:heet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCT Research Scientists. a) Record time and date on the attached data sheet. b) Record reactor power level on the attached data sheet. I c) Clear medical therapy room of personnel and close the shield door. d) Open the D O shutter and then the H 0, lead, and boral shutters. 2 2 l Wait until all shutters indicate full open. l CN s NJ SR#-0-93-5 MAY 281993

PM 3.14.2.2C Page 4 of 8 e) Measure the current using racetrack timing. Collect charge for about one minute and then record the charge and time interval. Repeat /l twice and average the results of the three measurements. The three () measurements should be within about 1% of the average. If not, several additional readings should be taken to ensure the system is at steady-state. Record data on the attached sheet. f) Close all shutters, enter the medical therapy room facility, and survey. 9. Purge the tissue-equivalent gas line for 20 minutes at 100 cc/ minute. (CAUTION: The next step is to disconnect the graphite-wall chamber and to connect the tissue-equivalent chamber to the electrometer. When doing so, the electrometer should be in the zero position and the high voltage should be off.) 10. Connect the tissue-equivalent ionization chamber to the tissue-equivalent gas line, snap on the Lucite tube, and insert it into the phantom. For convenience, the measurement should be taken at the 1 cm position for the head phantom and at the 0 cm position for the other phantoms. l l 11. Position the phantom in the beam so that the area in which the measurement l will be made is under the center line of the bismuth collimator (its center line l when the lead shutter is open) using the fiduciary marks on the bottom of l the delimiter. The top of the phantom should be immediately below the bottom of the delimiter. t l 12. Reduce the tissue-equivalent gas flow rate to 5 cc/ minute. (Epic: Higher gV) flow rates, up to 20 cc/ minute are acceptable provided that a correction 5 factor is apphed to the chamber current.) Record the tissue-equivalent gas flow rate on the attached data sheet or enter it on the appropriate spreadsheet. 13. Measure the temperature of the tissue-equivalent gas with a thermometer and the barometric pressure with the barometer in the reactor control room Record data on the attached sheet or enter it on the appropriate spreadsheet. 14. Commence the measurement using the sequence given below. Information may either be recorded oa the attached data sheets or, as an alternative, a l spreadsheet may be used to perform and record these calculations. If used, l these shall be signed, dated, and reviewed by two NCI' Research Scientists. l a) Record time and date on the attached data sheet, b) Record reactor power level on the attached data sheet. i c) Clear medical therapy room of personnel and close the shield door. d) Open the D O shutter and then the H 0, lead, and boral shutters. 2 2 l Wait until all shutters indicate full open. lp [ b' 1 SR#-0-93-5 MAY 281993 l

PM 3.14.2.2C Page 5 of 8 e) Measure the cunent using racetrack timing. Collect charge for about one minute and then record the charge and time interval. Repeat (~'T twice and average the results of the three measurements. The three d measurements should be within about 1% of the average. If not, several additional readings should be taken to ensure the system is at steady-state. Reconi data on the attached sheet. f) Close all shutters, enter the medical therapy room facility, cnd survey. 15. Secure medical room facility and equipment or continue with other scheduled procedures as appropriate. 16. Record the MIT Research Reactor's power history for the seven days prior to the above measurements using the attached form or enter the information on the appmpriate spreadsheet. 17. Calculate the photon and fast neutron dose rates using the procedure described in Appendix B of PM 3.14.2.4," Characterization of the Medical Therapy Beam," and record results on the attached data sheet. As an alternative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCF Research Scientists. 18. Record the measured and corrected currents for each chamber: a) Graphite Chamber Current: s Measured: Corrected: b) Tissue Chamber Current: Measured: Corrected: _ 19. Perform a calibration check of the medical therapy facility beam by computing the photon and fast neutron dose rates, normalizing them to the neutronic power that existed during the most recent beam characterization, and compting the deviation between these dose rates and those measured during that characterization. AL) SR#-0-93-5 MAY 281993 1 1 1

q r ! ~ PM 3.14.2.2C -i Page 6 of 8 - l l t Ouantity . Dose Rates Deviation i (cGy/ minute) Measured Normalized - Esfsrence i Photon / Brain ~ Fast Neutron / Brain t Photon / Muscle i Fast Neutn>n/. Muscle j .. t I .i Acceptance Criteria (deviation <10%) met: = Yes - No 1; ()/ \\ N Check performed by: l NCT Research Scientist Date l Check verified by: l j NCF Research Scientist Date t i Results reviewed by: i NRL Director Date Rdcrence: l i j 1. Rogus, R., Protocol for Mixed-Field Dosimetry of Epithermal Neutron Beams for l Boron Neutron Capture Therapy at the MITR-II Research Reactor," MITNRI-054,. October 1992. I i l l i i SR#-0-93-5 MAY 281993 l =l t j i' .) <,,.n n -.n .....ns,+. ,a =,N b

c PM 3.14.2.2C Page 7 of 8 a =, Record of Reactor Power History l ( I i Date Tune' Ch. 7 (pa) Ch. 9 ( a) Nominal Power j i l u 'f l l l l P 1 Data obtained by: 1 NCF Research Scientist Date r Data vedfied correct: Senior Reactor Operator Date l I - i SR#-0-93-5 MAY 281993 i I L-e 1 t v... ,,u-, w a ,,y, -y_.- y m. ,s---g-v.,--.

4 PM 3.14.2.2C Page 8 of 8 Graohite-Wall Ionization Chamber Measurement l Beam Designation: Date Installed: Phantom Type: Chamber Type: Serial #: CO gas flow: cc/ minute 2 Temperature: C; Barometric pressure: CO gas flow when chamber was calibrated: cc/ minute 2 Date and Time: Date Tune Reactor Power: Ch. 7 pa; Ch. 9 a; NominalPower MW Collection Phantom Position Measurement # Time Charge Deviation 1cm 1 2 3 Average N/A 0.0% Tissue-Eauivalent Ionization Chamber Measurement (~ Chamber Type:

- Serial #

Tissue-equivalent gas flow: cc/ minute Temperature : C; Barometric pressure: Tissue-equivalent gas flow when chamber was calibrated: _ cc/ minute Date and Time: Date Tune ReactorPower: Ch.7 a; Ch. 9 a; NominalPower MW Collection Phantom Position Measurement # Time Charge Deviation Icm 1 1 2 j 3 Average N/A 0.0% l Certified by: NCT Research Scientist Date l [ NCT Research Scientist Date SR#-0-93-5 MAY 281993 1

PM 3.14.2.3 Page 1 of 9 PM 3.14.2.3 Beam Monitor Plateau and Discriminator i l q'% J Setooints l Pumose: The purpose of this procedure is to ensure that the operational characteristics of the various beam monitors are consistent with their expected behavior. l Acceptance Criteria: The plateau voltage and disciminator levels am set such that a change of.i 10% will alter the count rate by less thani5%. Prerecuisites: 1. Reactor available for operation at a power level in excess of 1 MW. 2. Beam delimeterinstalled. l Procedure: l The beam monitor system consists of five detectors: two Li-6 covered %M fission chambers (TGM FC4A/100), a bare LND fission chamber (LND 30753), an LND He-3 l chamber, and an LND ionization chamber. Equivalents to these chambers may be used. l These chambers are, for simplicity, referred to elsewhere as epithermal #1, epithermal #2, thennal #1, thermal #2, and gamma. These names aflect the principle type of radiation to

p) which each chamber is sensitive. The objective here is to verify that each chamber is

(

performing according to its specified characteristics. l l l A. EPITHERMAL #1 High Voltace Plateau Determination: (Reference Operating High Voltage is 250 Volts) 1. Set all system serpoints to those specified in PM 3.14.3.4 (Part A). 2. Adjust the counter / timer to collect counts for 10 seconds. 3. Record counts for 10 seconds with the high voltage set at 30 volts. Repeat for each'of the following settings: 50,100,150,200,250,300 and 350 volts. 4. Plot a curve of counts per second versus high voltage and attach plot. 5. Verify that a Idgh voltage setting of 250 volts results in operation within the plateau and that a change ofi 10% in this voltage results in less than a 15% changein count rate. y (v) SR#-0-93-5 MAY 281993

+ PM 3.14.2.3 - -i Page 2 of 9 ' 'l i Discnminator 12 vel Determination: (Reference Discriminator level is 4 Volts) i 1. Set all system setpoints to those specified in PM 3.14.3.4 (Part A). 2. Adjust the counter / timer to collect counts for 10 seconds. l 3. Record counts for 10 seconds with the Lower Level (E) of the SCA set'at j 0.1 volts. Repeat for each of the following settings: 0.5,1,2,3,4,5,6,: 7,8,9 and 10 volts. 4. Plot a curve of counts per second'versus discriminator level (volts) and, j attach plot. 5. . Verify that a discriminator level of 4 volts results in operation within in the plateau and that a change ofi 10% in this voltage results in less than a. 15% change in count rate. -l j l B. EPITHERMAL #2 ~ 1 Hiph Voltase Platean Determinatinn: (Reference Operating High Voltage is 250 Volts): 1 1. Set all system setpoints to those specified in PM 3.14.3.4 (Pan B). { 2. Adjust the counter / timer to collect counts for 10 seconds. l 3. Record counts for 10 seconds with the high voltage set at 30 ' olts. Repeat v for each of the following settings:' 50,100,150,200,250,300 and 350 volts. i t 4. Plot a curve of counts per second versus high voltage and attach plot. l l i l 5. Verify that a high voltage setting of 250 volts results in operation within the l l plateau and that a change of t-10% in this voltage results in less than a. iS% changein count ate. Discriminator 12 vel Detmnination: (Reference Discriminatorlevelis 4 Volts) i -1. Set all system setpoints to those specified in PM 3.14.3.4 (Part B). -l 2. Adjust the counter / timer to collect' counts for 10==ds.- 3. Recorti counts for 10 seconds with the Lower Level (E) of the SCA set at' O.1 volts. Repeat for each of the following settings: 0.5, 1, 2, 3,~4, 5, 6 - 7,8,9 and 10 volts. 4. Plot a curve of counts per second versus discriminator level (volts) and-attach plot. O SR#-0-93-5 MAY 281993 -.a

PM 3.14.2.3 Page 3 of 9 5. Verify that a discriminator level of 4 volts results in operation within the plateau and that a change ofi 10% in this voltage results in less than a (] i 5% change in count rate. V C. THERMAL #1 High Voltage Plateau Determination: (Reference Operating High Voltage is 500 Volts) i 1. Set all system setpoints to those specified in PM 3.14.3.4 (Pan C). 2. Adjust the counter / timer to collect counts for 10 seconds. 3. Record counts for 10 seconds with the high voltage set at 30 volts. Repeat for each of the following settings: 50,100,200,300,400,500,600,700 and 800 volts. 4. Plot a curve of counts per second versus high voltage and attach plot. 5. Verify that a high voltage setting of 500 volts resuhs in operation within the plateau and that a change ofi 10% in this voltage results in less than,a 15% change in count rate. Discriminator Level Determination: (Reference Discriminator Level is 4 Volts) 1. Set all system setpoints to those specified in PM 3.14.3.4 (Pan C). ( ~) U 2. Adjust the counter / timer to collect counts for 10 seconds. 3. Record counts for 10 seconds with the Lower Level (E) of the SCA set at 0.1 volts. Repeat for each of the following settings: 0.5,1,2,3,4,5,6, 7,8,9 and 10 volts. 4. Plot a curve of counts per second versus discriminator level (volts) and attach plot. 5. Verify that a discriminator level of 4 volts results in operation within the plateau and that a change ofi 10% in this voltage results in less than a 15% change in count rate. D. THERMAL #2 Hich Voltage Plateau Determination: (Reference Operating High Voltage is 200 Volts) 1. Set all system setpoints to those specified in PM 3.14.3.4 (Part D). 2. Adjust the counter / timer to collect counts for 10 seconds. 3. Record counts for 10 seconds with the high voltage set at 30 volts. Repeat (~} for each of the following settings: 50,100,150,200, and 250 volts. Q./ SR#-0-93-5 MAY 281993

PM 3.14.2.3 1 Page 4 of 9 4. Plot a curve of counts per second versus high vohage and attach plot. N 5. Verify that a high voltage setting of 200 volts results in operation within the plateau and that a change ofi 10% in this voltage results in less than a 15% change in count rate. Discriminator Level Determination: Not Applicable. E. GAMMA Hich Voltace Plateau Determination: (Reference Operating High Voltage is 200 Volts) 1. Set all system setpoints to those specified in PM 3.14.3.4 (Part E). 2. Adjust the counter / timer to collect counts for 10 seconds. 3. Record counts for 10 seconds with the high voltage for each of the following settings: 30,50,100,150,200, and 250 volts. 4. Plot a curve of counts per second versus high voltage 5. Verify that a high voltage setting of 200 volts results in operation within the plateau and that a change ofi 10% in this voltage results in less than a (- iS% change in count rate. ( Discriminator 12 vel Determination: Not Applicable. The acceptance criteria is that changes ofi 10% in the plateau voltage and disenmination levels for each beam monitor shall cause a change in the count rate of less than i 5%. AcceptanceCriteria met: Yes O No O Procedure performed by: NCr Research Scientist Date Procedure reviewed by: NCF Research Scientist Date i i Results reviewed by: NRL Dutctor Date m SR#-0-93-5 MAY 281993

PM 3.14.2.3 Page 5 of 9 i Beam Monitor Plateau and Discriminator Setnoints Form e'3) EPITHERMAL #1 1. Time /Date: / 2. ReactorPower: Ch.7 ua; Ch. 9 ua; Nominal Power MW. 3. Beam Designation:

Dateinstalled

4. Hich Voltane and Discriminator 12 vel Data: l High Voltage Disc. level i REF. VALUE Counts- - REF. VALUE - Counts 250 Volts (per 10 s) 4 Volts (per 10 s) 30 0.1 i 50 0.5 l 100 1 150 2 200 3 l 1 i 250 4 300 5 350 6 7 8 9 10 I l Data certified by: NCF Research Scientist Dae Data reviewed by: NCF Research Scientist Dam O SR#-0-93-5 MAY 281993 c ~ ...c,,

I e. PM 3.14.2.3 ~~ Page 6 of 9 l Beam Monitor Plateau and-Discriminator Setnoints Form I lO i l i EPITHERMAL #2: i 1. Tune /Date: / i 2. Reactor Power: Ch. 7 ua; Ch. 9 ' ua; Nominal Power - MW. 3. Beam Designation:

Date installed

i i 4. Hiah Voltnee and Diceriminatar irvel Data: High Voltage Disc. Level-l REF. VALUE - ~ Counts REF. VALUE Counts - -[ 250 Volts - (per 10 s) - 4 Volts (per 10 s)' i

30 0.1

-l 50 - 0.5 100 1 150 2 200 3. l (~ 250-4- 300 5 350 6 7 j l 8 9 i i 10-t i i t i i Data certified by: l NCT Research Scientist Dat i F Data reviewed by: l . NCF Research Scientist Dat i I SR#-0-93-5 MAY 281993-i 1 .i

i PM 3.14.2.3

i Page 7 of 9 l

Beam Monitor Plateau and Discriminator Setnoints Form j O j THERMAL #1: -l i 1. Tune /Date: /~ 2. ReactorPower: Ch.7 ua; Ch. 9 ua;. Nominal Power - MW. 3. Beam Designation:

Date installed

i 4. Hioh Voltane and Discriminatar12 vel Data: I 'l High Voltage Disc. Level l - REF. VALUE Counts - REF. VALUE Counts 500 Volts - (per 10 s) ~ 4 Volts - (per 10 s) 'l 30 0.1 - j 50 0.5: 100 ~1 1 i 150 2 200

3.

f 300 4 400 5= 500 -6 f 600 7 ] 700 8 800 9 10 Data certified by: NCF Research Scientist Dat Data reviewed by: NCT Research Scientist Dae O SR#-0-93-5 MAY 281993.

PM 3.14.2.3 ' Page 8 of 9 Beam Monitor Plateau and Discriminator Setnoints Form-O THERMAL #2: 1. Time /Date: / 2. ReactorPower: Ch.7 ua; Ch. 9 ua; Nominal Power MW.- 3. Beam Designation:

Date installed:

4. High Voltage and Diceriminatnr 12 vel Data: High Voltage Disc. level - REF. VALUE Counts REF. VALUE - Counts 200 Volts (per 10 s) - Not Applicable - (per 10 s) 30 50 .100 -150 200 250 Data certified by: NCT Research Scientist Dae Data reviewed by: NCT Research Scientist Dam-O SR#-0-93-5 MAY 281993.

i, PM 3.14.2.3 Page 9 of 9 Beam Monitor Plateau and Discriminator' Setnoints-Form O GAMMA: 1.- Tune /Date: / 2. ReactorPower: Ch.7 ua; Ch. 9 - ua; Nominal Power MW. 3. Beam Designation:

Date installed:

4. Hinh Voltnae and Diceriminarnr 12 vel Data: High Voltage Disc. level-REF. VALUE ' Counts - REF. VALUE Counts - 200 Volts (per 10 s) - Not Applicable. -(per 10 s) 30 50 100-150 200 250 0 Data cemfied by: NCF Research Scientist Dam Data reviewed by: NCF Research Scientist Dam O SR#-0-93-5 ' MAY 28'1993

i~ PM 3.14.2.4 Page 1 of 34 PM 3.14.2.4 Characterization of the Medical Thernov Beam AU Pumose: i The purpose of this characterization procedure is to determine the dose-versus-depth pmfile of the MITR medical therapy beam on a central axis from the surface of a phantom to a depth at least equivalent to the total thickness of the body part that is to be l treated. Fast neutron, thermal neutron, and gamma ray components are determined. The results of the characterization serve as the reference for subsequent calibration checks of the beam and for beam monitor functional checks. Backemund: The thermal neutron flux, epitbermal neutron flux, photon dose rate, and fast l neutron dose rate are measured along the central axis of a phantom that appmximates the l part of the body that will be treated. A unilateral irradiation is assumed. Fluxes and doses are typically measured at depths of 0,1,2,3,4,5,6,8, and 10 cm and then every 2 cm until the bottom of the phantom is reached. However, a coarser grid may be used in regions where the shape of the dose-depth profile has previously been shown to be monotonic. The thermal and epithermal neutron fluxes are measured using bare and cadmium-covered gold foils. The photon and fast neutron dose rates are measured using calibrated, paired graphite-wall and tissue-equivalent ionization chambers. A general reference on the methods used is Attix [1]. The application of these methods to the MITR medical therapy beam is given by Rogus [2]. Accentance Criteria: ~ \\ j Beam parameters are, upon review of the characterization results by the Director of the MIT Nuclear Reactor Laboratory and by the program's Certified Medical Physicist, judged to be adequate for the conduct of human therapy. Prerequisites: 1. Reactor operating at a power level in excess of 1 MW. (Caution: It is important that reactor operating conditions be maintained constant during beam characterization. Therefore, it is suggested that this procedure only be done when the reactor has been at constant power for at least forty-eight hours.) 2. Beam delimiter and whole body shields are installed. These shields should be in the same position (i 2 mm side-to-side, i 2 mm front-to-back, and i 2 mm up-and-down) as that used for previous characterizations of the beam. 3. A standard phantom is available. This phantom is a right circular cylinder that is made of polyethylene and which is 18 cm in diameter and 20 cm long. This phantom is cut into ten layers so as to allow foils to be positioned at various depths. This phantom is also used for the calibration checks and beam monitor functional checks. Other phantoms may be used provided that there is consistency with these checks. These include the Wax-130 leg phantom and the paraffin half-body phantom. 4. Instmments required for the measurements of the beam's fast neutron and photon components are available including: SR#-0-93-5 MAY 281993

PM 3.14.2.4 Page 2 of 34 a) Tissue-equivalent chamber (Far West IC-18), s b) Graphite-wall ionization chamber (Far West IC-18G), c) Two electrometers (Keithley 616 or 617). The tissue-equivalent and graphite wall chambers as well as one of the electrometers shall have been ca.ibrated by a Secondary Calibration Laboratory within the last two years. The electrometer for which this is done is designated here as the ' calibrated' instrument (Keithley 617) while the other is referred to as the ' field' instrument (Keithley 616). The latter is calibrated against the former using PM 3.14.2.5, " Cross-Calibration of Electrometers." The ' field' instrument is the one used for the characterization. Each electrometer can be calibrated by itself or the electrometer and each chamber can be calibrated as an electrometer-chamber pair. 5. Low-noise signal cables, a high voltage power supply (Canberra HV Supply

1. 2816A or equivalent), high-voltage cables, and a stop watch with an accuracy and resolution of 0.1 s. (Caution: The signal cables should be handled gently. In particular, they should not be bent to radii ofless than 30 cm.)

