ML20024E686
| ML20024E686 | |
| Person / Time | |
|---|---|
| Site: | 05000199 |
| Issue date: | 08/31/1983 |
| From: | Augustus J, Berlin R, Kane G MANHATTAN COLLEGE, RIVERDALE, NY |
| To: | |
| Shared Package | |
| ML20024E685 | List: |
| References | |
| NUDOCS 8308300374 | |
| Download: ML20024E686 (40) | |
Text
{{#Wiki_filter:. SAFETY ANALYSIS REPORT Manhattan College, Zero Power Reactor
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by Dr. Joseph Augustus Mr. Robert Berlin Bro. Gabriel Kane, FSC Dr. Ronald Kane i Submitted to United States Nuclear Regulatory Commission for Renewal of Facility License R-94 Manhattan College Nuclear Engineering Facility Manhattan College Riverdale, New York 10471 ) 1 Atg ust 1983 gaoe3co374 i
TABLE OF CONTENTS Page Cover Sheet i Table of Contents ii List of Tables and Figures
- 1. 0 INTRODUCTION AND GENERAL DESCRIPTION 1-1
- 2.0 SITE CHARACTERISTICS 2-1 2.1 Geographical Location 2-1 2, 2 Geology 2-1 I 2.3 Hydrology 2-1
- 2. 4 Seismology 2-2 2-2 2.5 Meteorology Demography and Land Use 2-2
- 2. 6 3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS 3-1 3.1 Structural Design 3-1
- 3. 2 Waste System 3-2
- 3. 2.1 Used Demineralizing Resin 3-2 4
3.2.2 Waste Water 3-2 ,
- 3. 3 Utilities and Services 3-2
- 3. 3.1 Ventilation 3-2 3.3.2 Fir'e Protection 3-3
- 4. 0 REACTOR 4-1 4.1 Reactor Vesnel 4-1
- 4. 2 Control Systems 4 4. 3 Area Monitors 4-2
- 5. 0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5-1 5.1 Primary Coolant System 5-1
- 5. 2 Water Make-tp System 5-1
- 5. Demineralizer System 5-1
- 5. 4 Sediment Cleaning System 5-1
- 6. O ENGINEERED SAFETY FEATURES 6-1
- 7. 0 INSTRUMENTATION AND CONTROLS 7-1 7.1 Introduction . 7-1
- 7. 2 Identification of Safety-Related Systems 7-1 7.2.1 Console 7-1 7.2.2 Nuclear Instrumentation 7-3 7.2.2.1 Log Count Rate Channel 7-3
- h. Linear Channel 7-3
! 7.2.2.2 7.2.2.3 Gamma Channels 7-3 y I e li
Page 7.2.3 Non-Nuclear Instrumentation Channels 7-4 7.2.3,1 Control Rod Drive System 7-4 7.2.3.2 Control Rod Withdrawal 7-4 Inhibit System
- 7. 3 Reactor Trip System 7-5
- 7. 3.1 Nuclear Instrumentation Scram Trips 7-5 7.3.2 Nuclear Instrumentation Reverse Circuit Trips 7-6 8.0 ELECTRIC POWER 8-1 8,1 Introduction 8-1
- 8. 2 Offsite Pbwer Systems 8-1
' 8. 3 Onsite Power Systems 8-1
- 9. O AUXILIARY SYSTEMS 9-1 9.1 Fuel Storage and Handling 9-1 9.1.1 New Fuel Storage 9-1 l 9.1. 2 Spent Fuel Storage 9-1 9.1. 3 Temporary Storage of Fuel During 9-1 Preventive Maintenance
- 9. 2 Water Systems 9-1 9, 2.1 Cooling Systems 9-1 9.2.2 Demineralizing System 9-2 9.2.3 Water Make-Up System 9-2 9.2.4 Cathodic Protection 9-2 9.2.5 Potable Water 9-2 9.2.6 Sanitary Water 9-2
- 9. 3 Floor Drainage Systems 9-2
- 9. 4 Ventilation System 9-2
- 9. 5 Other Auxiliary Systems 9-3 l 9. 5. I Fire Protection System 9-3 s j 9.5.2 Communications System 9-3 9.5.3 Lighting System 9-3 10.O STEAM AND POWER CONVERSION SYSTEM 10-1 11.0 RADIOACTIVE WASTE MANAGEMENT 11-1 11.1 Waste Disposal Criteria 11-1 11.2 Accumulation of Active Wastes 11-1
- 11. 2.1 Dry Waste 11-1
- 11. 2. 2 Liquid Waste 11-1 11.3 Waste Transfer 11-2 11.4 Disposal of Pool Water and Demineralizer Resin 11-2
, 11.5 Surveys 11-2 iii
Page 11.6 Protective Supplies 11-3 11.7 Logs 11-3 12.O RADIATION PROTECTION 12-1