6. Standard radiological procedures for use of the medical therapy facility are to be observed. Quality Assurance: 73 1. Record the following for the instruments that are used to measure the beam's fast () neutron and photon components: Instmment Serial # Calibration Date Secondary Lab a) Tissue-Equivalent b) Graphite-Wall c) Keithley 617 d) Keithley 616 PM 3.14.2.5 2. Verify that the following were done during the instrument calibrations: a) Tissue-equivalent chamber was flushed with a methane-based tissue-equivalent gas at 5 cc/ minute; b) Graphite-wall chamber was flushed with CO at 5 cc/ minute. 2 Verified: NCF Research Scientist Date Nolc: If flows of 5 cc/ minute were not used, then corrections to the calibrations may be necessary. In that case, record the flow rates that were actually used on the attached data sheet. O 1 N_.) SR#-0-93-5 MAY 281993 e

PM 3.14.2.4 Page 3 of 34 ,q 3. Use PM 3.14.2.6, " Calibration and Stability Check of Ionization Chambers and Q Electrometers," to test the electrometer-chamber pairs for stability and to verify their calibration. Append completed procedure to this document. Stability Check Satisfactory: NCF Research Scientist Date Measurement of Thermal and Enithermal Neutron Fluxes 1. Weigh twenty-six gold foils (5-10 mg, ~0.002" thick) on a calibrated balance (Mettler AT 201 or equivalent) that has an absolute accuracy and repeatability of less than 1%. Place a small piece of pressure-sensitive polyester film tape on the top and bottom of eaci foil, pinch the sticky sides together, and then trim the tape. The foils can be marked with a number written with a permanent marker on the tape. Ents: Gold foils that have been previously irradiated may be used provided that the residual activity is less than 0.3 % of the initial amount. This corresponds to a decay interval of three weeks.) 2. Place the needed number of foils in the phantom at depths of 0,1,2,3,4, 5,6,8, and 10 cm and then every 2 cm until the bottom of the phantom is reached. The uppermost foil (0 cm) can be secured directly on the top of the phantom. Designate these foils as ' bare'. Record foil weights on the attached data sheet or enter them on a spreadsheet. If the latter is used, it (] shall be signed, dated, and reviewed by two NCF Research Scientists. 'V 3. Position the phantom so that it is under the centerline of the bismuth collimator (its centerline when the lead shutter is open) using the fiduciary marks on the inttom of the delimiter. The top of the phantom should be immediately below the bottom of the delimiter. 4. Commence the foil irradiations using the following sequence for opening of the D O shutter and the shutters that contml beam delivery: 2 a) Record ume and date: Tune Date b) Record reactor powerlevel: Ch.7 pa ; Ch. 9 a; Nominal Power MW c) Clear the medical therapy facility room of personnel and close the shield door. Open the D O shutter. (This usually requires three minutes.) d) 2 e) Depress the open button for the H O shutter and observe that it is 2 draining. Wait forty seconds and then open the lead and boral shutters. The ' irradiation start time'is the moment when the lead shutter indicates open. /"N SR#-0-93-5 MAY 281993

PM 3.14.2.4 Page 4 of 34 f) Record irradiation start time: m Tune Date g) Record readings of reactor power indicators once all shutters are open: Ch.7 ,_ a ; Ch. 9 a 5. Irradiate the foils for approximately sixty minutes. (Note: Shorter irradiations are acceptable. The consideration is that a long irradiation minimizes both the effect of the shutter cycle times and the required counting time.) 6. Monitor reactor power channels No. 7 and 9 during the irradiation. The drift should be less than 1 %. 7. Temnnate the foil irradiations using the following sequence for closing the D O shutter and the shutters that contml beam delivery: 2 a) Specify time at which irradiation is to be terminated: Wne Date b) Ten seconds prior to the specified termination time, depress the close button for the H O shutter. 2 (o) c) Close the lead and boral shutters at the official termination time and then close the D O shutter. 2 d) Record time at which the lead shutter was closed: Tune Date 8. Enter the medical therapy room facility, survey, and remove the bare foils from the phantor.1 9. Fold 0.020 inch thick, half-inch diameter cadmium discs in half and use them to cover the other gold foils. These are the ' covered' foils. Record the foil weights on the attached data sheet. l 10. Use polyester film tape to position the covered foils along one of the thin plastic rods that are available for each phantom. The foils should be at depths of 0,2,4,6,8, and 10 cm and then every 2 cm until the bottom of h the ? antom is reached. The uppermost foil (0 cm) can be secured directly on tie top of the phantom. 11. Position the phantom so that it is under the centerline of the bismuth collimator (its centerline when the lead shutter is open) using the fiduciary l marks on the bottom of the delimiter. The top of the phantom should be l immediately below the bottom of the delimiter. l [,) v SR#-0-93-5 MAY 281993

l . PM 3.14.2.4 Page 5 of 34 12. Commence the foil irradiations using the following sequence for opening of i (J,,') the D O shutter and the shutters that control beam delivery: 2 t a) Record time and date: Tune Date b) Record reactor powerlevel: t l Ch.7 a ; Ch. 9 pa ; Nominal Power MW I l c) Clear the medical therapy facility room of personnel and close the shield door. d) Open the D O shutter. ('Ihis usually requires three minutes.) 2 e) Depress the open button for the H O shutter and observe that it is 2 I draining. Wait forty seconds and then open the lead and boral j shutters. The ' irradiation start time'is the moment when the lead j shutterindicates open. l f) Record irmdiation start time: l Tune Date l l g) Record readings of reactor power indicators once all shutters are open: Ch.7 a ; Ch. 9 a l O l V 13. Irradiate the foils for a) proximately sixty minutes. (Note: Shorter irradiations are acceptab e. The consideration is that a long irradiation minimizes both the effect of the shutter cycle time and the required counting time.) 14. Monitor reactor power channels No. 7 and 9 during the irradiation. The drift should be less than 1 % 15. Terminate the foil irradiations using the following sequence for closing the D O shutter and the shutters that control beam delivery. 2 a) Specify time at which irradiation is to be terminated. Tune Dae i b) Ten seconds prior to the specified termination time, depress the. l close button for the H O shutter. 2 c) Close the lead and boral shutters at the official termination time and then close the D O shutter. 2 l d) Record time at which the lead shutter was closed: ( ) Tune Dat %) SR#-0-93-5 MAY 281993 i

PM 3.14.2.4 . Page 6 of 34 l 16. Enter the medical therapy room facility, survey, and remove the covered foils from the phantom. 17. Use PM 3.14.2.7, " Determination of High Purity Ge or Ge(Li) Detector - Efficiency," to determine the efficiency of the detector (a high purity Ge, u Ge(Li), or equivalent) that is to be used for counting the foils. Record the : following Detector Type: , Serial No.: Distance between detector face and source: inches Efficiency at 411 kev where the source was counted: 18. Remove the cadmium discs fmm the covered foils. 19. Count the foils. Details are again given in [2].with the principal j considerations summarized here. i a) In order to accelerate the counting process, position the foils close to or on top of the detector surface. ' In order to ensure accuracy, each foil that is counted should be positioned so that it is within 12 mm of the original foil. Cardboard holders similar to 35 mm projector - slides are available and should be used to position the foils. Obtain the detection efficiency at this in-close position from PM 3.14.2.7. O Record the following: Efficiency at 411 kev where the gold foils are counted. b) For each foil, record the relevant data on the attached sheet. I 20. Calculate the thermal and epithermal neutron fluxes using the method summarized in Appendix A to this procedure. Record calculations on the attached sheet. As an alternative, a spreadsheet may be used to perform and record.these calculations. If used, these shall be signed, dated, and reviewed by two NCF Research Scientists. 21. Normalize the fluxes calculated in step (20) to 5 MWt. Record calculations on the attached sheet. As an alternative, a spreadsheet may be used to ] perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCF Research Scientists. 22. Secure any equipment not required for the subsequent portions of this procedure. Functional and Calibration Check of Medical Therany Facility Beam Monitors 1. Perform PM 3.14.2.1, " Functional Check of Medical Therapy Facility _ Beam Monitors," and PM 3.14.2.2A, " Calibration Check of the Medical ( Therapy Beam via Chamber Measurements." Append a copy of the results ] to this procedure. j i SR#-0-93-5 MAY 281993 i 1 ..)

PM 3.14.2.4 Page 7 of 34 Measurement of the Photon and Fast Neutron Dose Rates ,. S 1. Energize the field electrometer and adjust the high voltage or the HV power supply to + 250 V. Check the HV cable to be certain that the chamber would be at 250i 10 V. The background current, with the voltage applied to the chambers but with no radiation field, should be less than 5E-15 Amperts. 2. Allow the field electrometer to warm up for one hour. Purge the CO line for 20 minutes at ~100 cc/ minutes. (CAUTION: The 3. 2 next step is to connect t' e graphite-wall chamber to the electrometer. When doing so, the electrometer should be in the zero position and the high voltage should be off.) 4. Connect the graphite-wallionization chamber to the CO line, snap on the 2 Lucite tube, and insert it into the phantom. For convenience, measurements should be initiated at the 1 cm position for the head phantom and at the O cm position for the other phantoms. 5. Position the phantom in the beam so that the area in which the measurement will be made is under the center line of the bismuth collimator (its center line when the lead shutter is open) using the fiduciary marks on the bottom of the delimiter. The top of the phantom should be immediately below the bottom of the delimiter. A 6. Reduce the CO flow rate to 5 cc/ minute. (Note: Higher flow rates, up to 2 U 20 cc/ minute are acceptable provided that a correction factor is applied to the chamber current.) Record the CO flow rate on the attached data sheet or 2 enter it on the appropriate spreadsheet. 7. Measure the temperature of the CO flush gas with a thermometer and the 2 barometric pressure with the barometer in the reactor control room Record data on the attached sheet or enter it on the appropriate sheadsheet. 8. Commence the measurements using the sequence given below. Information may either be recorded on the attached data sheet or, as an alternative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCI' Research Scientists. a) Record time and date on the attached data sheet. b) Record reactor power level on the attached data sheet. c) Clear medical therapy room of personnel and close the shield door, d) Open the D O shutter and then the H 0, lead, and boral shutters. 2 2 Wait until all shutters indicate full open. 3(G SR#-0-93-5 MAY 281993

1 PM 3.14.2.4 Page 8 of 34 e) Measure the current using racetrack timing. Collect charge for about 7(d one minute and then record the charge and time interval. Repeat twice and average the results of the three measurements. The three measurements should be within about 1% of the average. If not, several additional readings should be taken to ensure the system is at steady-state. Record data on the attached sheet. f) Close all shutters, enter the medical therapy room facility, survey, and reposition the chamber for the next measurement. g) Repeat steps (c) - (f) above with measurements taken at 0,1,2,3, 4,5,6,8, and 10 cm and then every 2 cm until the bottom of the phantom is reached. For the head phantom, data for the O cm position is obtained by placing the chamber on the top surface of the phantom. During the other head-phantom measurements, it is important that the head phantom be completely filled with water. When using the leg or half-body phantoms, the void above the chamber should be filled with a Wax-130 or paraffin insert. h) Upon completion of the measurement at the bottom of the phantom, repeat the measurement for the top of the phantom. Compare this result to the one obtained at the outset of the measurements series. The two should agree within 1%. 9. Purge the tissue-equivalent gas line for 20 minutes at 100 cc/ minute. (CAUTION: The next step is to disconnect the graphite-wall chamber and 3 to connect the tissue-equivalent chamber to the electrometer. When doing so, the electrometer should be in the zero position and the high voltage should be off.) 10. Connect the tissue-equivalent ionization chamber to the tissue-equivalent gas line, snap on the Lucite tube, and insert it into the phantom. For convenience, measuirments should be initiated at the 1 cm position for the head phantom and at the O cm position for the other phantoms. I1. Position the phantom in the beam so that the area in which the measurement will be made is under the center line of the bismuth collimator (its center line when the lead shutter is open) using the fiduciary marks on the bottom of the delimiter. The top of the phantom should be immediately below the bottomof thedelimiter. 12. Reduce the tissue-equivalent gas flow rate to 5 cc/ minute. (Helg: Higher flow rates, up to 20 cc/ minute are acceptable provided that a correction factor is apphed to the chamber current.) Record the tissue-equivalent gas flow rate on the attached data sheet or enter it on the appropriate spreadsheet. l 3. Measure the temperature of the tissue-equivalent gas with a thermometer and the barometric pressure with the barometer in the reactor control room Record data on the attached sheet or enter it on the appmpriate spreadsheet. O l L) SR#-0-93-5 MAY 281993

i PM 3.14.2.4 Page 9 of 34 j 14. Commence the measurements using the sequence given below. Information (~^I may either be recorded on the attached data sheets or, as an alternative, a G spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCI' Research Scientists, a) Record time and date on the attached data sheet. i b) Record reactor power level on the attached data sheet. c) Clear medical therapy room of personnel and close the shield door. Open the D O shutter and then the H 0, lead, and boral shutters. d) 2 2 Wait until all shutters indicate full open. e) Measure the current using racetrack tumng. Collect charge for about one minute and then record the charge and time int:rval. Repeat l twice and average the results of the three measurements. The three l measurements should be within about 1% of the average. If not, several additional readings should be taken to ensure the system is at i steady-state. Record data on the attached sheet. f) Close all shutters, enter the medical therapy room facility, survey, and reposition the chamber for the next measurement, g) Repeat steps (c) - (f) above with measurements taken at 0,1,2,3, 4,5,6,8, and 10 cm and then every 2 cm until the bottom of the phantom is reached. For the head phantom, data for the 0 cm position is obtained by placing the chamber on the top surface of the phantom. During the other head-phantom measurements, it is s important that the head phantom be completely filled with water. When using the leg or half-body phantoms, the void above the chamber should be filled with a Wax-130 or paraffin insen. h) Upon completion of the measurement at the bottom of the phantom, repeat the measurement for the top of the phantom. Compare this result to the one obtained at the outset of the measurements series. The two should agree within 1%. 15. Record the MIT Research Reactor's power history for the seven days prior to the above measurements using the attached form or enter the information on the appropriate spreadsheet. 16. Calculate the photon and fast neutron dose rates using the procedure described in Appendix B and record results on the attached data sheet. As an alternative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCI' Research Scientists. v SR#-0-93-5 MAY 281993

I-PM 3.14.2.4 l Page 10 of 34 17. Review the RBE factors and record the values to be used. Comnonent RBE Soume* B-10 N-14 Fast Neutron Photon

• If RBE values are unchanged from previous characterization, indicate

'N/A.' 18. Calculate the nitrogen-14, boron-10, and RBE-weighted dose rates (including the dose rate in healthy tissue and tumor) using the procedure given in Appendix C. (Natt: Concentrations of 7.5 ppm boron in healthy tissue and 30 ppm boron in tumor are assumed.) Record the results on the attached data sheet As an altemative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCT Research Scientists. 19. Plot the data obtained from steps (16) and (17) above as dose-depth distribution curves. These curves are to include the 30 ppm B-10, N-14, photon, fast neutron, healthy tissue, and tumor dose rates. The plots should be signed and dated by both the NCF Research Scientist who pmpamd them and the NCF Reseamh Scientist who reviewed them. f~ 20. Secure any equipment not required for the subsequent portions of this procedure. Calibration of Medical Thernov Facility Beam Monitors 1. Boot-up the beam monitor data acquisition program's computer system. 2. Use PM 3.14.3.4., " Beam Monitor System Setpoints," to verify the settings of all beam monitor system parameters (gains, discriminator setpoints, etc.). 3. Initiate the beam monitor data acquisition program. 4. Record the reactor power level (Ch. 7, Ch. 9, and nominal) on the attached data sheet or enter this infom1ation on the appropriate spmarkheet. 5. Take five one-minute counts for each monitor. Record data on the attached sheet and compute the average for each monitor. As an alternative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCF Research Scientists. t SR#-0-93-5 MAY 281993

PM 3.14.2.4 l Page 11 of 34 l c 6. Normalize the average counts for each monitor to 5 MWt. (Egin: Channel () No. 7 should be used for this purpose unless otherwise indicated by a j l Senior Member of the Operations Staff.) Describe method used for normalization: 1 l l 7. Use the dose-depth plot obtained from step (18) of the third part of this procedure to determine the dose rate to healthy tissue: RBE-cGy/ minute at 1 cm on the beam's central axis in a head phantom with 7.5 ppm boron assumed in healthy tissue and 30 ppm bomn assumed in tumor. 8. Calibrate the output of each beam monitor in tenns of the dose rate delivered to heaf thy tissue. The resulting calibration factor will have units of ' cps per RBE-cGy/ minute.' Record the results on the attached data sheet. As an alternative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCF Research Scientists. 9. Secure the medical room facility and equipment or continue with other l l scheduled procedures as appropriate. 10. Pmvide results of this characterization and beam monitor calibration to the Director of the MIT Nuclear Reactor Laboratory and to the Program's l Certified Medical Physicist. l Characterization performed by: NCF Research Scientist Date Characterization reviewed by: NCF Research Scientist Dae Beam judged adequate for the conduct of human therapy: Yes O No O l Certified Medical Physicist Date NRL Director Date J SR#-0-93-5 MAY 281993

PM 3.14.2.4 Page 12 of 34' References l 1. Attix. F.H., Introduction to Radiolonical Physics and R ndiation Dosimetry," John-i l Wiley & Sons, New York,1986. l l 2. Rogus, R., Protocol for Mixed Field Dosimetry of Epithermal Neutrons for Boron Neutron Captuit Therapy at the MITR-II Research Reactor," MITNRL-054, October 1992. f 1 O i L i l l l O SR#-0-93-5 MAY 281993 1 -. m ... + -..--.-

l i PM 3.14.2.4 Page 13 of 34 CD Bam Foils Covered Foils i Weight Img). Weight Ungl i 1 14 2 15 3-16 4 17 5 18 6 19 7 20 8 21 9 22' 10 ?.3 11 24 i 12 25 13 26 i Balance Type: Serial No.: Calibration Date: Foils weighed by: NCT Research Scientist Date l Weights spot-checked by: NCT Research Scientist Date i SR#-0-93-5 MAY 281993

PM 3.14.2.4 Page 14 of 34 ' Record of Foil Counts Relative to Time Count Counting AreaUnder. Foil # Detector Staned Time (s) 411 kev peak 1 2 3 i 4 .5 6 7 8 9 10 11 12 i 13 15 i 16 17 18 l 19 ] 20 21 22 23 24 l l-25 26 Counts taken by: NCF Research Scientist Date ~ Data rev;ewed by-lf NCF Research Scientist Date j SR#-0-93-5 MAY 281993 l [ ...i... ~~

j ' PM 3.14.2.4 - - Page 15 of 34 ' i I l Record of Thermal and Enithermal Neutron ~ Fluxes !O 4 4 j ReactorPower: Ch.7 a; Ch.9 a; NominalPower: MW '] Beam Designation: Date Installed: i i Nominal Power Normativ,a to 5 MWt i Phantom l Position Epithermal Epithennal (cm) Thennal Flux Flux 'Ihermal Flux Flux .l 4 i 0 1 4 j 2 s i 3 i 1 4 4 l 1 1 5 1 4 i i O 8 i 10 12 14 i 16 ~ ( 18 i i l Calculations performed by: NCT Research Scientist Date l Calculations reviewed by: .NCT Research Scientist Date SR#-0-93-5 MAY 281993 =.. . ~. a.

PM 3.14.2.4 - Page 16 of 34 i 1 1 Granhite-Wall Ionization Chamber Measurements ' O l \\/ Beam Designation: Date Installed: Phantom Type: Chamber Type: Serial #: CO gas flow: cc/ minute 2 Temperature: C Barometric pressure: CO gas flow when chamber was calibrated: cc/ minute 2 Date and Time: Date Tune l l ReactorPower: Ch.7 a; Ch.9 a; NominalPower MW r Collection. Phantom Position Measurement # Tune Charge - Deviation 0cm I i 2' i 3 Average N/A 0.0% 4 1m 1 2 3 Average N/A 0.0% i 2m 1 2 3 Average N/A 0.0% 3cm 1 2 3 Average N/A 0.0% 4cm 1 I 2 O 1 V 3 Average N/A 0.0% SR#-0-93-5 MAY 281993 l i

uq, l PM 3.14.2.4 Page 17 of 34 r. I Granhite-Wall Ionization Chamber Measurements (Continued)- Collection Phantom Position Measurement # Tune Charge - Deviation l 5cm 1 2 3 l Average N/A 0.0% 6cm 1 2 3 i l Average N/A 0.0% 8cm 1 l 2 l 3 l Average N/A 0.0% i 10 cm 1 0 2 3. Average N/A 0.0% - 12 cm 1 2 3 Average N/A 0.0% l 14 cm 1 2 3 Average N/A 0.0% 16 cm i i t 3 l Average N/A 0.0% O SR#-0-93-5 MAY 281993

1 l PM 3.14.2.4. Page 18 of 34 i -or

• iie-w ii'e i iie caemder ue e reme=<s(co ti ea).

O l 4 l Collection Phantom Position Measurement # Time Charge Deviation f 0cm 1 2 3 i Average N/A 0.0% I l l i i 1. For each phantom position, the deviation of each ofits three measurements from the average is less than 1%. 2. 'Ihe average value of the charge collected for the 0-cm measurement at the end of i the measurement series is within 1% of that obtained for the 0-cm measurement at - the start of the measurement series. I Certified by: NC1' Research Scientist ' Date t Date reviewed by: l NCT Research Scientist - Date O SR#-0-93-5 MAY 281993 i

• r+e

--tW-D 4

PM 3.14.2.4 - Page_19 of 34 i Tissue-Eaulvalent Ionization-Chamber Measurements - ~ Beam Designation: Date Installed: t Phantom Type: j i Chamber Type: Serial #: l Tissue-equivalent gas flow: cc/ minute i Temperature: - C Barometric pressure: l Tissue-equivalent gas flow when chamber was calibrated: cc/ minute - Date and Time-Date -Tune Reactor Power: Ch.7 pa; Ch. 9 a; NominalPower MW-t Collection Phantom Position Measurement # Time Charge Deviation - i, f 0cm 1 O 2 3 i Average. N/A 0.0% 1cm 1 [ 2 3 i Average N/A' O.0% [ 2cm 1 2 i 3 Average N/A 0.0% i 3cm 1 I 2 3 Average N/A 0.0% 4cm 1 2 3 Average N/A 0.0% SR#-0-93-5 MAY 281993 l l I' l-

i PM 3.14.2.4 Page 20 of 34 4 i Q Tissue-Eauivalent Ionization Chamber Measurements i (Continued) i Collection Phantom Position Measumment # Tune. ~ Charge Deviation 1 5cm 1. 2. 3 Average N/A 0.0% -l l 6cm 1 .2 '3 l l Average N/A. 0.0% t l 8cm 1 l 2 3 Average N/A 0.0% O' 10 cm 1 3 Average N/A 0.0% 12 cm 1 2 3 i Average N/A 0.0% i 14 cm 1 l 2 3 i Average N/A 0.0% 16 cm 1 -2 3 Average N/A 0.0% L l l SR#-0-93-5 MAY 281993

i PM 3.14.2.4 Page 21 of 34 1 1 Tissue-Eauivalent Ionization Chamber Measurements (Continued): j Collection Phantom Position Measurement # Tune Charge Deviation l Ocm 1 l 2-l 3 Average N/A 0.0% i i e '1. For each phantom position, the deviation of each ofits three measurements from the i l average is less than 1%. l 2. The average value of the charge collected for the 0 cm measurement at the end of i the measurement series is within 1% of that obtained for the 0-cm measurement at. l-the start of the measurement senes. l I Certified by: NCT Research Scientist - Dane - Data reviewed by: NCF Research Scientist - Dae t I s .I f 1 SR#-0-93-5 MAY 281993 i .... + ,w..

i i i PM 3.14.2.4 - Page 22 of 34 l Record of Reactor Power Historv i O i -~ i Daic Tune' Ch. 7 ( a) Ch. 9 ( a) Nominal Power i t r l t . i i l l l r l I l l i O Data obtained by: NCT Research Scientist Date Data verified comst-Senior Reactor Operator Date. . 1 SR#-0-93-5 MAY 281993-i P 2 P .<--.-.r

O O O ~ ~ Calculation of Photon and Fast Neutron Dose Rates: Beam No. en ? Brain Dose Rates Muscle Dose Rates 6 Phantom Graphite Chamber Tissue Chamber (cGyhninute) (cGyhninute) g Position 6 (cm) Measumi Conected Measured Corrected Photon - Fast Neutron - Photon Fast Neutron 0 1 2 3 4 5 6' 8 10 12 14 16 2? ? ' g> Calculation peifunid by: E[ j NCT Research Scientist Dae. l fig ' 2, y Calculation reviewed.by: g 'h NCF Research Scientist-Dee

~ O O 0: Calculation of N-14. B-10. and RBE-Weichied Dose Rates 5 Phantom N-14 Dose Rate (cGv/ minute) B-10 Dose Rate (cGvhninute) g Position 0 (cm) Muscle Brain Healthy Turmor 0 1 2 3 4 5 6 8 10 12 14 16 ?? v$ Calculation performed by: EC j NCF Research Scientist Dane %g~ P ia Calculation reviewed by: yh NCT Research Scientist Dane i i .m- ~ --.. .e4. =-mn --m..w-, c _-,_mo-m m

+ p g V V V.'. ' Calculation of N-14. B-10. and RBE-Weiehted Dose Rates (Continued) eng RBE-Weighted Dose Rates - 66Y Phantom Position (cm) 30 ppm B-10 ~ 7.5 ppm B-10 N-14 Fast Neutron Photon Healthy Tissue Tumor 0 1 2 3 4 4 - 5 6 8 10 12 14 16 33 =- d h5 Calculation performed by: o,,.3 = NCF Research Scientist Date gu-Calculation reviewed by: NCF Research Scientist Dane - .... ~

PM 3.14.2.4 l Page 26 of 34 Data Sheet for Beam Monitor Calibration l Beam Designation: Date Installed: Date and Time: Date Tune Reactor Power: Ch. 7 - a; Ch. 9 pa; Nominal Power: MW i 1 Beam Monitor Counts (cos). i Count # Epithermal #1 Epithermal #2 Thermal #1 Thermal #2 Gamma l 1 [ 3 4 l [ 5 1 Average 5MWt l' i ] SR#-0-93-5 MAY 281993 1

1 PM 3.14.2.4 Page 27 of 34 Data Sheet for Beam Monitor Calibration (Continued) Calibration Factor for Dose l Dose Rate to Normalized I Monitor Healthy Tissue Count Rate - Calibration Factor (RBE-cGy/ minute) (eps) (eps)/(RBE-cGy/ minute) Epithermal #1 l Epithermal #2 Thermal #1 i Thermal #2 Gamma CAUTION: The above correlation factors are for dose to healthy tissue at I cm on the beam's central axis in a head phantom with 7.5 ppm boron assumed in healthy tissue and l 30 ppm boron assumed in tumor. f I Data certified by: NCF Research Scientist Date l Data reviewed by: NCF Research Scientist Date SR#-0-93-5 MAY 281993 i

PM 3.14.2.4 Page 28 of 34 Anoendix A p) Calculation of Thermal and Epithermal Neutron Fluxes The method for calculating the thermal and epithermal fluxes for the MITR Medical Therapy Room Beam is described in detail by Rogus [2].- A summary is given here. The equation numbers used here correspond to those in Reference Two and are therefore not consecutive. The saturated activity for an infinitely-long irradiation and the 2200 m/s flux are given by the relations: AC A*= (36) c 'l - e-h -h _ e-h2 1 o e $2200 = A o2200 _( mb s - Fcd (37) v (me j_ t i where Am is the saturated activity (disintegrations /s); i A is the decay constant (s-1 in the numerator and inverse' days in the (Q denominator); LJ I C is the net counts under the 411 kev Au-198 peak (total counts minus background counts); e is the overall counting efficiency, which accounts for self-absorption (e ). a l detector efficiency (ed), and abundance of the detected radiation (e,) with all i efficiencies given as numbers, not percents; t is theirradiation time (days); o ti is the count start time (days); i l 12 is the count end time (days); 2 &2200 is the 2200 m/s absorption cross-section for gold-197 (cm / atom), ~1 j mb is the bare foil mass (mg); m is the covered foil mass (mg); and e Fcd is the cadmium conection factor. All times are referenced to the start of the irradiation which is considered zero. Upon substitution of known constants, the following are obtained: ) SR#-0-93-5 MAY281993 i

J L L PM 3.14.2.4 j I Page 29 of 34 1- " j Soecific Saturated Activity of the Bare Foil:

i 4rO 1

' Ag 2.975 E-6 x (C/ mb)- 1 ~ oke-12 ) j sm; 0.989 x 0.955 x ed Xl 1 - e-6 F where t, t, and t are in days.- ~i o i 2 1 t 2 Specific Activity of the Covered Foil-1 ' Ag 2.97 E-6 x (C/ ni ) j e - 0.989 x 0.955 x ed x (1-e-0.257to){,-0.257t _ e-0.2571 j i 2 ( ms i where t, t, and 1 are in days. l o i 2 l Neutron Flux at 2200 m/s: ] - 196 7 x 1000 ' 'Ag - 1.02(IA . sal 2200, 6.02 E+23 x 98.8E-24,, m. sb m. se, j where the factor of 1000 in the numerator of the last equation is to convert grams to milligrams. Also,it has been assumed that the correction for self-absorption of 411 kev photons in the gold foil is 0.989, that the 411 kev photon abundance is 0.955, and that_the i cadmium correction factor is 1.02. 'Ihe latter quantity is a function of foil thickness. Enithermal Neutmn Flux: The epithermal neutron flux can now be found. It is given by the relation: 10.1(F )(Asa/m)c(W) ed $ epi = (50)- (Aa)(RI)(F,,,) where $ep; is the epithermal neutron flux (n/cm2 ); 3 RI is the resonance integral for an ideal, infinitely dilute gold foil (cm2); and - F is the resonance self-shielding factor. m Upon substitution of known constants, the following is obtained: - 10.1'x 1.02 (A,g / m)c= x 196.97 x 1000 $*P = i -. 6.02E+23 + 1560E-24 x 0.28 where the resonance integral is taken as 1560 barns, and the resonance self-shielding factor is 0.28. O SR#-0-93 MAY281993 N 9 y e-Q g49 sy p-- -N =>pe-c -e ce = f W r -putes v*'TWhav tr -s+y a 4veg s uwgg-t --W*W "y F e r -gNW T-

~ PM 3.14.2.4 Page 30 of 34 Anoendix B Calculation of Photon and Fast Neutron Dose Rates The method for calculating the photon and fast neutron dose rates for the MITR Medical Therapy Room Beam is described in detail by Rogus [2]. A summary is given here. The equation numbers used here correspond to those m Reference Two and are therefore not j consecutive. The first step is to correct the currents measured with the electrometer for the gas flow rate, reactor power history, gas temperature, and gas pressure. This is done using the mlation: I = (f /f )(fTP)Im - (f )(@5)/(fRP) (19) c H f t where -I is the corrected current [ Coulombs / minute), c fu is the correction factor for the reactor's power history, fr is the correction factor for the gas flow rate, _ fTP is the cormction factor for the gas temperature and pressure, Im is the measured current [ Coulombs / minute], v f is the thermal response correction factor [ cpm /(n/enAs)], t &5 is the 5 MW 2200 m/s flux in the sensitive volume of the chamber ~ [n/cm2.s], and fRP is the scale factor for the reactor power. The quantity f is determined from the reactor's power history [2]. It is unity if the reactor H is at steady-state during the measurements. That is, the reactor should have been at constant power for a sufficiently long time prior to the initiation of measurements so that thermal equilibrium has been attained. The quantity fr is unity if the gas flow rates used during the measurements were those employed during the chamber calibrations. If this was not the case, refer to Reference Two for tabulated corrections. The quantity f i TP s given by the relation: ' T + 273 ' f 29.92' fTP = (22 + 273s ( P s where T and P are respectively the temperature (C) and pressure (inches Hg) of the purge gas in the sensitive volume of the chamber. The thermal response correction factor f,t which has units of [(counts / minute)/(n/cm2-s)] and has a magnitude of 1.5E-20 for the graphite-wall chamber and 4.77E-20 for the tissue-equivalent chamber. Finally, the quantity f i RP s scale factor for the reactor power and is given by: fap = 5.0/ n p SR#-0-93-5 MAY 281993

PM 3.14.2.4 Page 31 of 34 where n is the reactor power (MW) that equates to the reading on MITR Channel No. 7 p 7(V during the characterization. The conection for relative humidity is less than 0.3% and is therefore omitted. It is assumed that fa and fr are unity, then upon substituting known values, equation (19) becomes: For the graphite-wall (carbon-craphite) chamber-Ico = T + 2733 f 29.9~0 - (1.50E-20)($3)(5.0/ n ) I m p t 293 s( P s For the tissue-equivalent chamber: 'T + 2733 f 29.92' Im - (4.77E-20)(45)(5.0/n ) ITE = p ( 293 ;( P s Once these corrected currents are available, the photon and fast neutron dose rates can be calculated from the relations: 6_BTE CG - Bco n (3) T BnACG - Bco ATE TE CG - Aco Dn [/'} 6_A (4) s._ ATE BCG - ACG BTE where is the photon dose rate (cGy/ minute), y b is the fast neutron dose rate (cGy/ minute), n Dco is the corrected current of the graphite-wall (carbon-graphite) ionization chamber due to the mixed field (Coulombs / minute), and DTE is the corrected current of the tissue-equivalent ionization chamber due to the mixed field (Coulombs / minute). The parameters in equations (3) and (4) that are designated by the letters A and B describe the photon and neutron sensitivities of the chambers [2]. The Q values equal to the I values calculated above for each chamber. Upon substitution of known quantities into equations (3) and (4), the dose rates to brain and muscle can be determined. These are given below by equations (13) and (14) respectively. As an aid to the prospective user, units are also shown in these equations. n SR#-0-93-5 MAY 281993

l PM 3.14.2.4 l Page 32 of 34 i l l Brain: 'v Photon Dose Rate: i C C C C i 4.29E-11 ICG - 3.33E-12 In l 6= cGy en cGy un (13a) Y C C C C 4.29E-Il 7.62E-11 - 3.33E-12 4.67E-11 cGy cGy cGy cGy or l C C C C l 4.29E-11 Ico. - 3.33E-12 In b= cGy nn cGy un (13b) y l 3.114E-21 2 cGy Fast Neutron Dose Rate: C C C C 4.67E-11 ICG - 7.62E-11 In. 6" = cGy min cGy nun (14a) C C C C 4.67E-11 3.33E-12 - 7.62E-11 4.29E-11 cGy cGy cGy cGy f') or s.- C C C C 4.67E-11 ICG. - 7.62E-11 In 6= (14b) n 2 C -3.114E-11 2 cGy Muscle: Photon Dose Rate: C C C C 4.43E-11 ICG - 3.33E-12 In g_ cGy min cGy min (15a) Y C C C C 4.43E-11 7.62E-11 - 3.33E-12 4.67E-11 cGy cGy cGy cGy or C C C In "C 4.43E-11 I - 3.33E-12 CG ". b= Y Y y (15b) 3.221E-21 2 cGy 7._. IN. SR#-0-93-5 MAY 281993 1

PM 3.14.2.4 Page 33 of 34 t f-Fast Neutron Dose Rate: C C C C 4.67E-11 Ica. - 7.62E-11 In, g_ cGy min cGy nun (16a) n C C C C 4.67E-11 3.33E-12 - 7.62E-11 4.43E-11 cGy cGy cGy cGy or C C C C l 4.67E-Il Ica - 7.62E-11 In g_ cGy min cGy min (16b) C -3.221E-11 2 l cGy The photon and fast neutmn doses calculated here are to be normalized to a reactor power of 5 MW. This should be done using the Channel 7 value with all shutters closed. The latest calibration of Channel 7 to reactor thermal power at the end of the week should be I used. /'~ L)T b SR#-0-93-5 MAY 281993

PM 3.14.2.4 4 Page 34 of 34 i Annendix C p 1 d-Calculation of N-14. B-10. and RBE-Weighted Dose Rates i ) A. N-14 Dose Rate 2 2 For brain: 6 = 1.401E-11 cGyem / n x 42200 n /cm -s x 60 s/ min 2 2 For muscle: b = 2.724E-11 cGyem / n x $2200 n /cm -s x 60 s / min l B. B-10 Dose Rate in Healthy tissue @ 7.5 c_om B-10 2 2 = 8.66E-12cGyem / n-ppm x 7.5 ppm x 42200 n / em -s x 60 s/ min C. B-10 Dose Rate in Tumor Tissue @ 30 ppm B-10 2 2 8 = 8.66E-12cGyem / n-ppm x 30 ppm x $2200 n / cm -s.x 60 s/ min l D. RBE-Weighted Dose Rates I l The relations given below an: predicated on the following RBE values: 4.0 for B-10; 2.3 for N-14,2.3 for fast neutrons; and 0.5 for photons. These values should be reviewed at every characterization of the MITR Medical herapy Facility Beam, O t a) RBE 30 ppm B-10 dose rate = 4.0 x Da.io,30 ppm RBE 7.5 ppm B-10 dose rate = 4.0 x Da.io.7.5 ppm l RBE N-14 dose rate = 2.3 x Dn.i4 '(muscle or brain) RBE fast neutron dose rate = 2.3 x Drn RBE photon dose rate = 0.5 x Dy b) RBE healthy tissue dose rate = 4.0 x Da.10.7.5 ppm + 2.3 x Dn.34 + 2.3 x Drn + 0.5 x Dy Use muscle N-14 dose to calculate the muscle tissue dose and use brain i N-14 dose to calculate the brain dose. c) RBE tumor tissue dose rate = 4.0 x Ds.io,30 ppm + 2.3 x Dn.14 +2.3 x Drn +0.5 x Dy Use muscle N-14 dose to calculate the muscle tissue dose and use brain N-14 dose to calculate the brain dose. SR#-0-93-5 MAY 281993

1 PM 3.14.2.6 Page 1 of 6 i 8 O PM 3.14.2.6 Calibration and Stability Check of Ionization f Chambers and Electrometers ~ Pumose: 'Ihis pmcedure provides a standard method for checking the calibration and stability i of both the ionization chambers and the electrometers. The method is a relative, not an absolute, calibration and is intended to detect trends. Acceptance Criteria: Exposure rates measured with the Cs-137 check source are within 3% of those obtained during the most recent calibration of the instruments in question at a secondary calibration laboratory. Prereayisites: 1. The following are available: a) Tissue-equivalent chamber (Far West IC-18), b) Graphite-wall ionization chamber (Far West IC-180), (] c) Magnesium-wall ionization chamber (Far West IC-18 #670-TMW), U d) An electrometer (Keithley 616 or 617). Only one electmmeter is required. liither may be used. 2. The three chambers and the Keithley 617 shall have been calibrated by a Secondary Calibration Laboratory within the last two years. The Keithley 616 shall have been calibrated against the Keithley 617 within the last two years. 3. Low-noise signal cables, a high voltage power supply (Canberra HV Supply 1

1. 2816A or equivalent), high-voltage cables, a calibration jig, a digital voltmeter, and a stop watch with an accuracy and resolution of 0.1 s. (Caution: The signal cables should be handled gently. In particular, they should not be bent to radii of less than 30 cm.)

j 4. Standard radiological procedures are to be observed. 5. 5 Ci Cs-137 source. 6. A thermometer and a means of monitoring barometnc pressure. 7. The area in which the calibration is to be performed is to be secured and posted as a "High Radiation

• area.