- 12. 1 Health Physics Program 12-1 12.2 Insuring That Occupational' Radiation Exposures 12-2 Are As Low As Reasonably Achievable (ALARA) 12,2.1 Administration 12-2
- 12. 2. 2 Reactor Operations Committee (ROC) 12-3 12,2. 3 Radiation Safety Officer (RSO) 12-4
- 12. 2. 4 Authorized Users 12-4
- 12. 2. 5 Persons Who Receive Occupational Radiation 12-5 Exposure
- 12. 2. 6 Establishment of Investigations 1 Levels In 12-5 Order to Monitor Individual Occupational External Radiation Exposures 12.3 Personnel Monitoring 12-7 12.4 Other Radiation Protection Measures 12-7 13.0 CONDUCT OF OPERATIONS 13-1
- 13. 1 Organizational Structure of the Applicant 13-1 13.1.1 Management and Technical Support 13-1 Organization 13.1. 2 Operating Organization. Reactor 13-1 Operations Committee 13.2 Training 13-2 13.3 Emergency Planning 13-2 13.4 Review and Audit 13-3 13.5 Plant Procedures 13-3 13.6 Physical Security Plan 13-3 14.O INITIAL TEST PROGRAM 14 15.0 ACCIDENT ANALYSIS 15-1
-15. 1 Introduction 15-1 15.2 ' Nuclear Excursions 15-1 15.2.1 Nuclear Excursion During Operation 15-1
- 15. 2. 2 Nuclear Excursion During Fuel Leading 15-1
-15. 3 Effects of Rapid Reactivity Insertion 15-2 15.4 Lo s s of Co 'olant 15-2 15.5 Fission Products Release 15-2 15.6 Radiation Dose for the Maximum Hypothetical 15-2
, Accident 15.7 Conclusion 15-2 iv l i
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Page 16.0 TECHNICAL SPECIFICATIONS 16-1 (Self-Contained Table of Contents with 7 Figures) 17.0 QUALITY ASSURANCE 17-1 REFERENCES R-1 APPENDICES A. Radiation Safety Manual A-1 i B. Plan for Training Applicants to Prepare for a B-1 Reactor Operator's License Examination for Manhattan College Zero Power Reactor C. Current Operators Licenses C-1 l D. Reactor Console Checkout Sheets D-1 E. Emergency Plan: St. Joseph's Hospital Agreement E-1 F. Physical Security Plan F-1 G. October 6,1966 Correspondence G-1! H. November 15, 1966 Corre spondence H-1 I. January 24, 1967 Correspondence " Experimental I Determination of the Temperature Coefficient of Reactivity of the Manhattan College Zero Power Reacto r" J. Operator Requalification Program J-1 ' e il l-4 V
LIST OF FIGURES Figure Title Page 2.1 Plan of Manhattan College Campus 2-3
- 2. 2 Map of Area Surrounding the Leo Engineering Building 2-5 3.1 Plan of First Floor of the Leo Engineering Building 3-4
- 3. 2 Plan of Second Floor of the Leo Engineering Building 3-5
- 3. 3 Plan of First Floor of ZPR Room 3-6
- 3. 4 Plan of Second Floor of ZPR Room 3-7 5.1 Schematic Diagram of the Demineralizing System 5-2
- 5. 2 Reactor Tank Cleaning System 5-3 7.1 Control System Block Diagram 7-7
- 7. 2 Control Rod Drive Circuit 7-8
- 13. 1 Organizational Structure 13-4 13.2 Agenda of Semiannual Reactor Operations Committee 13-5 Meeting vi
l l I l ! l l
- 1. 0 INTRODUCTION AND GENERAL DESCRIPTION l The Manhattan College Zero Power Reactor (MCZPR) is located I l
on the campus of Manhattan College in Riverdale, a residential section of the Borough of the Bronx in New York City. The reactor
- is situated in a Nuclear Engineering Facility within the Leo Engineer-ing Building at 3825 Corlear Avenue. The Nuclear Engineering l Facility, and particularly the Zero Power Reactor, are however designed for isolation from the rest of the engineering building to l provide additional security and safety.
The Nuclear Engineering Facility contains the Zero Power Reactor (a critical reactor), a graphite moderated suberitical reactor, and a light water moderated suberitical reactor. The physica11ayout includes a separate room containing the top of the critical reactor l vessel and the control console, a basement containing the bottom of the critical reactor vessel and auxiliary equipment, a separate room i containing the two suberitical reactors, a separate counting room, and a separate classroom. The critical reactor is a low power, pool type reactor, designed for a maximum power level of 0. I watt by AMF Atomics of Greenwich, Connecticut. Prior to installation at Manhattan College in 1964, the i reactor core had been used in 1961 by AMF Atomics in PTR (pressur - ized tube reactor) low critical research experiments at the IRL (Industrial Reactor Laboratory) reactor site in Plainsboro, New Jersey. The reactor is a heterogeneous pool type reactor, light water moderated I and fueled with 92 percent enriched uranium. It is intended solely for teaching and training. Consequently the maximum power level of 100 milliwatts authorized first by the Atomic Energy Commission and later by the Nuclear Regulatory Commission is quite adequate to serve these purposes. It also guarantees a high degree of safety. The radiation intensity at the reactor deck level directly above the core is only 1 mR/hr ! when operated at the maximum allowed power. There are two control rods in the reactor: one cadmium-stainless steel shim rod and one stainless steel regulating rod. The two detecting j instruments in the reactor are a BF 3 neutr n e ec r an an unc mPensated ion chamber. Two Geiger-Mueller counters are used for area radiation monitoring. The control console is located near the reactor vessel and contains all the necessary control switches, lights, and instrumentation required to operate the reactor efficiently and safely throughout its designed power range. I 1-1
- 2. O SITE CHARACTERISTICS 2.1 Geographical Location Manhattan College is situated along Manhattan College Parkway on the heights sbove Van Cortlandt Park, in the Riverdale section of the Bronx, New York City, just a few blocks south of the Yonkers City line.
The Zero Power Reactor is located on the first floor of the Leo Engineering Building (two blocks from the main campus) on Corlear
' Avenue. This building has been owned and occupied by Manhattan College since 1963. It was extensively remodeled three years ago with completion of new Chemical Engineering Laboratory and office space and expansion of the Engineering Library. The Zero Power
-Reactor has been in the same building and location since its installation at Manhattan College. The location of the building andits relationship to its surrounding is indicated in Figure 2-1.
The Leo Engineering Building provides classrooms, laboratories, library and computer facilities for an estimated 1800 students at any one time. Office space for the Dean of the School of Engineering, department heads, and engineering faculty is located in the building.
- 2. 2 Geology The main Manhattan College campus is situated on one of the highest elevations in New York City. Thirteen of the twenty acres on which the majority of College buildings are constructed, are situated over a rock formation known as the Fordham Schist which extends from this site south into northern Manhattan Borough under the Harlem River. However, the Leo Engineering Building in which the reactor is located is constructed on alluvial fill which extends to a depth of some one hundred and fifty feet.
- 2. 3 Hydrology No wells have been drilled on the Manhattan College campus nor in its vicinity. The water supply of the College is part of the New York City water system supplied principally through Croton Reservoir in Westchester County.
Surface runoff water is collected in concrete-line storm drains which empty into the New York City sewage disposal system. This drainage system has been adequate to prevent any flooding of the campus by f heavy rains. It is conceivable that the Leo Engineering Building in L which the reactor is located, constructed as it is on filled creek 2-1
. __ _ _ ~. _ _ _
L i L bottom land, could have a drainage problem in a very severe rain storm. However, this has not occurred over the 20 years in which the building has been maintained by Manhattan College. l Such an occurrence would not create a radiation hazard. I
- 2. 4 Seismology New York City has been seismically inactive in the geologic past u and it is extremely improbable that an earthquake will occur here l -in the near future. The reactor site should be free from any earth-quake hazard. However, the Leo Engineering Building (which is structurally independent.of any other building) does conform to the building code of the City of New York and should withstand even a severe shock. In the event of a rupture of the reacto r vessel, loss
- of water will reduce moderation and scram the reactor. The water in the vessel would then be contained within an independent overflow area in the basement of the reactor facility.