SR#-0-93-5 MAY281993

i I PM 3.14.2.6 l Page 2 of 6 -i I 'I l. Procedure: 1 1. Record the following information: I l Instmment Serial # rnlibration Secondmv DWa lah-i t i Tissue-equivalent Chamber l l Graphite-Wall Chamber Magnesium-Wall Chamber K - 616 electrometer PM 3.14.2.5 K - 617 electrometer i 2. Describe the signal cable: 3. Energize the electrometer and adjust the high voltage or the HV power i supply to + 250 V. Use the digital voltmeter to verify that the voltage applied to the cable is + 250 V i 10 V. The background current, with the voltage applied to the chamber but with no radiation field, should be less than IE-14 Amperes. 4. Allow the electmmeter to wann up for one hour. 5. Attach the calibration jig to the Cs-137 source and plug in the Cs-source warning lights. 6. Set the K-617 electrometer to the Coulomb mode and for autoranging. 4 Check that the Volt / Ohm Guardis Off. 7. Attach any one of the ionization chambers to the electrometer and position l one of the chambers in the calibration jig. Record the position number (one or two) on the attached data sheet. The chamber should now be at +250 V. 1 8. Allow the chamber-electrometer pair to stabilize for several minutes. l 9. Depress the electmmeter's 'zem correct' button so as to zero the unit. l 10. Perform the following: a) Disable the zert>< heck. b) Collect charge for about one minute. AU SR#-0-93-5 MAY 281993

l' PM 3.14.2.6 i l Page 3 of 6 lf c) Record the collected charge: Coulombs i and the collection time: minutes. l d) Compute the current: Coulomb / minute. l c) Repeat steps (a) - (d) and record the collected l charge: Coulombs and the collection time: minutes. f) Compute the current: Coulombs / minute. I g) Average the currents obtained in steps (d) and (f) above: i Coulombs / minute. This is the background current cf the electrometer. 11. Verify that the background current for the electrometer is less than i 6E-13 Coulombs / minute. If not, notify the Director of the MIT Nuclear Reactor Laboratory and the program's Certified Medical Physicist. 12. Lift the depleted uranium shield to irradiate the chamber. (Note: The chamber is open to the air; no flushing gas is needed.) Four measurements should be taken and the results recorded on the attached data sheet. Also l record ambient tempenture and pressure. l 3 13. Check the repeatability of the measurements obtained in step (15) above. If l (V the repeatability is not within 1%, then the electrometer, chamber, or system l as a whole (including cables) is not stable. Suspend the procedure until the cause isidentified and rectified. l 14. Lower the depleted uranium shield to shut off the beam. 15. Compute the average of each of the four measurements and record it on the attached data sheet. 16. Repeat steps (7) - (14) for each of the three ionization chambers. 17. Obtain the Co-60 calibration factors in air at 22 C and 29.92 inches of Hg from the most recent calibration of the three ionization chambers by a secondary calibration laboratory. Record these below: Tissue-equivalent: Roentgen / Coulomb Graphite-wall: Roentgen / Coulomb Magnesium-wall: Roentgen / Coulomb j Date of Calibration:

Laboratory a

(V SR#-0-93-5 MAY281993 l

PM 3.14.2.6 Page 4 of 6 18. Calculate and record the measured exposure rates for each chamber. Use the following equation: A = N Q T+ 273 29.92 (ECP) i x 22* + 273 P where i is the exposure rate (Roentgen / minutes), N is the Co-60 exposure calibration factor in air at 22 'C and 3 29.92 inches of Hg, D is the chamber current (Coulomb / minute),_ T is the temperature of gas in sensitive volume of chamber ( C),and i l P is the pressure of gas in sensitive volume of chamber (inches of Hg). I ECP is the electrometer calibration factor for the panicular electrometer and scale. 19. Obtain the expected exposure rate from the most recent reference calibration l~ of the Cs-137 source: Roentgen / Coulomb on _i (Note: This would normally be the exposure rate obtained following the most recent calibration of the chambers by a secondary calibration j laboratory.)- 20. Calculate and record the expected exposure rate. Use the following f equanon _ 04935 11/2 A=ie o where i is the expected exposure mte'(Roentgen / Coulomb), io is the exposure rate meastued at the time of the most recent l reference calibration (Roentgen / Coulomb), t is the time elapsed since the reference' calibration (years), and 1/2 is the half-life of Cs-137 (30.17 years). 1 i t SR#-0-93-5 - MAY 281993

~.. PM 3.14.2.6 -

i Page 5 of 6' jj t

21. Calculate the percent difference between the measured and expected - ~ l l exposure rates and record on the attached data sheet. 22. Decnergize and store all equipment. l The acceptance criteria is that the measured and expected exposure rates agree within i 2E t Acceptance Criteria Met: .Yes No i a i Calibration performed by: [ NCT Research Scientist Date 1; O 1 Calibration checked by: l NCF Research Scientist-Date j l. i i i l -t Results reviewed by: NRL Director - Date l i t i .i f . SR#-0-93-5 .MAY 281993 i s -l l ..-.~.

-i W V -Data Sh :t for~ lontration Cham er Calibration and Stability Check Pbsition Ionization h"ad Measured Average Pressure Temperature Measural ' Eer y number chamber Charge (C) Time (s) Current (inches Hg) ( C) Exposure (Meas-(1 or 2) (C/ min) Rate - Exp)/Exp 6 (R/ min) (%) ew in 1-Chamber 1. i 2. l Time 3. 4. Tissue 1. 2. Time 3. 4. Graphite 1. 2. I Time 3. I 4. i-i Magnesium 1. 2. t l Time 3. 4. i'

• t! *tf i

AK +w l g Expected Exposure Rate (R/ min): h g g-m ;o. i. 4 :

• a i

w Certified by: ~ NCF Research Scientist ' Date l-Data reviewed by: NCF Research Scientist - - Dane, m,J.-..--.e,,ee,.-e.-. - -, ......--.....~....~,ow ~,-.~.,,4.si-,.-...,-...--..J.~ .,.m., 4.-.. ..._,.,..-..---,,.e,.m....__,-.-...+.,,.....,....~v.m..- -..w

3' PM 3.14.2.5 Page 1 of 7 - 3 i O r a 3.14.2.5 cress-ceiidretiee er siec're-eters Puroose: His procedure provides a standard method for calibrating electrometers against an electrometer that has been calibrated at a secondary calibration lahomtory. l Accentance Criteria: Two Coulomb scales (E-10 C and E-09 C) of the field electmmeter are calibrated to within 2 % against the unit that was sent to the secondary calibration laboratory. l

Background:

Provision No.14(c) and Definition (5) of MITR Technical Specification No. 6.5 - establish a requirement that "the beam monitors be calibrated at two-year intervals against instruments that measure dose including a tissue-equivalent chamber and a graphite or magnesium wall ionization chamber (or the equivalent to any of these three) that have in t turn been calibrated by a secondary calibration laboratory." As part of this requirement, one of the facility's electrometers is included in the instruments sent to the secondary calibration laboratory. This procedure pmvides a means for calibrating the facility's other electrometers (if any) against the one calibrated at the secondary laboratory. j Prerequisites: 1. He following are available: a) Graphite-wall ionization chamber (Far West IC-18G), t b) Two or more electrometers (Keithley 616 or 617). 2. The graphite-wall chamber as well as one of the electrometers shall have been calibrated by a Secondary Calibration Laboratory within the last two years. The electrometer for which this is done is designated here as the ' calibrated' instrument while the other is referred to as the ' field' instrument. The latter is calibrated - against the former. Each electrometer can be calibrated by itself or the electrometer and each chamber can be calibrated as an electrometer-chamber pair. 3. Low-noise signal cables, a high voltage power supply (Canberra HV Supply

1. 2816A or equivalent), high-voltage cables, a calibration jig, and a stop watch with an accuracy and resolution of 0.1 s. (Caution: The signal cables should be handled i

gently. In particular, they should not be bent to radii of less than 30 cm.) l 4. Standani radiological procedures are to be observed 5. 5 Ci Cs-137 source. 6. A thermometer and a means of monitoring barometric pressure. n j SR#-0-93-5 MAY 281993 .1

?- PM 3.14.2.5 l Page 2 of 7 l' l[C 7. The area in which the calibration is to be performed is to be secured and posted as a l 'High Radiation' area. j Procedure: The Keithley 617 is the unit sent to the secondary calibration laboratory. The Keithley 616 is the field instrument. The calibration method is to measure the same current ) with both electrometers and then to assign an electrometer calibration factor to the field instrument (K-616). The graphite-wall chamber is exposed to about a 1 R/ min field from the Cs-137 source. Charge is collected using the K-617 electrometer. The results of four measurements, each about 1 minute long, are averaged. The K-616 electrometer is then i used similarly to measure the same current. The above cunents are compared. i 1. Record the following information: Instrument Serial # Calibration Secondary Rat lah K-616 e ectrometer N/A N/A K-617 electrometer l Graphite-wall Chamber 2. Describe the signal cable: ib 3. Energize both electrometers and adjust the high voltage or the HV power supply to + 250 V. Check the HV cables to be certain that the chambers would be at 250 i 10 V. 'Ihe background currents, with the voltage applied to the chambers but with no radiation field, should be less than 1E-14 Amperes. 4. Allow both electrometers to warm up for two hours. 5. Attach the calibration jig to the Cs-137 source and plug in the Cs-source l warning lights. a 6. Monitor ambient temperature and pressure using the thermometer and the j control room barometer. Correction to the calibration will be required if variations in temperature and pressure that occur during the actual calibration affect the currents by more than 0.2%. 7. Set the K-617 electrometer to the Coulomb mode and for autoranging. j Check that the Volt / Ohm Guardis Off. i 8. Position the graphite-wall ionization chamber in the calibration jig (the position closer to the source) and connect it to the electrometer that was sent the secondary calibration laboratory. This should be the K-617. (Note: The K-617 is autoranging. A particular scale need not be specified.) t SR#-0-93-5 MAY 281993 i

PM 3.14.2.5 Page 3 of 7 9. Allow the system to stabilize for ten minutes. 10. Perform the following with the unit sent to the secondary calibration laboratory (K-617): a) Disable the zero-check. b) Collect charge for about one minute. c) Record the collected charge: Coulombs and the collection time: minutes. d) Compute the current: Coulomb / minute. e) Repeat steps (a) - (d) and reconi the collected charge: Coulombs and the collection time: minutes. f) Compute the current: Coulombs / minute. g) Average the currents obtained in Steps (d) and (f) above: Coulombs / minute. This is the background current of the K-617 unit. OV 11. Verify that the background current for the electrometer is less than i 6E-13 Coulombs / minute. If not, notify the Director of the MIT Nuclear Reactor Laboratory and the program's Cenified Medical Physicist. 12. Lift the depleted uranium shield to irradiate the chamber. (No.tt: The chamber is open to the air; no flushing gas is needed.) Four measurements should be taken and the results recorded on the attached data sheet. 13. Check the repeatability of the measurements obtained in step (12) above. If the repeatability is not within 1%, then the electrometer, chzmber, or system i as a whole (including cables)is not stable. Suspend the procedure until the j cause is identified and rectified. j 1 14. I.ower the depleted uranium shield to shut off the beam. 15. Remove the signal cable from the electrometer that was sent to the secondary calibration laboratory and attach it to the field electrometer. This should be the K-616. 16. Set the K-616 electrometer to the E-10 C range. Select the triax mode for l the cable and the fast mode for the collection time. 17. Allow the system to stabilize for ten minutes. ,i l C i SR#-0-93-5 MAY 281993 l l

PM 3.14.2.5 Page 4 of 7 f 18. Perform the following for the field unit (the K-616). i d a) Disable the zero-check. b) Collect charge for about one minute. c) Record the collected charge: Coulombs and the collection time: minutes. d) Compute the current: Coulomb / minute. e) Repeat steps (a) - (d) and reconi the collected charge: Coulombs and the collection time:

minutes, f) Compute the current:

Coulombs / minute. g) Average the currents obtained in Steps (d) and (f) above: Coulombs / minute. This is the background current of the K-616 unit on the E-10 C scale. 19. Verify that the background current for the electrometer is less than i 6E-13 Coulombs / minute. If not, notify the Director of the MIT Nuclear (] Reacter Laboratory and the program's Certified Medical Physicist. '%J 20. Lift the depleted uranium shield to uradiate the chamber. (Note: The chamber is open to the air; no flushing gas is needed.) Four measurements should be taken and the results recorded on the attached data sheet. 21. Check the repeatability of the measurements obtained in step (20) above. If the repeatability is not within 1%, then the electrometer, chamber, or system 1 as a whole (including cables) is not stable. Suspend the procedure until the causeis identified and rectified. 22. IAwer the depleted uranium shield to shut off the beam. 23. Set the K-616 electrometer to the E-09 C range. Select the triax mode for the cable and the fast mode for the collection ume. 24. Allow the system to stabilize for ten minutes. _ 25. Perform the following for the field unit: a) Disable the zero-check. b) Collect charge for about one minute. o) t SR#-0-93-5 MAY 281993 .1

PM 3.14.2.5 Page 5 of 7 c) Remr 'ae collected charge: Coulombs and s aollection time: minutes. d) Compute the current: Coulomb / minute. e) Repeat steps (a)- (d) and record the collected charge: Coulombs and the collection time: minutes. f) Compute the current: Coulombs / minute. g) Average the currents obtained in Steps (d) and (f) above: Coulombs / minute. This is the background current of the K-616 unit on the E-09 C scale. 26. Verify that the background current for the electrometer is less than i 6E-13 Coulombs / minute. If not, notify the Director of the MIT Nuclear Reactor Laboratory and the program's Certified Medical Physicist. 27. Lift the depleted uranium shield to irradiate the chamber. (Note: The chamber is open to the air; no flushing gas is needed.) Four measurements should be taken and the results recorded on the attached data sheet. f' 28. Check the repeatability of the measurements obtained in step (27) above. If the repeatability is not within 1%, then the electrometer, chamber, or system x as a whole (including cables) is not stable. Suspend the procedure until the cause is identified and rectified. 29. Lower the depleted uranium shield to shut off the beam. 30. Average the currents for each electrometer and record on the data sheet. 31. Obtain the ' electronic calibration factor' or ECF for the electrometer that was i calibrated at the secondary calibration laboratory: -I (ECF)K-617 = i l (Note: In 1993, this factor was 1.001.) m. ,f V SR#-0-93-5 MAY 281993 l l

PM 3.14.2.5 Page 6 of 7-O 32. Calculate the ECFs for the two scales of the field instrument from the relation: (ECF)K-617 (Avg. Current of K-617)- (ECF)K-616 = (Avg. Current of K-616)l (ECF)K-616 f r E-10 C scale: (ECF)K-616 or E-09 C scale: f 4 33. . Decnergize and store all equipment.- l l The acceptance criteria is that the field instrument's two Coulomb scales (E-10'and E-09) are calibrated to within i 2% of the electrometer that was sent to the secondary calibration j laboratory. ~ i O Acceptance Criteria Met: Yes O No O Calibration performed by: NCF Research Scientist Date Calibration checked by: NCF Research Scientist Date-Results reviewed by: NRL Duector Dae O SR#-0-93-5 MAY281993 _ _ _ =_ _

) l\\. -PM 3.14.2.5 Page 7 of 7 - l

• l O

n=' T 6'e rer eie<'reme'er crese-c iibr 'i - Electrometer Charge collected (C) . Collection time (min) - Averagecurrent(Chnin) i i 1. K-617 2. 3. 4. i 1. 1 K-616 2. E-10 C scale 3. i 4. i l 1. lA K-616 2. i E-09 C scale 3. I ~ 4. l 'l I 4 F Certified by: l NCF Research Scientist Dane j Data reviewed by: NCF Research Scientist Dam -j SR#-0-93-5 MAY281993 ~ 'I

l~ PM 3.14.2.7 ' Page 1 of 4 iE b i ii l] PM 3.14.2.7 Determination of Hieh Purity Ge or Ge(LiY Detector Efficiency j i i [ Pumose: This procedure provides a standard method for determining the counting efficiency of high purity Ge or Ge(Li) detectors.- 4 Accentance Criteria: The absolute efficiency at 411 kev (Au-198) is determined to' within i 2%. Prerecyicites: 1. The following are available: { a)- Diode detector. b) NIST Standard Mixed Radionuclide Source (SRM 4275C-45) or an l equivalent made as a thin deposit of small area (< 0.125" diameter)._ l c) Data sheet for the source in which photon energies and disintegration rates arelisted. (Nets: A data sheet for SNM 4275C-45 is attached.) i d) Sources for use in energy calibrating the detector. i e) Plexiglass holder that is used to position the standard source and foils at a fixed distance from the detector. i f) A gold foil (5-10 mg, -0.002" thick). The foil should have been irradiated 2 to a fluence of about 3.6 1013 neutrons /cm, j Procedure: b 1. Record detector type and serial number. Type:

Serial #

l 2. Energy. calibrate the detector using Cs-137, Co-60, Na-22 or other appropriate radionuclides such'as those corresponding to the gamma-ray i ermtters of the SRM source. If possible, the energy peaks of the nuclides 4 4 chosen should bracket the energy peaks of the nuclide(s) to be measumi.' Record the following: a) Nuclide(s) to be measured: Energy Peaks: (kev). 1 SR#-0-93-5 ' MAY 281993 j

PM 3.14.2.7 Page 2 of 4 O) ( b) Nuclide(s) for calibration: Energy Peaks: (kev). The energy calibration procedure is itselflargely automated. The user need only identify the peaks of the source nuclides. 3. Position the standard source four-six inches from the detector. This distance is selected so as to minimize summing errors. Record the distance from the face of the detector to the source:._. inches. 4. Count the standard source until the peaks that will be used to determine efficiency have a counting error of about i 1% (one standard deviation). This will require approximately one hour. For each peak, complete Part A of the attached data table and determine the count rate, which is the net area divided by the counting (live) time. As an altemative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCT Research Scientists. 5. Complete Part B of the attached data table. As an altemative, a spreadsheet may be used to perform and record these calculations. If used, these shall be signed, dated, and reviewed by two NCT Research Scientists. 6. Determine the detector efficiency at the distance recorded in step (3) above c. for the 411 kev peak by plotting the ' log of detector efficiency' versus ' log (~ of photon energy' fer several peaks between 250 and 700 kev. A straight line, least squares fit should be used and the efficiency at 411 kev determined by linear interpolation. A sample efficiency plot is attached. Sign and date the efficiency plot and append it to this procedure. Efficiency at 411 kev at inches: (%) 7. Determine the 411 kev efficiency for the gold foil placed directly on top of the detector. (Mals.: In order to ensure accuracy when other foils are subsequently counted in this position, it is necessary that each be positioned within i 2 mm of the foil used here for the calibration. Cardboard holders similar to 35 mm projector slides are available and should be used to position this and subsequent foils.) The detection efficiency at this in-close i position is determined by counting a gold foil at the 4-6" distance and then counting the same foil at the close distance. 'Ihis gives a ratio of count rates which, when multiplied by the efficiency at the 4-6" distance, gives the efficiency at the in-close distance. Foils should be counted at each position until a statistical counting error of less than i 1% is obtained. A small I correction accounting for decay of the Au-198 during the time that elapses between these measurements should be applied. It is best, however, to calculate the saturated activity per unit mass of the foil with the foil at both l l ( \\ l G i SR#-0-93-5 MAY 281993 l l l 4

PM 3.14.2.7 i L~ Page 3 of 4 l r positions. *Ihe ratio of the efficiencies is equal to the ratio of the calculated saturated activities per unit mass. In this way, the decay correction is j accounted for automatically. Reconi the following: e l a)_ Count rate with foil at 4-6 inches: (eps)i l b) Count rate with foil on top of detector. - (cps)i - c) Ratio of count rates (near/far): i 8. Compute the detector efficiency at 411 kev for the foil on top of the detector - by multiplying the count rate rate ratio from step (7(c)) above by the j efficiency determined in step (6) above. Detector efficiency at 411 kev for foil on top of the detector: 9. Deenergize and store all equipment. i l l. i l The acceptance criteria is that the absolute efficiency at 411 kev is determined to within - i 2%. O Acceptance Criteria Met: Yes - 0 No O-l I j L Calibration performedby: NCF Research Scientist Date. Calibration checked by: ' NCF Research Scientist-Dane-Results reviewed by: NRL Director Date - i O i SR#4)-93-5 MAY281993 p q

PM 3.14.2.7 Page.4 of 4 - Data Table for Calculation of Ge/Ge(LI) Detector Efficiency DetectorType: Serial No.: Date: i Part A Peak (kev) Net Area (counts) ' Live Tune (s) - Count Rate (eps) 3 l l 1. 2. 3. l 4. 5. r Part B l Peak (kev) Reference Current. Measured Efficiency i Disintegration Disintegration Count Rate (%) l Rate (dps) Rate (dos) (cos) i i O 3. 4. 5. i Notes: (1) Obtain reference disintegration rate from the data sheet supplied with the source. 1 (2) Obtain current disintegration rate by correcting the reference disintegration mte for decay from the time of the source's manufacture to the present.' Use the half-lives pmvided on the data sheet that was supplied with the source. (3) 'Ihe efficiency is a measured count rate divided by the cunent disintegration - rate, expressed as a percent. I Date Certified by: NCF Research Scientist. Dam i Data Reviewed by: i NCF Research Scientist. Dae SR#-0-93-5 MAY 281993 1

/A'O [T Diational institute of Ctanbarbs 8e Ecct;nology j I. .O~ Eertificate j j Standard Reference Material 4275C 1 Radioactivity Standard R i d l MIZED-RADIONUCLIDE POINT-SOURCE STANDARD l } for the EFFICIENCY CALIBRATION OF CERMANIUM-SPECTROMETER SYSTEMS-Antimony-125-Tellurium-125m i j Europium-154 l Europium-155 i i Source identification SRM 4275C-45 i m* l i Source. description Point source on polyester tape i l Reference time 1200 EST September 1, 1988 l of l This standard is intended for use in measuring the full-energy-peak' efficiencies i i spectrometry systems for x and gamma rays from 27 to 1596 kev, provided that the responses l l p to radiations approximately 5 kev apart can be resolved. Emission' rates are specified at j G18energiesforphotonradiationsfromamixtureofantimony-125-te11urium-125a, i europium-154, and europium-155. Uncertainties are estimated and combined at a level J corresponding to a standard deviation of the mean, with the_ intent that the user can j j propagate this uncertainty along with the other uncertainties in the spectrometer i calibration. For a more conservative overall. uncertainty corresponding to that given on j other NIST radioactivity certificates, multiply the combined uncertainty by three. j j Teble 1 gives the energies, emission rates, and uncertainties for selected radiations. A l l footnote indicates how emission rates will change with time. If there are any changes in j maasured emission rates that would correspond to an emission rate 0.5 percent different from that calculated from Table 1, or in measured half lives that would cause a l corresponding difference after five years, notification will be.sent to purchasers of the I standard. i Table 2 lists the estimates of component uncertainties which have been added in quadrature to give the combined uncertainty in each emission rate. I J Notes on the use of this standard are appended. One of the tables in the supplemental j notes gives relative emission rates for radiations close in energy to the certified ~ j rediations; for spectrometry systems of poorer resolution, it may be necessary to use'a ceabined emission rate for some multiple peaks. 1 This Standard Reference Material was prepared in the Center for Radiation Research, Ionizing Radiation Division, Radioactivity Group Dale D. Hoppes, Group Leader. ! O aithersburg, MD ] G 20899 Stanley D. Rasberry, Chief j September, 1988 Office of Standard Reference Materials ] Notes on page 4 MAY 28 1993 3' ~SR#-0-93-5 i t i 4 1 i,... ~,,-,- l

) i TABl.E 1 i O '.t X-Ray and Gamma-Ray Energies, Emission Rates (2,33, and Uncertainties for Standard Reference Material 4275C-45 i Photon Emission Rate Energy (x s-1) or ( r s'1) Total Estimated Radionuclide (kev) 1200 EST September 1, 1988~ Uncertainty (%)* L 12sSb 12Me Ka, 27.4 4.704 x 10' 1.3 e 15'Eu 158Eu Fa, 42.8 2.775 x 10' 1.3 158Eu 86.5 1.062 x 10' O.9 8 155Eu 105.3 7.396 x 10 1.3 15'Eu 123.1 4.321 x 10' O.8 8 125Sb 176.3 5.162 x 10 0.6 3 15"Eu 247.7 7.325 x 10 0.6 12sSb 427.9 2.244 x 10' O.8 tas b 463.4 7.888 x 10 0.7 l 5 s t 3 15'Eu 591.8 5.242 x 10 0.6 125Sb 600.6 1.333 x 10* 0.7 r f 12sSb 635.9 8.518 x 10 0.6 8 f 15'Eu 723.3 2.127 x 10' O.6 I 15'Eu 873.2 1.291 x 10' O.7 15'Eu 996.3 1.105 x 10' O.9 -l 15'Eu 1004.7 1.917 x 10' O.7 l 15'Eu 1274.5 3.694 x 10' O.5 l 3 -0.7 15'Eu 1596.4 1.878 x 10

• Estimated total uncertainties have the significance of one standard deviation of the mean. Components of these estimates are given in Table 2.

SRM 4275C SR#-0-93-5 MAY 28 1993

n TABLE 2 Estimates of the Component Uncertainties for Photon-Emission-Rate Values for SRM 4275C TYPICAL UNCERTAINTY COMPONENTS (%) i 7 I Photon Number of Std. Dev. Pile-up Combined Energy Determi-of the Effici-Peak Compen-Uncer-(kev) nations Mean ency Analysis sation Geometry Other* tainty'~ l l 27.4 6 0.3 10 0.7 0.3 0.1 0.3 1.3 I + 42.8 12 0.05 1.0 0.7 0.1 0.1 0.3 1.3 l 1 86.5 12 0.06 0.70 0.5 0.1 0.1 0.3 0.9 f 105.3 12 0.06 1.2 0.5 0.1 0.1 0.4 1.3 { 123.1 6 0.08 0.6 0.4 0.1 0.08 0.4 0.8 176.3 6 0.09 0.5 0.2 0.2 0.1 0.4 0.6 247.7 6 0.04 0.5 0.3 0.1 0.08 0.4 0.6 l 427.9 6 0.23 0.7 0.2 0.2 0.08 0.4 0.8 () 463.4 7 0.22 0.58 0.2 0.2 0.08 0.4 0.7 591.8 6 0.12 0.45 0.3 0.1 0.08 0.4 0.6 I l a 3 600.6 7 0.20 0.42 0.4 0.2 0.08 0.4 0.7 635.9 6 0.19 0.42 0.2 0.2 0.08 0.4 0.6 723.3 6 0.05 0.54 0.2 0.1 0.08 0.4 0.6 873.2 5 0.12 0.63 0.3 0.1 0.08 0.4 0.7 l i 996.3 5 0.11 0.54 0.75 0.1 0.08 0.4 0.9 l 1004.7 5 0.06 0.54 0.4 0.1 0.08 0.4 0.7 l 1274.5 5 0.06 0.45 0.1 0.1 0.08 0.4 0.5 1596.4 6 0.43 0.40 0.1 0.2 0.15 0.4 0.7 i

• Includes contributions for the half lives for the Te x ray, for the decay schemes for the Gd x ray, and for gravimetric factors in the source preparation.
  • Components of the uncertainty have been added in quadrature. This is the s

I uncertainty for a typical detector, and some of the values are slightly greater than those given in the last column in Table 1. SRM 4275C SR#-0-93-5 MAY 28 1993

li. e i 4 j [- 1 il* l l' l i O mm 1) . Sample consists of a dried deposit of the radionuclides between two-layers of polyester _ type 0.006-cm thick which are mounted on an~aluminwn annulus (3.8-cm inside diameter.and 5.4-cmloutside diameter)-. j 2) These values are_ based on gamma-ray' spectrometry, measurements made.at; i the National Institute of Standards and; Technology, which-are described in the reference: B.M. Coursey, D.D. Hoppes, and F.J.'Schina,. " Determination of the Photon Emission Rates'of the NBS Long-Lived Mixed-Radionuclide-Standard", Nuclear. Instruments and Methods 12),, 1 (1982). i i 3) Emission rates at later times can be calculated using the following: evaluated' half-life values and' decay constants: Malf'Lifa Decav Constant 12sSb ' 1008 i 2 days 6.876' x 10 days-1 18'Eu. 3141 i 12 days-

2. 207 x.10 days-1 188Eu 1738 i 4 days 3.986 x 10** days ~1 4)

For the 42.8-kev Gd K, x rays, the emission rate N is given by g N - N, x (0.6724 e -2.aor : 10~' ' + 0.3276 e.~88"l), g where N, is the emission rate given in Table 1, and t 'is the _ time in days from 1200 EST September 1, 1988. For further information contact Dr. F.J.. Schina '(301) 975-5537.or Dr. D.D.- Hoppes (301) 975-5532. SRM 4275C I O l SR#-0-93-5 MAY 28 1993

44 4 i* i i, 9 -5.5 J Detector #1 - I Distant. = 4.73* SRM4275C standard i a = 25 - -6.0 - i <j x .2 i u j 1 l 1 3 g -6.5 - g 1 4 i y on i 1' -7.0 - 1 y = -0.26502 + 1.0099x R= 0.99988 j 3 i -7.5 i 5.0 5.5 6.0 6.5 7.0 Logof photonenergy (energyin kev) i t } I t i e t. I This is a typical efficiency-energy plot. Detector #1 is a Ge(Li) detector. i i l 1 .j l 1 3 4 4 k a LO i SR#-0-93-5 MAY 28 1993 )

f e PM 3.14.3.1 i-Page 1 of 10 id PM 3.14.3.1 General Prermration for Use of the Medical l q Thernov Fac I tv 3eam for Human Lse !b Puroose: This procedure ensures that the administrative requirements of MITR Technical Specification No. 6.5 and the associated Quality Management Program are satisfied prior to the conduct of a human therapy.'.' Steps in this procedure that require the signature of a senior member of the operations staff shall be signed by the Director of Reactor Operations or the Superintendent for Engineering or the Superintendent for Opentions. i Identity of Administrative Orennizations and Key Personnel 1. Name of Patient:

- Fraction No.

2. Scheduled Time and Date of Human Therapy: Time Date i l 3. Name of Physician Authorized User: Registration No. State: l 4. Name of Certified Medical Physicist: ( Certification No. Organization: l7 5. Name of NRL Director (or designate):

\\

6. Number of NRC Medical Use Licensee: 7. Physician Authorized User verified to have been so designated by the Medical Use Licensee (i.e., the referring hospital) and Medical Use Licensee verified to be authorized by the U.S. Nuclear Regulatory Commission for utilization of MIT Research Reactor's Medical Therapy Facility beam for neutmn capture therapy. Senior Member of Operations Staff Date 8. Names and functions of other attending medical personnel: Name Function i i S R#-0-93-5 MAY 281993

PM 3.14.3.1 Page 2 of 10 l Verification of Trainine Reautrements l O i 1. Documentation on file that the Medical Use Licensee has verified that the Certified Medical Physicist has received specific training in neutron' dosimetry and neutron capture therapy. l I Senior Memberof Operations Staff Date. 1 2. Medical personnel who will be responsible for conducting the human therapy are. verified to have been trained properly on use of the controls for the medical therapy facility beam: - Date ofInitial Training Name or Proficiency Check (l) l i lO

0) Mots: Date listed must be within one year of the scheduled therapy.

l I l Senior Member of Operations Staff Date i 1 3. Instructions mquired under provision 16(b) of MITR Technical Specification No. ' 6.5 verified to be posted at the medical therapy facility's local control panel. Verified by: Senior ReactorOperator Dale O SR#-0-93-5 MAY 281993

f PM 3.14.3.1 l Page 3 of 10 Status of Medical Thernov Facility 1. The following interlocks or channels shall be verified to have been tested within one month prior to the scheduled human therapy: l Interlock or Channel Surveillance Date Document (2) l a) MedicalTherapy facility Scram test minor scram (D l b) Shutters will not open Operational test unless shield dooris closed c) Shutters close upon both Operational test manualand automatic opening of shield door d) Shutters close on loss of Operational test electrical power and reduction of pressure in l pneumatic operators,if applicable e) Manualclosure of Operational test pneumatic shutters () f) Shutters can be closed Operational test [ from within the facility g) Shutter status lights Operational test h) Radiation monitor alarm Operational test i) Radiation monitor and/or Operational test alarm enabled upon opening of shield door j) Intercoms Operational test Notes: (1) In addition to the above requirements, the medical therapy facility minor scram shall be tested prior to reactor startup if the reactor had been shut down for more than sixteen hours. (2) Under the ' document' column indicate where the performance of the test was recorded (i.e., preoperational test, startup checklist, test and calibration procedure, etc.) (. () SR#-0-93-5 MAY 281993

PM 3.14.3.1 Page 4 of 10 2. If any of the requirements listed in step (1) above are being satisfied through a 7m temporary provision, list that provision below together with the authorizing section i of MITR Technical Specification No. 6.5. tRJ 3. The medical therapy facility's radiation monitor shall be checked as follows: a) Satisfactory performance of source-check on calendar day of and prior to the human therapy per PM 3.14.1.3 Date Tune b) Date of most recent calibration: (N_qtr Required frequency is quanerly.) c) Audible alarm set at or below 50 mR/hr: mR/hr d) Verification that any ponable instruments and/or audible-alarm personnel dosimeters that are to be used in the event of a malfunction of the radiation ,sQ monitor are calibrated. Instrument # Calibration Date 1 e) Source-check any instruments listed in step (3(d)) above. Source-check (s) satisfactory: l Senior Reactor Operator Date 4. Both closed-circuit TV camera that is used for patient viewing and viewing port I operable: l 7, Senior Reactor Operator Date I f 1 SR#-0-93-5 MAY 281993

PM' 3.14.3.1 Page 5 of 10 l 5. Medical facility emergency lighting verified operable within the past three months: Date Tested Document File No. 6. Medical therapy facility door operated manually within the past six months: l Date Tested Document File No. l 7. Reactor floor elevator operable (if required): l Senior Reactor Operator Date 1 Status of Medical Therany Facility Beam j l 1. Secondary Calibration Laboratory performed calibration of the instruments (dual 3 ion chambers) that are used in accordance with Definition No.' 5 of MITR Technical i Specification No. 6.5 to calibrate the beam monitors. This was done within the past two years: i a) Date of calibration: I b) Name oflaboratory: c) Calibration cenificate(s) in Q/A file No.- l ( 2. Functional check of beam monitors completed per PM 3.14.2.1, " Functional Check i of the Medical Therapy Facility Beam Monitors," within the past week: J Date of Functional Check Document File No. 3. Calibration check of beam completed per PM 3.14.2.2, " Calibration Check of 1 L Medical Therapy Facility Beam," within the past week: l t Date of Calibration Check Document File No. l 4. Beam monitors verified operable per PM 3.14.2.3, " Beam Monitor Plateau and - 1 Discriminator Setpoint Tests," within the past six months:- Date of Calibration ~ Document File No. h j SR#-0-93-5 MAY 281993 1 ~

PM 3.14.3.1 s Page 6 of 10 5. Beam characterization completed per PM 3.14.2.4, " Characterization of the Medical Therapy Facility Beam," within the past six months: _ ~') (V Date of Characterization Document File No. 6. In the event that a component of a given beam design is replaced, a calibration check shall be performed. In the event of a design modification, both a calibration ] check and~a functional check shall be performed.- 'Also, a characterization is - l required. Therefore, one of the following should be verified: j a) There have been no component replacements and/or design modifications since the last use of the medical therapy beam on

or.