2.5 Meteorology . 1
- New York City has a warmer climate in winter and a cooler climate
in summer than most other cities located in the same latitude with the exception of some cities on the Pacific coast. The average annual 3
- precipitation is forty-two inches. Northwest winds prevail from -
November to April. From May to October south or southwest winds , are dominant. Light to gentle winds prevail much of the time during the warm months and on many days in the winter season, and winds i of gale force are seldom experienced. Occasionally during the months of August and September tropical storms of hurricane force are felt in the City. At these times high winds of almost fifty miles per hour are experienced. Such conditions do not present a danger to the structural integrity of the Leo Engineering Building or the Zero Power Reactor facility. Since the facility produces no gaseous effluent, the frequent temperature-inversions in the area present no radiological hazard to the public from the facility. 2.6 Demography and Land Use The demographic patterns and land use in the vicinity of the reactor building, including the Manhattan College campus buildings and local residences and businesses, have changed little since initiation of reactor operations in 1964. Figure 2.2 is a map of the area surrounding the Leo Engineering Building, showing individual residence structures, businesses, and [ other land use designations. The accompanying Table 2. I provides data on occupancy for the structures delineated on the map. I l i e 2-2
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st 38 - Rock Ledge 37 - St Joseph's llaN g' QA ** D g y 39 - Christian Brotters' 14 - Sears llaN (Development a%* Residence (3) Ofrece) i 43 DroderickllaN 6 Smah AuditoriunVChapel 41 - Galway flouse of De La Salle and His 42 - Dowiing flan Brothers 43 Bluff Cottage 12 - Solomon House 44 - Donohue llaN 45 SuNivanllail
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- Figure 2-1. Plari of Manhattan College Campus 2-3
Table 2.1 Estimated Occupancy of Buildings Shown on Map Legend Type of Building Estimated Occupancy Al 2 story detached I family 5-6 A2 1 story 1 family 7 A3 2 story brick semi-detached 1 family 6-7 B1 2 story brick 2 family 10 B2 2 story frame 2 family 8 i B3 Converted dwelling 2 family 8 ( C2 Walkup apartment 3-6 family 15-25 Walkup converted dwelling C5 15 D1 Elevator apartment 300 D2 6 story apartment 320 G4 Gas station with Work Shop 5-10 each G8 Garage with Show Room 10-20 K9 Proposed Manhattan College Research 300-500 and Learning Center S9 Unclassified Miscellaneous Buildings 10-50 U4 Utility Substation 5 V Va cant Lot - None Manhattan College Main Campus 2000-3000 None Leo Engineering Building 1000-2000 ( 10-25 i None Farrell Hall None Paulian Labs 10-30 None Gaelic Park 100-500 None Interborough Rapid Transit (Car Barn) 20-40 l I I l I l l j 2-4
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i 3.0 DESIGN OF STRUCTURES. COMPONENTS. EQUIPMENT AND SYSTEMS l This chapter identifies, describes and discusses the principal features i of the MCZPR laboratory. This presentation is simplified considerably from that required for a power reactor or most of the research and teaching reactors due to the characteristics of the MCZPR whicitis a compact,open
- pool reactor with low power capability (O. I watt).
3.1 Structural Design The MCZPR laboratory is located at the southeast corner of the Leo Engineering Building of Manhattan College. The floor plans for the first and second floors of the building are shown in Figures 3.1 and 3. 2 respectively, with the ZPR area shaded. The only access to the first (lower) floor of the ZPR area from the first floor of the Leo Engineering Building is through door D1 (Figure 3.1) which is kept locked and bolted from inside at all times. Door D2 on the first floor leads to a staircase to room 221 from which access to the ZPR room is through door D4 ~ (see Figure 3. 2) Access to Room 221 from the second floor of the Leo Engineering Building is through door D3. Access to the control console in the ZPR Room on the second floor is through door D4 from Room 221, Door D4 is visible to the operator at the console. The access doors D2 and D3 to Room 221 are provided with Fox Police locks. Room 107 on the first floow (Figure 3.1) is used as a Counting Room and Room 108 as a Briefing Room. Room 221 on the second floor contains a graphite moderated suberitical reactor and a water moderated suberitical reactor. The reactor tank made of aluminum sits on a concrete slab on the first floor. The tank is held in place by five aluminum brackets welded to the side of the tank near the bottom. The brackets are bolted to the concrete floor. Several concrete piers were added to the first floor of the structure to strengthen it (Figure 3. 3). There are concrete walls on three sides of the room. The base of the fourth wall consists of a concrete curb 1'0" high sufficient to permit the room to contain the entire contents of the tank. The remainder of the fourth wall consists of a metal partition to separate the reactor room from the ventilation equipment room for the Leo Engineering Building. The door D1 on this wall serves as access i 3-1
. t for bringing heavy items into the room. This door is kept locked and bolted from inside the reactor area.
The south wall of the room is an outside wall. This wall is reinforced and protected by a sloping slab of concrete 6'0" wide. A demineralizing tank sits on the floor next to the tank. Pipes to and from the demineralizer are suspended by supports from the ceiling. The height of this first floor room is 7'4-1/2". The reactor tank which is 8 ft. high extends upwards through the ceiling of the first floor. The reactor vessel is surmounted by a platform 2' 2-1/2" above the top of the tank and 2' 4-1/2" above the floor. The reactor vessel and the edge of the platform are protected with chain fences. The room is 16' 4" high. A window, VI, 4'3" X 4'3" is located on the south wall 8'0" above the floor. This window is protected by wire mesh and is secured with lock and key. The control console is 5'3" X 2'0" and 6'1" high. It is located 3'0" from the west wall of the ZPR Room. Plans of the first and second floors of the ZPR facility are shown in Figures 3. 3 and 3.4. 3.2 Waste System The reactor does not produce any radioactive waste either in the form of spent fuel or as radioactive b yproduct.
- 3. 2.1 Used Demineralizing Resin The demineralizing resin is replaced about two or three times a year.
The used resin is kept in marked containers for testing by the Health Physicist and appropriate disposal. No radioactivity has ever been found in the resin. 3.~ 2. 2 Waste Water The reactor does not generate any radioactive water. When the demineralizing resin is replaced, a small amount of water (about 3 gallons) is extracted along with the resin. This water is stored in marked containers for testing by the Health Physicist and proper dispo sal. ,
- 3. 3 Utilities and Services
- 3. 3.1 Ventilation l
The ZPR Laboratory contains a forced circulating ventilation system consisting of a blower and associated duct work which are' designed so as not to return air from the laboratory back into the ventilation system of the Leo Engineering Building. A separate blower, controlled by a switch located on the west wall of the ZPR Room, returns air into the atmosphere. 3-2
I l i I l 3.3.2 Fire Protection i l l Conventional fire protection is available throughout the Leo l Engineering Building. In addition, carbon dioxide fire extinguishers j are available on both floors of the Reactor Laboratory, i l t l I I l P 3-3
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- 4. 0 REACTOR The Manhattan College Zero Power Reactor (MCZPR) is a heterogeneous, pool-type using solid enriched uranium fuel and is moderated by light water. The principal components of the !
, reactor are the reactor vessel and its associated equipment, the control system, and the demineralizer system. The maximum t power allowed by the Nuclear Regulatory Commission is 100 milliwatts.
4.1 Reactor Vessel The reactor vessel consists of a large aluminum drum eight feet high and ten feet in diameter. The drum wall is one quarter of an inch thick. .The reactor core is centrally located at the bottom of the vessel and consists of a grid plate and stand upon which the fuel l elements are mounted. The fuel is 92 percent enriched U-235. There are fifteen full fuel elements and one partial fuel element containing a total of 3024 grams
; of enriched uranium. Each full fuel element is' made up of six concentric cylinders of fuel and is protected by a thick aluminum shield.
) Support for the neutron detectors, control rod drive mechanisms, and other control system hardware is provided by the reactor platform above the pool. Neutron and gamma-ray detectors are suspended in the pool while drive mechanisms are located on a mounting plate on the platform. i
- 4. 2 Control System The control console is located near the reactor vessel and contains all the necessary control switches, lights, and instrumentation required to efficiently and safely operate the reactor throughout its designed power range.
' There are two control rods, a cadmium-stainless steel shim rod and a e tainless steel regulating rod. By operating the control console j switches, the operator can drive the neutron-absorbing control rods either into or out of the reactor core, as required to control the
. reactor power level.
4 Measured neutron levels from the neutron detectors are amplified and displayed on the control console instruments, thus permitting the operator to monitor reactor performance. Several of these instruments can shut down the reactor automatically by providing a signal that t. 4-1
will catise the control rods to be driven or dropped into the core. These controls insure that the reactor will alwaye operate safely. 4.3 Area Monitors One area monitor (gamma-1) is located at the level of the reactor deck and a second area monitor (gamma-2) is located at the side of the reactor vessel about the height of the reactor core. When operated at maximum allowed power, gamma-1 reads ImR/hr and gamma-2 reads 2mR/hr. l L 4-2
- 5. 0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS This chapter describes the cooling system and other systems connected to the reactor. Due to the extremely low power rating of the reactor (O.1 W) these systems are very simple when compared with power reactors and most other research and teaching reactors.
5.1 Primary Coolant System The water in the reactor has an enormous heat capacity relative to the power rating (O.1 W). No recirculating cooling system is,
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therefore, provided. The total heat capacity of the poolis about 65 MJ/ C. 5.2 Water Make-Up System Water lost due to evaporation is replenished with city water. The water from the city system is passed through an electrically controlled Versa check valvea Barnstead -Bantam demineralizer, a flow meter and a short flexible hose over the top of the reactor tank. The check valve insures no back flow of water from the reactor in case of pressure loss in the water supply system. The flexible hose is removed from the reactor tank when the hose is not in use. The water levelin the tank is maintained at about 7 feet. 5.3 Demineralizer System Figure 5. I shows a schematic diagram of the demineralizing system. The only tank wall penetration-is a 3/4 inch aluminum coupling located 2" from the tank bottom, with a 3/4 inch short nipple and a 3/4 inch aluminum gate valve. The pump is connected to a 24 hour clock which is used to activate the pump switch. The system is run almost continuously except for daily
- rest periods. The flow starts at the bottom of the tank and passes through the pump, heat exchanger, demineralizer and into the tank through a goose neck over the edge of the tank. Valves are provided to alter the direction of flow through the demineralizing column. The steam-to-water heat exchanger was installed to study the temperature coefficient of reactivity.