l l b) The required characterization, functional, and calibration checks have been performed pursuant to a component replacement and/or design modification. l l Attach separate docun)entation to show compliance with MITR Technical l l Specification No. 6.5. Senior Member of Operations Staff . Date Written Directive and Plan of Treatment l. 1. Attach copy of the written directive prepared by the Physician Authorized User of the NRC-approved Medical Use Licensee to this procedure. 2. Record the following information from the written directive: a) Name of Physician Authorized User: i b) License Number of NRL Medical Use Licensee: c) Name and other means ofidentifying patient: i) Name: j ii) Address: iii) Date of Birth: l iv) ~ SSN: l 3 v) Hospital Wristband Identification No.: vi) Photograph: (1o le attached).- d) Name of Certified Medical Physicist-SR#-0-93-5 MAY 281993 i I i V

I PM 3.14.3.1 Page 7 of 10 e) Treatment Information: i) Total maximum radiation dose to normal tissue-RBE-cGy on the central axis of the beam at: cm. ii) Number of fractions to deliver total dose: iii) Maximum radiation dose to normal tissue per fraction: RBE-cGy on the central axis of the beam at: cm. i iv) Treatment Site: l v) OverallTreatment Period: l vi) Time (s) of B-10 administration (s): Time

D ale

.j Tune . Date vii) Amount of BPA administered: / mg/kg-viii) Results of previous boron uptake test: 3 (1) B-10 in tumor: ppm @ - hours after administration (2) B-10 in blood: ppm @ hours after l l administration l l (3) B-10 tumor to blood ratio: B-10/H @ hours after administration - NEc: A tumor-to-blood ratio of at least 3:1 is desired. ix) Dose rate calculations: 1 L 1) Dose rate calculated for head phantom using 7.5 ppm boron m normal tissue: RBE-cGy/ minute at cm. 2) Dose rate calculated for phantom of body part to be treated using boron concentration measured during the boron uptake test: RBE-cGy/ minute at cm for ppm boron after hours. Note:. Attach documentation sup prting the above calculations such as a copy of the dose-depq profile determined for the actual - L - boron concentration or an mterpolation from a set of pre-calculated dose-depth profiles, t O SR#-0-93 MAY281993 .l

PM 3.14.3.1 ' Page 8 of 10 ' t x) List any special precautions that are specified in the wrinen directive: 3. Compare information from step (2) above with that in the section of this pmcedure entitled, " Identity of Administrative Organization and Key Personnel." Repon any differences to the Medical Use Licensee: 4 Senior Member of Operations Staff Date 4. Verify that the written directive has been written, signed, and dated by the Physician Authorized User: i Senior Member of Operations Staff Date 5. Attach copy of plan of treatment prepared by the Certified Medical Physicist of the Medical Use Licensee to this procedure. (N_qtg: If the plan is lengthy, attach cover sheet and signatum page and file plan with Q/A files.) 6. Verify that the plan of treatment has been signed by the Certified Medical Physicist and that it is for the patient identified in the written directive: Senior Member of Operations Staff Date I Final Prenarations 'l 1. Reactor Radiation Protection Officer and MIT Radiation Protection Officer notified of the planned therapy. 2. Prompt-gamma facility available. -) 3. Irradiation Information Form (Part II) prepared and signed by both MITR Operations and Radiation Protection. 4. Alpha-cradle made and available at the medical therapy facility if so required by the medical uselicensee. (Egic: The alpha-cradle is the responsibility of the medical use licensee. Its purpose is to position the body part that is to -. be irradiated so that it is at the proper angle to the beam.) SR#-0-93-5 MAY 281993

4 PM 3.14.3.1 Page 9 of 10 5. Install the medical therapy facility's TV camera and verify that it is operational. 6. Determine the allowed difference between the measured and prescribed fluence in accordance with provision 11 of MITR Technical Specification No. 6.5. This figure is normally 20% unless the treatment consists of three or fewer fractions in which case it is 10%. However, other exceptions may apply. Allowed difference: 7. Patient No.: (assigned by NRL). 8. Vials for biopsy and blood samples available together with labels and polyethylene bags. Inscribe the vials with a number unique to the patient. For example, use the following for the first patient: 1-1,1-2,1-3, and 1-4. 9. Sterile biopsy kit available. 10. Gurney available. I 1. Inclinometer for measuring angle of alpha-cradle available. 12. Stick-mirror for use in patient-positioning available. 13. Interior and exterior winches available for manual operation of medical therapy facility shield door. 14. Two high-intensity flashlights available. If possible, cycle the D 0, H 0, lead, and boral shutters with the reactor at 15. 2 2 the power level that is to be used during the scheduled therapy. Record the following: a) Reactor neutronic power: MW b) Ch. 9 reading with shutters closed: a c) Ch. 7 reading with shutters closed: a d) Ch. 9 reading with shutters open: pa c) Ch. 7 reading was shutter open: a f) Fractional change in channel #7 upon opening shutters SR#-0-93-5 MAY 281993

PM 3.14.3.1 Page 10 of 10 16. List any special precautions: n 17. MIT Research Reactor scheduled for operation in accordance with the plan of treatment. Checklist completed by: l Senior Member of Operations Staff Date j (~~' Checkhst reviewed by: (. NRL Director Date l Checklist audited by: MIT Radiation Protection Officer Date l l i C') v SR#-0-93-5 MAY 281993 l-l

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l PM 3.14.3.2 Page 1 of 2 1 PM 3.14.3.2 Use of Promot-Gamma Facility for Boron Assay OO Puroose: This procedure provides a standard method for the determination of boron-10 concentration in blood or tissue samples. i Acceptance Criteria. Boron concentration is accurately determined. Prerequisites: i 1. Reactor operating at a power level of at least 3 MW. 2. Prompt-gamma facility operable. 3. Calibrated high purity Ge or Ge(Li) detector available. 4. Standard radiological procedures for use of an MITR beam pon are observed. t 5. Personnel who are to use the prompt-gamma facility are qualified to do so pursuant to PM 1.10.13, " Operator Qualification Sheet for Radial Beam Port Use." 6. Calibration curve of B-10/H ratio versus B-10 concentration or other calibration information available. i Procedure: 1. Verify that the high purity Ge or Ge(Li) detector has been calibrated within the last six months pursuant to PM 3.14.2.7, " Determination of High Purity Ge or Ge(Li) Detector Efficiency." Record data: + 2. Place the blood or tissue sample in the beam line of the prompt-gamma facility. Record the sample label: 1 3. Admit the neutron beam from pon 4DH3 to the pmmpt-gamma facility, a) Record time and date: Time Date j b) Record reactor powerlevel: Ch.7 pa ; Ch. 9 pa; Nominal Power MW 4. Irradiate the sample for approximately five-fifteen minutes while collecting. prompt gammas m a high purity Ge or Ge(Li) detector and associated multi-channel analyzer. j O SR#-0-93-5 MAY 281993

l L. l l PM 3.14.3.2 i Page 2 of 2 I l 5. Stop the data collection. Record the time and date: O Time - Date 6. Record the areas (corrected.for background) under the 478 kev peak (boron-10) and the 2.2 MeV. peak (hydrogen). (M21g: The correction for i background is a linear subtraction done automatically by the detection l system.) l 478 kev'- 2.2 MeV-i Net Counts 7. Compute the ratio of boron-10 to hydrogen: B-10/H. 8. Determine the boron-10 con.entration in the sample' from the calibration. curve of-B-10/H ratio versus B-10 concentration. Append copy of - calibration cuwe to this procedure. Boron concentration: ppm j 9.- _ If necessary to obtain better accuracy in the boron ' determination resu'me data collection, accumulate more counts in the multi-channel analyzer, and repeat steps (5) - (8). 10. Terminate theirradiation. AcceptanceCriteria met: Yes O No O i i Assay performed by: NCF Research Scientist Date - Assay reviewed by: NCF Research Scientist Date-Results checked by: NRL Director Date O - SR#-0-93-5 MAY 281993 i ~.

PM 3.14.3.3 Page 1 of 26 4 PM 3.14.3.3 Conduct of Human Therany Usine the Medical ,,(Jl Therany Facility Beam Pumose: This procedure outlines the protocol that is to be followed for the conduct of human therapies at the MIT Research Reactor. Acceptance Criteria: The therapy is conducted in accordance with the plan of treatment prepared by the physician authorized user and reviewed by a certified medical physicist.

Background:

l Pursuant to MITR Technical Specification No. 6.5, all medical treatments, l including irradiations and analyses of the neutron capture agents in the patients, are the l responsibility of the physician authorized user in charge of the therapy and the medical l physicists from the NRC-licensed medical center. The Massachusetts Institute of Technology it only responsible for providing current and accurate beam characteristic parameters to the medical use licensee and for delivery of the desired radiation dose as i requested in the written directive. Before the start of a therapy, both a certified medical physicist and the Director of the Nuclear Reactor Laboratory, or his designate, must agree that the therapy can be initiated. The physician authorized user is responsible for monitoring the therapy and for directing its termination. However, a radiation therapy can !(] also be terminated at any time if either the physician authorized user or the NRL Director, (/ or their designates, judge that the therapy should be tenninated. t The Medical Use Licensee (e.g., the hospital) is responsible for transport of the patient both to and from the MIT Research Reactor. A member of the hospital staff (boan!- certified radiation oncologist, medical physicist, or a therapist) will accompany the patient to the reactor facility. l Patient Preonration: 1. PM 3.14.3.1, " General Preparations for Use of the Medical Therapy Facility Beam for Human Use," complete. 2. Escort the patient and accompanying medical personnel to the medical l therapy facility room. 3. Adjust reactor power to facilitate the assay of boron in blood using the prompt-gamma facility. A power level of at least 3 MW is preferred. t l Reactor powerlevel: MW. 4. MITR Staff obtain hand-delivered copy of the written directive from the medical personnel who accompanied the patient. Stamp this hand-delivered lq copy to show date and time and append a copy to this procedure. O l SR#-0-93-5 MAY 281993 l I

~ l PM 3.14.3.3 l Page 2 of 26 l l l l l _ 5. Check the hand-delivered written directive against the copy previously ' [s) received (copy appended to PM 3.14.3.1) and verify that no discrepancies \\> exist. (&ls: If a discrepancy is found, it shall be resolved by the physician authorized user prior to the initiation of patient irradiation.) Written directive is verified correct: NRL Director Date l Certified Medical Physicist Date 6. Record the following information from the written directive: j a) Name of Physician Authorized User: b) License Number of NRC Medical Use Licensee: c) Name and other means ofidentifying patient: i) Name: l ii) Address: i ltO iii) Date of Birth: ' L] l iv) SSN: v) Hospital Wristband Identification No.: vi) Photograph: (To be attached). d) Name of Certified Medical Physicist: e) TreatmentInformation: i) Total maximum radiation dose to normal tissue: RBE-cGy on the central axis of the beam at: cm. ii) Number of fractions to deliver total dose: iii) Maximum radiation dose to normal tissue per fraction: RBE-cGy on the central axis of the beam at: cm. iv) Treatment Site: i v) OverallTreatment Period: (.(.) S R#-0-93-5 MAY 281993

PM 3.14.3.3 Page 3 of 26 i 1 vi) Time (s) of B-10 administration (s): l-Tune. Date. l Tune Date~ vii) Amount of BPA administered: / mg/kg viii) Results of previous boron uptake test: (1) B-10in tumor: ppm @ - hours after administration l (2) B-10in blood: ppm @. hours after administration i (3) B-10 tumor to blood ratio: B-10/H @ hours 3 after administration Eglg: A tumor-to-blood ratio of at least 3:1 is desired. l ix) Dose rate calculations: 1) Dose rate calculated for head phantom vsing 7.5 ppm boron l in normal tissue: RBE-cGy/ minute at cm.. 2) Dose rate calculated for phantom of body part to be treated using boron concentration measured during the boron uptake. l test: RBE-cGy/ minute at cm for ppm boron after hotus. x) List any special precautions that are specified in the written directive: l 7. Verify the patient's identity as the individual named in the written directive. [ Any Igo of the following methods shall be used: l a) Self-identification in which any two of the following are obtained from the patient: i) Name: ii) Address: l iii) Date of Birth: iv) SSN: L l-SR#-0-93-5 MAY 281993 I l

PM 3.14.3.3 Page 4 of 26 - The social security number is to be compared to the corresponding - O information in the patient's record and all the above information is to be verified against that which is listed in the written directive. b) Hospital wristband identification with the wristband information - compared to the corresponding information in the patient's record. Wristband Identificadon No.: c) Visual identificadon against photographs provided with the written directive. Photograph provided: Patient identified as the individual named in the written directive. -The methods used for identification were: R h tm h Certified MedicalPhysicist Dale 8. Assist patient onto the gumey. 9. Medical personnel draw about a 3 m1 sample of venous blood into a haparinized vacuutainer. Transfer about 1 ml to a pre-inscribed Teflon vial. Analyze the 1 ml sample for boron-10 concentration using prompt-gamma, neutron-activation analysis. (Refer to PM 3.14.3.2) Label the vials and record thelabeldata: Patient name: Date:

Time

Samplelocation:

Sample size

Praction numberof treatment: Inscribed number on 1 ml vial: Inscribed numberon vacuutainer: Nameof person drawing sample: V('s SR#-0-93-5 MAY 281993 I'.

PM 3.14.3.3 Page 5 of 26 10. Request that medical personnel biopsy the tumor by the punch technique .h -[d (vide supra) to obtain about a 50 mg sample. Place the sample in a pre-inscribed Teflon vial. Another punch biopsy may be taken for prompt-gamma analysis. 11. If desired, freeze the sample in a mixture of acetone and dry ice for later analysis by alpha-track autoradiography. 12. Label the sample (s). Record label data: Patient name: Date:

Time

Sample location: Sample (i.e., punch) size: Fraction number of treatment: Inscribed number on vial: (1st sample) Inscribed number on vial: (2nd sample) Name of person performing biopsy: 13. Review the results of the prompt-gamma analysis. A 3:1 tumor <o-blood (q) ratio is desired. The achievement of this ratio for a given patierr. is vedfied through a previous test conducted at the hospital. The objective here is to verify that the blood concentration attained in that test has been r: plicated.) Boron-10 concentration in blood is: ppm. Thisis acceptable: Certified MedicalPhysicist Tune Date Physician Authorized User Tune Date 14. I.ower reactor power to 50 kW or less. 15. If specified in the written directive, attach vital-sign medical monitodng eqmpment to the patient. 16. Use mylar tape to affix gold foils (5-10 mg, ~0.002" thick) to the patient in the vicinity of the treatment site. (Note: This should be done by medical personnel under the Certified Medical Physicist's direction and only when requested by that individual. It is not envisioned that these foils will be used routinely.) (,\\ %,) SR#-0-93-5 MAY281993

' PM 3.14.3.3 Page 6 of 26 j i 17. NRL Director calculate the required ' epithermal beam monitor integrated x") counts' and ' megawatt-minutes' to achieve the radiation dose to healthy tissue specified in the written directive. Record the following i a) Radiation dose from all beam RBE-cGy for l components to healthy tissue healthy tissue at a depth of as specified in the written cm on the beam's directive for this fraction. central axis. ] b) Radiation dose rate at 5 MWt RBE-cGy/ minute from all beam components to at 5 MWt for healthy tissue at a - i healthy tissue at I cm with 7.5 depth of I cm on the beam's ppm boron as determined by central axis with 7.5 ppm bomn beam characterization mea-presentin healthy tissue. surement. c) Boron concentration in healthy ppm boron in tissue as recorded in step (13) healthy tissue at: of this procedure. l on Time Date O. d) Radiation dose rate at 5 MWt - RBE-cGy/ minute from all beam components to at 5 MWt for healthy tissue at a healthy tissue adjusted for the _ depth of cm on the i boron concentration recorded beam's central axis with in step (13) of this procedure. ppm bomn present in healthy tissue. Hols: Attach documentation supporting the above dose rate such as a dose-depth profile determined for the actual boron concen-tration or an interpolation from a set of pre-calculated dose-depth profiles. e) Minutes of irradiation at 5 - minutes at 5 MWt. MWt to achieve dose specified - in the written directive for this i fraction. 1 [ Sequence: a+d] l f) Megawatt-minutes to achieve MW-minutes dose specified in written directive for this fraction. l [ Sequence: e x 5] l O SR#-0-93 MAY 281993 l l l L l

PM 3.14.3.3 Page 7 of 26 g) Calibration factor from dose 7.~h (d rate to healthy tissue at a depth of I cm with 7.5 ppm boron to epithermal beam monitor count rate as given in PM 3.14.2.4, " Characterization of the Medical Facility Beam." (cps)ep;,3 (i) EpithennalDetector#1 RBE-cGy/ minute (cps) epi,2 (ii) EpithennalDetector#2 RBE-cGy/ minute h) Calibration factor corrected to (ens) cpi l the actual depth of cm and actualbomn concentration RBE-cGy/ minute of ppm as recorded in step (13). (eps)5,2 Sequence: [g x b + d] RBE-cGy/ minute i) Integrated epithermal beam monitor counts to achieve dose specified in the written directive for this fmetion. Sequence: [h x a x 60] \\ (i) EpithermalDetector #1 Counts (ii) EpithermalDetector#2 Counts Calculation performed by: NRL Duector Tune Date l l ,r \\ N. Y SR#-0-93-5 MAY 281993 l i

o PM 3.14.3.3 l Page 8 of 26 i i 18. Cerdfied Medical Physicist calculate the required ' epithermal beam monitor / n integrated counts' and ' megawatt-minutes' to achieve the radiation dose to V healthy tissue specified in the written directive. Record the following: ) i i a) Radiation dose from all beam RBE-cGy for components to healthy tissue healthy tissue at a depth of as specified in the written cm on the beam's directive for this fraction. central axis. b) Radiation dose rate at 5 MWt RBE-cGyhninute from all beam components to at 5 MWt for healthy tissue at a healthy tissue at I cm with 7.5 depth of I cm on the beam's ppm boron as determined by central axis with 7.5 ppm boron beam characterization mea-presentin healthy tissue. surement. c) Boron concentration in healthy ppm boron in tissue as recorded in step (13) healthy tissue at : of thisprocedure. on Time Date d) Radiation dose rate at 5 MWt RBE-cGy/ minute ,r~) from all beam components to at 5 MWt for healthy tissue at a ( healthy tissue adjusted for the depth of cm on the boron concentration recorded beam's central axis with in step (13) of this procedure. ppm bomn present in healthy tissue. No.te: Attach documentation supporting the above dose rate such as a dose-depth profile determined for the actual boron concen-tration or an mterpolation from a set of pre-calculated dose-depth profiles. e) Minutes of irradiation at 5 minutes at 5 MWt. MWt to achieve dose specified in the written directive for this fraction. [ Sequence: a+d] f) Megawatt-minutes to achieve MW-minutes dose specified in written directive for this fraction. [ Sequence: e x 5] gQ,) SR#-0-93-5 MAY 281993

\\ PM 3.14.3.3 ' Page 9 of 26 I g) Calibration factor from dose rate to healthy tissue at a depth - \\ of I cm with 7.5 ppm boron to. epithermal beam monitor count rate as given in PM-i 3.14.2.4, " Characterization of the Medical Facility Beam." - (cps) ep;,3 { (i) EpithennalDetector #1 RBE-cGy/ minute (cps) epi,2 (ii) EpithermalDetector#2 RBE-cGy/ minute h) Calibration factor corrected to (eps)*Di 1 ' the actual depth of cm-and actual boron concentration RBE-cGy/ minute of ppm as recorded l i in step (13). (cps) epi,2 Sequence: [g x b + d). RBE-cGy/ minute i i) Integrated epithermal beam monitor counts to achieve dose specified in the written directive for this fraction. Sequence: [h x a x 60]' O (i). EpithermalDetector#1 Counts (ii) EpithermalDetector #2 Counts L k Calculation performed by: Certified MedicalPhysicist Tune-Date f I i O SR#-0-93-5 MAY 281993 i I )