. 5. 4 Sediment Cleaning System The reactor tank bottom is cleaned several times a year using a pool vacuum. The vacuum head is connected to the inlet of the pump through a flexible hose. The demineralizer column is b ypassed (Figure 5. 2) and the water returns to the tank through a gooseneck pipe at the end 4-of which a polyester filter bag is attached. The sediments collected in the filter bag and the used bags are retained for testing by the Health Physicist and appropriate disposal. The vacuum head and flexible hose are disconnected and stored when the system is not in use.
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- 6. 0 ENGINEERED SAFETY FEATURES No features are required in the reactor facility design to maintain safety against normal operations, upset conditions, or the
design basis accident other than those described in other sections of this report. The major safety features are the inherent excess reactivity characteristics of the core, the redundant methods available to make the core subcritical, and the extremely low operating power level, 1 l l 6-1
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- 7. O INSTRUMENTATION AND CONTROLS I
7.1 Introduction The reactor instrumentation monitors several reactor parameters and transmits the appropriate signals to the regulating system during normal operation, and during abnormal and accident conditions to the reactor trip and safety systems. Since the Manhattan College Zero Power Reactor (MCZPR) is an extremely low power (O. I watt), self limiting reactor, the instrumentation and associated controls are considerably simplified when compared to the instrumentation, and control systems of power reactor or even those of large research reacto rs.
- 7. 2 Identification of Safety-Related Systems The safety-related instrumentation and controls for the MCZPR include the control console, the control and safety channels, the facility interlock system, control drive switches, and the reactor scram circuitry. Figure 7. I shows a block diagram of the nuclear instrumentation and scram logic of the MCZPR.
7~. 2.1 Console j All functions essential to the operation of the MCZPR are controlled by the operator from a desk-type control console. The reactor console is conveniently located near the reactor to allow the reactor operator to monitor activities in the reactor core during operation. All instru-ments contained in the console accept signals from or send signals to the control rod drives, the reactor interlock systems and various detectors located around the reactor core and other parts of the i reactor system. l The reactor control panel contains the following control and indicating l instrumentation: 1 Reactor On-Off key
- 2. Power On switch
! 3. Toggle switch for Reg Rod
- 4. Toggle switch for Shim Rod
- 5. Coarse con;;rol indicator for Reg Rod i 6. Coarse controlindicator for Shim Rod
- 7. Fine control indicator for Reg Rod and Shim Rod 8 Log count rate meter scaler
- 9. Log count rate meter strip chart recorder i
7-1
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- 10. Linear meter recorder for non compensated ion chamber
- 11. Range switch for linear recorder
- 12. Battery test for linear recorder
- 13. Strip chart recorder for linear meter
- 14. Meter for. gamma 1 detector (above reactor core)
- 15. Meter for gamma 2 detector (at edge of reactor tank in basement)
- 16. Strip chart recorder for gamma 1 and gamma 2 detectors
- 17. Annunciator and annunciator lights for scram, reset, magnet power supply, high flux count, log count rate channel high, linear channel flux high, gamma channels high, and low water level.
- 18. Resets for gamma 1 and gamma 2
- 19. Reset for entire console
', 20. Reactor period meter The functions of some of these controls and indicating devices are summarized in the following paragraphs. The console Power On switch controls the AC power to all control circuits. The nuclear instrumentation channels receive power from a circuit breaker located in the rear of the console. The Reactor On switch activates the power in the electro-magnets permitting the operator to move the control rods thereby increasing or decreasing the reactivity. The coarse control rod indicators determine the position of the control rods to within 2%. The fine control rod indicators determine the position of the control rods to within O.1% A range switch for the linear recorder with 12 allowed steady state positions is located in the lower right-hand corner of the horizontal portion of the control panel. It is used in conjunction with the linear a.nplifier. A single pen strip-chart recorder is centrally located in the upper center portion of the console. The red pen provides a linear indication of power as a percentage of the range's position.
! . A log count rate meter ranging from 1 to 10 5 counts /second
. is located on the left side of the control panel along with the Reactor Period meter. t 7-2
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1 7.2.2 Nuclear Instrumentation Whenever fuelis present in the reactor tank the design of the nuclear instrumentation must conform to the specifications of this section. The following channels of instrumentation are functioning when the
, reactor is operated or core components are being moved. These channels are of the type and range as specified below:
7.2.7.1 Log Count Rate Channel 4 The log count rate channel consists of a BF Proportional counter, a preamplifier, high voltage power supply, 3 scales, log count rate meter, log count rate recorder, period detector and period indicator. The count rate channel detector is suspended from the reactor platform in the vicinity of the core such that a count rate of at least 2 counts per second is indicated as a result of subcritical multiplication with both control rods fully inserted.
- 7. 2. 2,2 Linear Channel i
f The 1!near channel consists of an uncompensated ion chamber, high voltage power supply, picoammeter, and a linear recorder. The linear
- channel detector is suspended from the vicinity of the reactor core such that a current greater than 5% of full scale as indicated on the recorder with the most sensitive scale selected on the amplifier will result with both rods fully inserted. The highest scale setting on the picoammeter is physically set such that 100% of full scale is no more than 0. 2 watts.
- 7. 2.2.3 Gamma Channels 1.- Two radiation monitoring channels are provided to measure gamma intensity. These channels are also used to monitor reactor operation and are used in the reactor safety system.
A strip chart recorder is provided with a selector switch for . recording the output of either channel.
- 2. Each channel consists of a Gamma Detector and a Gamma Indicator.
- 3. The Gamma Detector is a sealed unit containing a Geiger- ,
Mueller tube, transistorized count rate amplifier, and check source. The output from the Detector is logarithmic with respect to the radiation level. The check source is exposed to the Detector by a solenoid which is actuated by a push-button'on the control chassis. 7-3
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- 4. One of the Detectors (Gamma 1) is located on the reactor platform directly over the core area while the other Detector (Gamma 2) is mounted on the side of the reactor tank.
- 5. The Gamma Indicator contains the power supply for the system, the alarm reset check source control, and the output connector for the Detector. Also contained on the front of the Indicator I is a logarithmic meter relay for indication and alarm of the l gamma level. The alarm is set to give audible annunciation l should the radiation level exceed 6mR /hr for Gamma 1 or 10m R/hr for Gamma 2.
- 6. The range of both detectors is from . 01 to 100 mr/hr. The system is designed so that if the radiation intensity ever exceeds 100mR/hr the detector reads full scale.
- 7. 2. 3. Non-Nuclear Instrumentation Channels The MCZPR is supplied with several process instrumentation channels to monitor the normal operation of various systems; to aid in maintain-ing a steady-state power level, and also trip the system should an unsafe situation occur or instrument fail. Other channels supply information needed to safely operate the reactor but do not have protective functions. These Non-Nuclear Instrumentation Channels are described in the next three subsections.
7.2.3.1 Control Rod Drive System The control rod drive circuit is shown in Figure 7. 2. It consists of toggle switches and indicating devices used in operating the two control knobs. Six indicator lights are arranged in the center of the control panel in two vertical rows. Each row contains a green DOWN light, an amber UP light, and a white ON (on magnet) light. Push buttons make it possible to release either of the control rods separately and a SCRAM button makes it possible to release both control rods simultaneously. Turning off the Reactor-On key has the same effect as pres 61ng the SCRAM button. The currents in the electromagnets supporting the control rods are regulated by control knobs and measured by 100 milliampere meters. 7.2.3.2 Control Rod Withdrawal Inhibit System The Control Rod WithdrawalInhibit System has been shown in Fig. 7.1. This Inhibit Syatem is part of the reactor protection system and functions should the following situations arise: 4 7-4
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- 1. Instrumentation switches are not in proper position to monitor the neutron levelincrease as the blades are raised.
- 2. Insufficient neutron source counts are available to insure the proper function of the source level instrumentation.
A minimum of 2 counts per second is required by the 4 Technical Specifications.
- 3. The water level reading drops more than one foot below the normal tank full position.
- 4. The gamma channelintensity recorded on the strip chart recorder is below 0.2mR/hr and the bypass switch has not been turned on.
7.3 Reactor Trip System The MCZPR is provided with two types of reactor trips. The i reactor trips can be classified into two categories:
- 1. Scram trips. A Scram system is provided that will cause interruption of the magnet current to the electromagnets
; should a Scram trip be exceeded. The control rods then fall into the reactor core under the force of gravity.
' 2. Reverse Grcuit trips. A Reverse Circuit system is provided that will cause both control rod drives to drive the control rods into the reactor should a Reverse trip be exceeded. The Reverse action overides any rod selection made by the operator and persists as long as a Reverse trip levelis exceeded. 7.3.1 Nuclear Instrumentation Scram Trips l A Scram trip is provided for each of the conditions below, with the trip setting as specified: l
- 1. High neutron flux-Count Rate Channel electronic trip set for 400 % or less of Full Power (Full power is equal to 0. I watt).
I
- 2. High neutron flux-Linear Channel electronic trip set for 200% or less of Full Power.
- 3. IIigh gamma activity-high level signal from either of the two Gamma Channels electronically set for 10m R/hr or less.