1 PM 3.14.3.3 Page 10 of 26 19. Compare the megawatt-minutes and epithermal beam monitor integrated m i counts calculated in steps 17 and 18. Any discrepancy must be resolved l ('~d before proceeding. (CAUTION: Be certain that the calculation is for the l dose per fraction and not the dose for the entire treatment.) l l 20. Senior Member of Operations compute duration of irradiation on j assumption that reactor power is held constant. Reconi the following: l l a) Megawatt-minutes for this MW-minutes fraction i l b) Scheduled reactor neutronic MW(neutronic) power c) Length ofirradiation: minutes d) Ch. 9 reading with shutters pa closed: e) Fractional change in Ch. 9 upon opening all shutters f) Ch. 9 reading with shutters pa open: h g) Ch. 7 reading with shutters pa closed: h) Fractional change in Ch. 7 upon opening all shutters i) Ch. 7 reading with shutters. pa open: 21. Verify that the shutters that control beam delivery and the D O shutter are 2 closed. 22. Request that medical personnel verify that the treatment site is properly marked on the patient. 23. Boot-up the beam monitor data acquisition program's computer system. 24. Use PM 3.14.3.4, " Beam Monitor System Setpoints," to verify settings of all beam monitor system parameters (gains, discriminator setpoints, etc.). v SR#-0-93-5 MAY 281993

~ i l PM 3.14.3.3 l Page 11 of 26 l Patient Positionine - I 1. Open the medical therapy facility's shield door. 2. Request that Reactor Radiation Pmtection personnel survey the room. l 3. Verify operability of interior and exterior battery-operated lights. ( 4. Verify that the platform and operating couch am set up as shown in Figure One. The couch's safety rail that is nearest to the shield door should be removed. The outer rail may also be removed at the physician's discretion. 5. Verify that the plumb-bob is attached to the underside of the lead shutter. 6. Position the couch so that once the patient is on it, the treatment site will be - under the beam center. 7. lock the couch so thatit can not roll. 8. Transfer the patient to the couch. (Hols: Thereis a long wooden stairs with two steps available so that the patient can be readily assisted. 'Ihis is shown in Figure Two.) This and all subsequent steps that concern positioning of the patient are to be done under the direction of the physician authorized user. 9. If specified in the written directive, set up the vital-sign medical monitoring - equipment. l (q 10. Position the alpha-cradle, if used. Record angle specified in plan of l treatment: 11. Verify that the height of the alpha-cradle does not exceed that of the body 3 part to be treated. 12. Use the couch controls to adjust the patient's head, body, and feet for ^ comfon. l 13. Secure the patient with the safety belts. The patient's arms should be under the straps to preclude any contact with shutter mechanical components. Belt l buckles should be on the side of the couch nearest the therapy room door. l This limits activation of the buckles and facilitates access for patient removal. 14. Reverify that the patient is comfortable. 15. Once the patient has been secured, remove the remaining safety rail (if it was used) and move the stairs out of the way of those who will position the panent. 16. Position the couch so that the body pan to be treated is appmximately under i the beam's geometric center. This may require first unlocking, then l moving, and then locking the couch. l: SR#-0-93-5 j MAY281993

PM 3.14.3.3 i Page 12 of 26 1 17. Close the platform's hydraulic valve. 18. Raise the platform 20 cm and lock the platform legs with pins as shown in Figure Three. Use the foot-peddle for major adjustments and the hand-wheel for fine ones. (Natt: Inform the patient to expect one or more jolts.) 19. Once the platform legs have been locked in position, verify that all personnel are clear of the platform legs. Then, lower the platform gently by cracking open the hydraulic valve. 20. Once the platform is fully supported by the legs, open the platform hydraulic valve fully so that the patient can not be inadvertently raised funher. 21. Use the plumb-bob to position the patient in the treatment area of the beam. 22. Cover the patient with the lithium-6 blankets if so specified in the plan of treatment. 23. Raise the plumb-bob so that it is ~30 cm below the deUmiter. Use the hydraulic system of the operating couch to raise the patient to this height and position the treatment area again. Adjust the position of the gold foils if necessary. 24. Close the operating couch's hydraulic valve. O __ _. 2 5. Request that the physician authorized user direct positioning of the patient. (-) One person should be assigned to operate the couch's hydraulic system and other controls and this person should only take directions from the physician authorized user. The positioning process may have to be done iteratively with the plumb-bob to heights of 20 cm and then 10 cm below the delimiter. At each height, the body-part to be treated should be positioned directly below the plumb-bob, the angle of the alpha-cradle should be checked, and the position of the gold foils should be checked. 26. Upon completion of step (21), the patient should be about 10 cm below the delimiter. 27. Unscrew the plumb-bob and store it. 28. Use the hydraulic system of the operating couch to raise the patient until the body part that is to be treated barely touches the bottom of the delimiter (refer to Figure Five). If desired, mark the position of the alpha-cradle on the bottom of the delimiter. Recorti the following: Angle of alpha cradle: Tilt of Couch: Inclination of couch: 29. Angle of alpha-cradle verified correct: 1 /7 Certified MedicalPhysicist Date U SR#-0-93-5 MAY 281993

PM - 3.14.3.3 Page l3 of 26 30. Patient positioned as modeled in Monte-Carlo simulation: Cenified MedicalPhysicist Date j 31. Position the TV camera to view the patient. [ 32. Activate background music,if desired. (Nole: Music should not interfere l with communications via the intercom. Lighting must be sufficient for-continuous viewing of the patient via TV, minors, and direct sight.) 33. Verify that any conscious patient is audible over the medical therapy facility' mtercom. l 34. Physician authorized user verifies that patient is properly prepared for i therapy. Physician Authorized User Tune Date F 35. Clear the medical therapy facility of au personnel except the patient. Also - remove any unneeded equipment. 36. . Either the Reactor Radiation Protection Officer or the Director of Reactor erations, or their respective designates, verify. that the medical therapy lity is clear of all personnel except the patient. Reactor Radiation Pmtection Officer Tune Date Director of Reactor Operations Tune ~ Date 37. Close the medical therapy room's inner door, masonite door, and shield door. 'ntis action deactivates the medical room radiation monitor's alarm i function. Upon opening the door the function is automatically restored. 38. Observe via either the closed-circuit TV or the viewin5 window that the ' medical therapy room is clear of all personnel except the patient. O l SR#-0-93-5 MAY 281993

PM 3.14.3.3 ' Page 14 of 26 Patient Irradiation: O 1. Reverify the epithermal beam monitor integrated counts. In particular, be - certain that the calculated quantities are for the fraction of the fluence that is to be delivered and not the fluence for the entire treatment. l Epithermal beam monitorintegrated counts: counts 2. Initiate beam monitor data acquisition program. p 3. Request that the reactor operator set up the trip on the medical room area 4 radiation monitor. l 4. Raise the reactor power to the level scheduled for the treatment. Record the following: a) Scheduled power level per plan of treatment: MW b) Actual powerlevel: MW . c) Ch.7 a Ch.9 pa. i e) Time at which power attained: Date: i 5. Reactor power verified to be at steady-state. 6. Reshim so that regulating rod is in the range 3.5 to 6.0 inches. l 7. Reactor on analog automatic control. 8. Both the Certified Medical Physicist and the NRL Director (or his designate) agree that the therapy can be initiated: f Certified MedicalPhysicist Tune Date NRL Duector Tune Date 9. Commence the treatment using the following sequence for opening of the D O shutter and t1 shutters that control beam delivery: 2 a) Record time and date: Tune Date b) Record reactor powerlevel: Ch. 7 pa ; Ch. 9 pa; Nominal Power MW SR#-0-93-5 MAY 281993

PM 3.14.3.3 Page 15 of 26 l Open the D O shutter. (This usually requires three minutes.)

fm c) 2 l()

d) Depress the open button for the H O shutter and observe that it is 2 draining. Wait forty seconds and then open the lead and boral shutters. The ' treatment start time' is the moment when the lead shutterindicates open. e) Record treatment start time: Tune Date f) Record readings of reactor power indicators once all shutters are l open. l Ch.7 a ; Ch. 9 a 10. Instruct the control room personnel to monitor the irradiation time. I1. Instruct the Certified Medical Physicist to monitor the integrated beam monitor counts. 12. Continue the treatment v the discretion of the physician authorized user until the integrated beam moni:cr count for the irradiation is attained. Close the H 0, lead, and boral shutters simultaneously at that time. Record i 2 ' treatment end time:' ime Date ~ p 13. If the H O shutter does not start to close, notify the control room operator 2 () to lower reactor power to 50 kW or less via the 'all rods in' button. 14. If either the lead or boral shutters fail to close, attempt to close them manually. If they still can not be closed, notify the control room operator to lower reactor power to 50 kW or less via the 'all rods in' button. 15. Once the H O shutter is completely closed, close the D O shutter. 2 2 16. If desired, lower reactor power to 50 kW or less. Monitor power on Channel No. 9. _. _ 17. Personnel who will be entering the medical therapy facility to assist the patient should don gloves, ,c 4 %) SR#-0-93-5 MAY 281993 l

PM 3.14.3.3 ' Page 16 of 26 1 i Removal of Patient O-(/ 1. Verify both visually (water level gauges and position of manual pulleys) and by the indicator lights that the shutters are closed. 2. Open the medical therapy shield door once radiation levels in the room drop - i below 50 mR/hr. (CAUTION: Opening the door when radiation levels are above this level will sound an alarm inside the medical therapy room.) - j 3. Reactor radiation protection personnel enter the room and survey. ) 4. Medical personnel enter the room. - 5. Lower the couch by opening the fast-operating hydraulic valve (see Figure - Six). ~! _. __ 6. Close the hydraulic valve that controls movement of the platform. l l 7. Raise,the platform 1 cm and remove the locking pins of the lower leg l extensions. 8. Verify all personnel clear of the platform. 9. Crack open the platform's hydraulic valve and lower the platform so that the legs reach the floor.

10. '

Open the platform's hydraulic valve fully. k 11. Remove the vital-sign monitoring equipment ifit was used. 12. Attach the plumb-bob and use it to check the positioning of the treatment site under the beam. Record any change since treatment initiation: mm.. 13. Unlock the operating couch and slide it so that the patient will be able to step onto the platform upon being assisted off the couch.: 14. Disengage the safety belts. 15. Remove the gold foils from the patient, survey, store, and label with patient's name as well as date and time of removal. 16. Assist the patient from the operating couch and escort him or her fmm the medical therapy room to the gumey. (Refer to Figure Eight) l 17. Adjust reactor power to facilitate the assay of boron in blood using the prompt-gamma facility. A power level of at least 3 MW is preferred. Reactor powerlevel: MW. L SR#-0-93-5 MAY 281993

PM 3.14.3.3 Page 17 of 26 - 18. Medical personnel draw about a 3 mi sample of venous blood into a {c') haparinized vacuutainer. Transfer about 1 ml to a pre-inscribed Teflon vial. 'u Analyze the 1 ml sample for boron-10 concentration using prompt-gamma, neutron-activation analysis. (Refer to PM 3.14.3.2) Label the vials and record the labeldata: Patient name: Date:

Time

Sample location: Sample size: Fraction number of treatment: Inscribed number on 1 mi vial: Inscribed number on vacuutainer: Name of person drawing sample: 19. Boron-10 concentration in blood is: ppm. 20. Request that Reactor Radiation Protection personnel survey the patient. 21. Request that medical personnel escon the patient back to the hospital. n ( ) 22. Verify that all data has been recorded on a pennanent reconi that is labeled \\> for the patient. Record the following: Channel Counts 1. Hermal#1 2. Ecrmal#2 3. Epithermal #1 4. Epithermal #2 5. Gamma 23. Secure the beam monitor data acquisition system and the beam monitoring system's electronics. 24. Request that the reactor operator reset the trip on the medical room area radiation monitor. 25. If this is the last therapy for the patient, remove the mark on the delimiter denoting the position of the alpha-cradle on the delimiter so as not to cause confusion with future therapies. O N.,) 1 S R#-0-93-5 MAY 281993 i

_~ l PM 3.14.3.3 Page 18 of 26 - 1 s 2 6.' Remove and store the TV camera. i 27. Store thelithium blankets. 28. The Director of the MIT Nuclear Reactor Laboratory, or his designate, and the Certified Medical Physicist shall date and sign a copy of the written-directive to verify that current and accurate beam characteristic parameters were provided to the NRC-approved medical use licensee and that the-1 radiation fluence desired in the written directive was delivered. J 29. Provide a copy of this signed directive to the medical u' se licensee within twenty-four hours. A i i I I i l l-Checklist completed by: Senior Member of Operations Staff _ Date Checklist reviewed by: NRL Director Date' Checklist audited by: MIT Radiation Protection' Date -' Oficer 1 E i i SR#-0-93-5 MAY 281993

j PM 3.14.3.3 Page 19 of 26 Neutron beam lxad shutte M '<1 < m'<<<<sy reve'hy',; [ Delimi Laser i Whole body shield i 1 I I I I Plumb bob 235 A F!P! couch at m; {W j lowest position. 4:-r:-: 2 = Y NE;';'ay I I <[-- Stool 50 m lmma umasummmmmm mmmmmuamap Y Y Figure 1 i i !O i i SR#-0-93-5 MAY 281993 4

j' u l_ PM 3.14.3.3 l l Page 20 of 26 1-( Neutron beam l l lM M i i } l Physician i Patient I j cM/> l pjElR F W6 \\ 2t i i-. 'i T"'T" M min [sumEmum innsa aump t l lMm M mMl i f l Figure 2 f I i i i Y h l i 1 l SR#-0-93-5 MAY 281993 3 a

1 e i PM 3.14.3.3 Page 21 of 26 1 4 Neutron beam i. i 'X'X'X lead shutter N i i N,W/, /,W,W i N,W/, pWN// M I I j I IM M b i i j i i I i 4 N i 5-- 2: fj i:::-J-sm.-.2.: -i i l'. 'l F. 'l l Si / 1 lMEmW Emp i y lMIMM IWl 1 j IEl I!l i Figure 3 4 1 1 i i 1-i J e 1 I SR#-0-93-5 MAY 281993 E i

l,. PM 3.14.3.3 Page 22 of 26 4 1 ] Neutron beam h i 30 cm U V [ l i _, l 3;iaisr'kk7!- d I l 1i I j j i--_ --3 l'. 'l F. "I \\ [ i lMEmW EMl I!I I!I i l-Figure 4 i SR#4)-93-5 MAY 281993

i i PM 3.14.3.3 i Page 23 of 26 4 1 i Neutron beam i { .y'y'y';yX lead shu ^ N I fy,';,sy; / /// // / ////// M M j [ b 4 i I-M I I i l 1 i i i l l y----_ l E --- - 1 I l'. 'l F. "I i l N i / j i-s-lmI-m.-I ll 1 irl i!! 1, Figure 5 i i i l 1 i i t i 8 j 0 1 i I i 1 SR#-0-93-5 MAY 281993 4 a i

PM 3.14.3.3 Page 24 of 26 Neutron beam l ' ',' ',' ' p lead shutter M s'o'o'e'e's's /*s 's's'e','e,' ss ssssss ssss t y Y T1/'

EITI C lM 5

h I i v - -- - ---_' FEM --E = l' e 'l F. *1 %i / O i-- I!l I!! Figure 6 i f i i i i 4 i

lO SR#-0-93-5 MAY 281993

i j PM 3.14.3.3 Page 25 of 26 i Neutron beam ,' ','u,,,,',5;;:: Lead shutter M, asus, s .'N, NN

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t 3 j lME M EMl 1 i 4 Figure 7 I i 1 i 1 i j 4 l f 3 SR#-0-93-5 MAY 281993 4 i I 1

jl' PM 3.14.3.3 l Page 26 of 26 i, i l Neutron beam X '?' X ad shutte N /t 4 ??????, ??????; 1 i ??????, p W r??/ i j m M 1 i ,i luus M I .I 1 ] l 1 E 1 umanamaammaama6 1 t s s {- t x :- D mHW83 m 'i r i 4 i'. !O i lME M EMl J 4 j Figure 8 i 3 1 1 4 1 i 1 1 i O i SR#-0-93-5 MAY 281993 4 t i e d

9 PM 3.14.3.4 Page 1 of 8 l.

!r PM 3.14.3.4 Beam Monitor System Setooints l r Puroose: This procedure ensures that the various controls for the neutron capture therapy l facility's beam monitors are set at the proper values. Accentance Criteria: l l Beam monitor system settings are set as specified.- Procedure: The beam monitor system consists of five detectors: two Li-6 covered TGM fission chambers (TGM FC4A/100), a bare LND fission chamber (LND 30753), an LND He-3 chamber, and an LND ionization chamber. Equivalents to these chambers may be used. These chambers are, for simplicity, referred to elsewhere as epithermal #1, epithermal #2, thermal #1, thermal #2, and gamma. These names reflect the principle type of radiation to which each chamber is sensitive. The objective here is to verify that the controls for these detectors are set as specified. l A. EPITHERMAL #1 - (TGM FC4A/100) HIGH VOLTAGE (CANBERRA Model 3106D ) Turn power to: ON Tum voltage to: 0.25 kV lack voltage dial. SCA (CANBERRA Model 2035A) Window (AE): . MAX lowerlevel(E): 2.0 AE range b 10V IV Delay : LO. Input Shaping: O 0.1-0.5 s 00.5-2s d 2-10 s O SR#-0-93-5 MAY 281993

. PM 3.14.3.4 Page 2 of 8 Delay Range: 01-li s b0.1-1.1 s [ AMPLIFIER (CANBERRA Model 2012) I i' Coarse Gain: O4 O8 0 16 b 32 0 64 O 128 Adjust Fine Gain to: 5.0 Input Polarity: b Positive (+) O Negative (-). COUNTER / TIMER (CANBERRA Model 1772) Set counts to b 0.1 sec 0 0.01 min Set counts to O SINGLE b RECYCLE Set signal to N POSITIVE O NEGATIVE l M SET to % (N x 10 ) i Press STOP Press RESET l Press START i SR#-0-93-5 MAY 281993 i l l

PM 3.14.3.4 Page 3 of 8 B. EPITHERMAL #2 - (TGM FC4A/100) O HIGH VOLTAGE (CANBERRA Model 3102D) Turn power to: ON Turn voltage to: 0.25 kV Iack voltage dial. l i SCA (CANBERRA Model 2030) Window (AE): MAX Imwer12 vel (E): 2.0 AMPLIFIER (CANBERRA Model 2012) Coarse Gain: O4 08 0 16 b 32 O O e4 O 128 _._ Adjust Fine Gain to: 3.0 Input Polarity: b Positive (+) O Negative (-) COUNTER / TIMER (CANBERRA Model 1790C) l l Display Select OA bB Set counts to b 0.lsec 0 0.1 min O SR#-0-93-5 MAY 281993 l l-4

. j f- - PM 3.14.3.4 l Page 4 of 8 l j l .\\ l Set PRESET as follows: b Value of Nis 3 b Value of Mis 5 ~ - 1 Set counts to: SINGLE. b RECYCLE Pmscalar bin l Out Preset bin O out i Press STOP i Pmss RESET Press START i C. THERMAL #1 - (LND 30753) i HIGH VOLTAGE ( CANBERRA Model 3106D) Turn voltage dial to zero Turn power to: ON Turn Voltage to: 0.50 kV lock voltage dial. SCA (CAMBERRA Model 2035A) Window (AE): MAX Lower Level (E): 4.0 AE range N 10V IV ) Delay : _.LD_ SR#-0-93-5 MAY 281993 j .m w T-~t*

[. i ' PM 3.14.3.4 Page 5 of 8 l Input Shaping: O 0.1 - 0.5 ps - i O 00.5-2 s N 2-10 s f l Delay Range: 0 1 - 11 l s. N0.1-1.1 s 1 AMPLIFIER (ORTEC Model 485) CoarseGain 0 4 l j l 08 0.16 N 32 0 64 0 128 Adjust Fine Gain to: 2.0 i l -I Input Polarity: b Positive (+) Os Negative (-) i Signal N Unipolar l Bipolar l COUNTERfrIMER (CANBERRA Model 2071 A) i _ Display Select O A bB i Set counts to: O 0.01 sec } Count B l w 0.01 min Set PRESET as follows: Value of Nis 9 Value of M is 9 Value of Pis 6 SR#-0-93-5 MAY 281993' i +-Tt' +'W t

• r 9

4 rr*m'v =W4* Y +r

1. f*wt Trs=' M94r- = -

w

PM 3.14.3.4 l Page 6 of 8 i Set signal to: N SINGLE O RECYCLE f Press STOP l Press RESET Set signal to: SINGLE l b RECYCLE Press START i D. THERM AL #2 - (LND He-3 Chamber) HICI: VOLTAGE ( CANBERRA Model 3102) s Tum power to: ON l Turn Voltage to: 20Q Volts i lock voltage dial. 3 PICOAMMETER (KEITHLEY Model480) Turn power to: ON Zero check OUT I Push botton to select approparite scale and record: 01 nA j O 10 nA I i 100 nA O 1pA O 10 A 100 pA 1.mA i i DUAL COUNTER (CANBERRA Model 2072A) Display Select bA B Press STOP SR#-0-93-5 MAY281993

PM 3.14.3.4 Page 7 of 8 Press RESET Press START l J E. GAMMA-(LND Ionization Chamber) HIGH VOLTAGE (ORTEC Model 459) - l Turn power to: ON Turn Voltage to: 200 Volts i = Ink voltage dial. i l l l PICOAMMETER (KEITHLEY Model 485) Set Zero Check botton to: OUT l i l Turn power to: ON Set to AUTO DUAL COUNTER (CANBERRA Model 2072A) Display Select C A bB i Press STOP t l Press RESET l l Press START i l l l F. OSCILLOSCOPE SETTINGS- (Model No. 1 [ TRIGGERING Set source to: INT Set mode to: AUTO l O SR#-0-93-5 MAY 281993 i

i - PM 3.14.3.4. I Page 8 of 8. 9-CONTROLS i O Setinput signal from dete: tor to: FRONT l t Setinput to: CHANNEL #1 I Set volts per division to: 2 for epithermal #1 f 2 for epitherma! #2 l 2 for thermal #1 } Set seconds per division to: 1 ps for epithermal #1 j 2 s for epithermal #2 [ 2 s for thermal #1 Set voltage to: AC l i The acceptance criteria is that all beam monitor system settings are set as specified. Acceptance Criteria Met: Yes O No O Check performed by: { NCF Research Scientist Dme l l. Check checked by: i NCF Research Scientist Dme i i I Reviewed by-NRL Director Date l l ( l I. i l . l l - r i SR#-0-93-5 MAY 281993 l g 4 r % m s- .y w,

PM 3.14.4.1 i Page1of1 PM 3.14.4.1 Searchine and Securine of the Medical Therany Facility 1. Physician authorized user verifies that patient is properly prepared for therapy. 2. All personnel, except the patient, are directed to clear the facility.- 3. The Reactor Radiation Protection Officer and the Director of Reactor Operations, or ' i their designates, search the medical therapy facility and verify that it is clear of personnel. l i 4. The medical therapy room's inner door, masonite door, and shield door are closed. 5. Observation via either the closed-circuit TV or the viewing window indicates that the room is clear of all personnel except the patient. I I lO 1 l i i -O v SR#-0-93-5 MAY 281993 i _,,-,.m.

PM 3.14.4.2 Page1of1 PM 3.14.4.2 Corrective Action for a Shutter or Other ? Malfunction k 1. For any type of malfunction, notify the contml room operator. i If the H O shutter does not close, notify the control room operator to lower tractor ' 2. 2 power to 50 kW or less. 3. If either the lead or boral shutters fails to close, do the following: a) Pull the lanyard for the manual control air release valve that is located above the sernndary chemistry facility. b) Close shutters manually by pulling the lanyards located outside the wall of the fuel pool storage room. 4. If the shutters still can not be closed, notify the control room operator to lower reactor power to 50 kW orless. 1 r i l O l SR#-0-93-5 MAY 281993 l l ... m ~. w 9 92 9

{- PM 3.14.4.3 Page1of1 PM 3.14.4.3 FDA NOTICE REOUIREMENTS

• * *
• CAUTION * * *
• t I

h THE MITR-II MEDICAL BEAM IS AN INVESTIGATIONAL DEVICE, LIMirED BY FEDERAL LAW TO INVESTIGATIONAL USE. l t THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY REACTOR (MITR-II) MEDICAL BEAM HAS BEEN CATEGORIZED AND APPROVED BY THE U.S. FOOD AND DRUG ADMINISTRATION (FDA) AS A."SIGNIFICANT RISK DEVICE." AS SUCH THIS DEVICE FULLY COMPLIES WITH FDA INVESTIGATIONAL DEVICE EXEMPTION REGULATIONS AS DETAILED IN THE U.S. CODE OF FEDE ' '.L - REGULATIONS SECTIONS 21 CFR PART 812,21 CFR PART 813,21 CFR PART l 50, AND 21 CFR PART 56. THE FOLLOWING INFORMATION IS PROVIDED i UNDER FDA REQUIREhENTS AS DEFINED IN 21 CFR 812.5. l ADDRESS OF LOCATION OF MITR-II hEDICAL BEAM MIT NUCLEAR REACTOR LABORATORY hEDICALROOM BUILDING NW12 RIDG 39 i i l ' O SR#-0-93-5 MAY 281993 ..w,,. - - 4

PM 3.14.4.4 Page1of1 PM 3.14.4.4 Emereenev Evacuation of a Patient !,\\ h 1. Initiate a minor scram of the reactor from either the medical therapy facility console or the reactor control room. Console operator notify Reactor Radiation Protection Office of the emergency. 2. Open the shield door to the medical therapy facility and verify that both the shutters that control beam delivery and the D O all stan to close. 2 3. Two or more attending personnel and the member of the Reactor Radiation Protection Office who is assigned to the therapy enter the medical therapy facility room. The fonner are to assist the patient. The latter is to survey the room. 4. Iower the couch by opening the fast +perating pressure relief valve for the couch's hydraulic system. 5. Release the strap buckler and rails (if used) while lowering the couch. 6. Assist the patient off the couch and exit the room. p k. l l t i\\ l V SR#-0-93-5 MAY 281993 L --

l t L PM 3.14.4.5 Page1 of1 i l PM 3.14.4.5 Emernency Entry with Pb and Boral Shutters Pumose: This procedure provides a means to enter the medical therapy facility room without first closing the Pb and Boral shutters. Such an entry would be necessary if closure of either shutter could cause injury to the patient. This situation is considered incredible because the beam delimiter completely blocks access to the closure paths of the shutters. } Nevenheless, prudence dictates that a procedure be in place for such an eventuality. Use of this procedure defeats the interlock that causes the shutters to be closed upon operung of the medical therapy facility's shield door. Hence, strict adherence to radiation safety is essential. Prereoyisite: l 1. Reactor Radiation Protection Officer or his designate notified of the need to use this procedure. ~ Procedure: i 1. Minimize radiation levels in the medical therapy facility room by: Closing the H O and D O shutters, a) 2 2 b) Lowering the reactor's power level to 50 kW or less. 2. Pull the lanyard for the manual control air release value (CV-77) that is located above the secondary chemistry facility. 3. Open the medical thempy facility's shield door via the pushbutton on the contml panel. 4. Reactor radiation protection personnel enter the room and survey. 5. Medical personnel enter the mom and assist the patient as appropriate. 6. Verify that closure of the shutters will not cause any injury to the patient or to anyone else. 7. Close the manual control air release valve, CV-77. This action will cause the shutters to close. l Checklist completed by-Reactor Operator Date j Checklist reviewed by: l fm Senior Member of Operations Date 1 5 SR#-0-93-5 MAY 281993 l

PM 3.14.5.1 Page 1 of 8 - 1 l I PM 3.14.5.1 Non-Licensed Medical Personnel Oualification g(y Proernm for Use of the Medical Therany Facility i Puroose: This qualification pmgan provides a means for training non-licensed individuals, either experimenters or mcdical personnel, on the use of the MITR medical therapy facility. Those wishing to participate in human therapies, or other medical activities,'should complete the entire program. Those whose only use of the facility will be for experiments that do not include human subjects may omit items related to MITR Technical Specification No. 6.5 and the Quality Management Program. Material for Studv: 1. Read and study the following material: l a) MITR Reactor Systems Manual - Sections 2.6, 2.11, 3.34, 3.52, and Figure 2.9. b) MITR Technical Specification No. 6.5, " Generation of Medical Therapy Facility Beam for Human Therapy." c) MITR Quality Management Program for Generation of MITR-II Medical herapy Facility Beam for Human Herapy. d) Procedures (3.14 series) used to implement the technical specification and quality management program. 2. Obtain a tour of the medical therapy facility that includes a discussion and, where possible, a demonstration of the following: Operation of the D O shutter and the shutters that control beam delivery, a) 2 b) Operation of the shield access door, inner door, and the masonite door. c) Operation of the hydrauliclift. i d) Shutter controls including the medical room minor scram. e) Use of the intercoms. i f) 1.ocation and use of radiation monitors. g) Scam alarms associated with the medical facility room. Knowledge Factors - Facility Ooeration and Design 1. Discuss each of the factors listed under facility operation and design on the qualification card with a licensed senior reactor operator. When the senior operator O SR#-0-93-5 MAY 281993 ._j

. PM 3.14.5.1 Page 2 of 8 is satisfied with the applicant's comprehension of the subject, he or she will initial and date the card in the appropriate column. l 2. Discuss each of the factors listed under technical specificadon and QMP on the qualification card with the Director of Reactor Operations or his. designate. When : ..the latter is satisfied with the applicant's comprehension of the subject, he will initial and date the card in the appmpriate column. 3. Perform the practical factors listed in the c ualification card to the satisfaction of a licensed semor reactor operator. _ When tie senior operator is satisfied with the ' applicant's comprehension of the subject, he or she will initial and date the card in the appropriate column. a t I i k LO I l l f i SR#-0-93-5 MAY 281993 l. -1 l I m..

1 PM 3.14.5.1 i Page 3 of 8. 1 Qualification Card for Use of MITR Medical Therany Facility-O 1 j 1. Name: 2.

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3. Organization: l 4. Telephone / Fax No.: j

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Study Material: I cenify that I ' ave read and studied sections 2.6, 2.11, 3.34, 3.52, and Figure 1 h ' 2.9. of the MIT Reactor Systems Manual, MITR Technical Specification No. 6.5, the associated Quality Management Program, and the procedures. (3.14 series) for implementing the technical specification and QMP. + Signature Dae. -i O l Knowledee Factors on Facility Ooeration and Desien -) i l i lism - laitial ' Dan 1. Shutters a) Types and design b) Methods of operation (automatic, manual) c): Purpose of each shutter p d) Normal sequence for opening / closing e)- Reactivity effects of shutter operation f)~ Interiveks [ g) Shuttercycle ames LO ~ SR#-0-93-5 MAY 281993 .. m.

PM 3.14.5.1-Page 4 of 8 i Itsm. lainal Dat O 2. Shield Access Doors a) Design j 1 ~ b) Method of operation (automatic, manual). j c) Purpose d) Interlocks with shutters j e) Imcation of breaker f) location of emergency stop. g) . Role of masonite auxiliary door 3. Control Parel j a) ' Key switch and key control l b) Minor scram H 0/D Olevelmeters. c) 2 2 I d) Shutterindicatorlights e) Shutter controls f) Low air pressure light. g) Low air pressure interlock. 4. Radiation Monitors a) Area monitor (location, setpoint, remote alarm) b) Medical room monitor (location, setpoint, remote alarm) c) Interlock of medicalroom monitor with shield access door d) Control panelradiationindicator. e) Use of portable monitors O SR#-0-93-5 MAY 281993

= PM 3.14.5.1 Page 5 of 8 I .l f - llCm lilitial Dale l s 5. Scam Panel Alarms i a) Medical room shield door open-l f ~ b)- ' High radiation area monitor I c) No overflow H O shutter. 2 d) Reactor o xratorresponse on receipt of medicalarea alarms i 6. Intercoms i a) Operation ofintercom to controlmom b)

• . tion ofintercom to medical mom inIrior 7.

Radianon Izvels a) Neutron flux in beam b) Gamma flux in beam c) Dose rates within room with shutters open l_ I d) Dose rates within room with shutters closed o ) e) Dose rates exterior to medical therapy.. facility. i L f) Response to radiation alarms l 8. Exm--L.#nt Setun a) Prevention of medical room activation from scattered neutrons b) Protection against gamma rays i c) Mdicalroom ventilation d). Use of medral mom' sink - - i e) Use of hydraulic lift f) Effect of residual liquid in shutters on beam characteristics t SR#-0-93-5 MAY 281993

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~. L PM 3.14.5.1 ' Page 6 of 8 4 i t 4 6 l-hcm lainal Dalc l i j-9. Administrative Reauirements l t.. 1 a) - Scheduling of experiments j-b) MITR Irradiation Infonnation j j for Appmved Samples Form ~ c) Irradiation Information Form (Part II) j . d) Irradiation Request Form (Pan I) ' .l t l l. h j e) . Rules for experimenters 1 ? t 4 j Knowledne Factors on Technical Snecification/OMP - 4 i I 1. Teeindcal Soccification Provisinnc.

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i 4 e j a) Patient referral. i l b) Division of responsibility between - -i j MIT and Medical Use Licensee 1 4 i c) Authority to initiate patient therapy i. j d) Authority to terminate patient therapy 1 i e) Daily source-check of radiation monitor ] i i f) Continuation of patient therapy on loss' l l of closed-circuit TV. l g) Cri,teria on the delivery of fluence to the. j panent h) Beam monitor functionalcheck i j-i) Calibration check of beam i j) Beam char.2aization ?- sj' k) Maintenance / repair activities l). Training requirements l m). Operation of shutters that affect reactivity 1 4~ n) Reporting of misadministrations to the - U.S. Nuclear Regulatory Commission : - _ /~Y V SR#-0-93-5 MAY281993 L i )

l PM 3.14.5.1 Page 7 of 8 r^ hcm Inmal Dit 2. Onnlity Management Procram Provisions r a) Authorized MedicalUse Licensees b) Contents of written directive .t c) Hand-delivery of written durctive d) MIT sign-off on written directive i for delivery of requested fluence e) Patientidentification i l f) Plan of treatment - g) Monthly review of satisfactory. l performance of written directive requurments i i h) Reviews of the QMP i) Response to recordable event j) Program modification 3(G 3. Procedures a) Technical Specification as a condition i of the reactor's license l b) Requirements to change a procedure l l l l c) General pirparations for therapy .i l d) Conduct of human therapy e) Source check of medical room monitor i f) Requirements for posted instructions g) Search and secure procedure h) Action if shutters failto close l i) Emergency temovalof patient l j) FDA posting requirements. A I l l SR#-0-93-5 MAY 281993 . ~...

t PM 3.14.5.1 Page 8 of 8 ~ Practical Factors lism Imtial Dan Cycle the H O or D O shutter-l 1. 2 2 2. Cycle the lead and boral shutters 3. Close the lead and boral shutters manually 4. Demonstrate procedure to open medical room shield access door manually - using either the exterior or interior winch 5. Demonstrate operation of hydraulic lift l 6. Demonstrate operation of fast-operating l relief valve on the operating couch i 7. Use theintercom to the controlroom 8. Test the area radiation monitor - 9. Test the medical room radiation monitor O. 10. Demonstrate the procedure for emergency removal of a patient l Certification l l This is to certify that is qualified to utilize the MITR medical therapy facility for the conduct of: a) Experiments O b) Human'Iherapy i l l Senior Memberof Operations Staff - Date - G ,O L SR#-0-93-5 MAY 281993 b-

ti. i-PM 3.14.5.2 L. Page1ofI r6 PM 3.14.5.2 Test of Emereency Evacuation of a Patient from i the Medical Therany Facilif" RRDE j i. 4 Purnose: 1 This procedure provides directions for the safe and rapid evacuation of a patient { from the MITR Medical Therapy Facility. Accentance Criterion: Patients who are strapped into the medical therapy facility's couch can be evacuated i within about 120 seconds without any undue exposure to assisting personnel. j Procedure: 1 1. Initiate a minor scram of the reactor from either the rrdical therapy facility ? 3 console or the reactor control room. Console operator notify Reactor. Radiation Protection Office of the emergency. 2. Open the shield door to the medical therapy facility and verify that both the j shutters that control beam delivery and the D O shutter all start to close. 2 l 3. Two or more attending personnel and the member of the Reactor Radiation i Protection Office who is assigned to the therapy enter the medical therapy 8 facility room. The former are to assist the patient. The latter is to survey the area. 3 4 l 4. Iewer the couch by opening the fast-operating pressure relief valve (15 's). j 7 i 5. Release the strap buckles and rails (if used) while lowering the couch (< 5 s). i l 6. Assist the patient off the couch and exit the room (< 35 s).. 7. Verify that a copy of steps (1) - (7) of this procedure are posted at the j medical therapy room facihty. i Acceptance Criteria (patient removed s 120 s) met: Yes O No-O ) i Test performed by: NCF Research Scientist Date Supervisor: Senior Reactor Operator Date. SR#-0-93 MAY 281993

t'. t' Emereency Evacuation of a ' Patient O l Initiate a minor scram of the reactor fmm either the medical th facility console 1. or the reactor control room. Console operator notify Reactor Rbation Protection l Office of the emergency. 1 - 2. Open the shield door to the medical therapy facility and verify that both the shutters -. that control beam delivery and the D O shutter all stan to close.; ' i 2 s 3. Two or more attending personnel and the member of the Reactor Radiation. J Protection Office who is assigned to the therapy enter the medical therapy facility ' room. The former are to assist the patient.' He latter is to survey the area. 4. Lower the couch by opening the fast-operating pressure relief valve. 5. Release th'c strap buckles and rails (if used) while lowering the couch. l 6. - Assist the patient off the couch and exit the mom. i t lo 4 'l I O SR#-0-93-5 MAY 281993 i i v g,, r-y. y y e c.+ ir . an ea 4 my+--w.- r., ,-e-, e -w e e w --.+-w. .r,-w,---- -e,- v. er, .c-o+.,--.%,--.-et-r,,m4 eI}}