{ 4. Manuti scram-operates upon actuation of the manual Scram
. button on the console.-
- 5. Low water level-operates should the tank water drop one
, foot below the normal tank full operation.
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- 6. Reactor On key switch off -operates when the " REACTOR ON" switch is turned to the off position.
7.3.2 Nuclear Instrumentation Reverse Circuit Trips Reverse Circuit trips are provided for each condition as below with the trip setting as specified:
- 1. A Count Rate Channel Reverse trip occurs for any of the ic11owing conditions:
- a. Count Rate recorder off
- b. Count Rate recorder down scale - occurs should the recorder indicate less than 2 counts per second
- c. Count Rate recorder up scale - occurs should the recorder indicate greater than 50,000 counts per second 2 Linear Channel Reverse trips occur for any of the following conditions:
- a. Linear recorder off I
- b. Linear recorder down scale - occurs when the linear recorder is less than 5% of full scale
- c. Linear recorder up scale - occurs when the linear recorder is greater than 95% of full scale
- 3. Gamma Channel Reverse trip occurs for any of the following conditions:
- a. Gamma recorder off
- b. Gamma recorder down scale - occurs should the recorder indicate less than 0. 2mR/hr.
- 4. Any Scram condition will cause the control rod drives to drive i in the electromagnets.
- 5. Manual run-in trip- occurs upon actuation of the "Run-In" switch on the control console.
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- 8. 0 ELECTRIC POWER 8.1 Introduction The MCZPR is a teaching and training reactor presently licensed to operate at only O I watt. It is not used to generate electrical power.
- 8. 2 Offsite Power System During operation, the electric power requirements for t'#e MCZPR are supplied by the Consolidated Edison Company of New York which services Manhattan College. The reactor facility requires 110 Volt AC at 60 cycles.
Since the system is fail safe, no auxiliary power is needed for the operation of post-shutdown safety systems. The loss of electrical powerdraws out the scram relays and de-energizes the current in the electromagnets causing the control rods to drop under gravity completely into the core. Therefore, there is no need to consider offsite sources for emergency power.
- 8. 3 Onsite Power System Interruptions in power from the Consolidated Edison Company are very rare. Although any trip associated with a loss of power is inconvenient, such a loss of power has no bearing on the safe operation of the MCZPR
, system. When power is lost, the reactor automatically trips. Since such interruptions are usually of short duration, it has not been deemed necessary to install any secondary power systems.
8-1
i l 1
- 9. 0 AUXILIARY SYSTEMS 9.1 Fuel Storage and Handling 9.1.1 New Fuel Storage Due to the extremely low power rating of the MCZPR (O. I watt),
periodic fuel replacement is not necessary. Hence no built-in provision is made for the storage of new fuel. During 1965 the excess reactivity was reduced from 0. 3 percent to 0.29 percent with removal of three fuel plates from a partial ele ment. . These were: i Weight in grams Weight in grams Number (Element) (Isotope) HCF27 13. 16 12.27 HCF28 13.22 12,32 HCF29 13.30 12.40 These fuel elements are permanently stored in a locked steel container 8-1/4" X 8-1/2" X 50" made of 1/16 in steel sheet metal. The steel container is fastened to the floor of the first floor of the MCZPR Room. The container has a shelf welded inside it. The three fuel plates are placed on the shelf and secured with metal straps. The metal straps are welded to the shelf. The container has a hinged cover which is kept padlocked. 9,1. 2 Spent Fuel Storage The reactor does not generate any spent fuel that has to be replaced periodically. No provision is, therefore, provided for the storage of spent fuel. 9.1. 3 Temporary Storage of Fuel During Preventive Maintenance
- If fuel elements need to be removed from the core for purposes of preventive maintenance, they will be stored in their original Sylcor shipping containers on the first floor of the MCZPR Room. The removal and reloading of the fuel elements will be performed in the presence
; of a reactor supervisor.
- 9. 2 Water Systems
- 9. 2,1 Cooling Systems i The MCZPR does not have recirculating primary or secondary cooling systems.
9-1
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I l l 1 i 9.2.2 Demineralizing System The water in the reactor tank is demineralized by pumping water through a column containing demineralizing resin. Water is drawn through a 3/4" pipe attached to the only tank penetration located 2" from the bottom of the tank and returned back to the tank through a gooseneck pipe over the edge of the reactor tank.
~ 9. 2. 3 Water Make-Up System Water lost due to evaporation is replenished with city water. The water from the city water system is passed through an electrically controlled Versa checic valve, a Bantam demineralizer, a flow meter and a short flexible hose over the top of the reactor tank. The check valve prevents back flow. The flexible hose is removed from the tank when the hose is not in use.
I 9.2.4 Cathodic Protection
- A cathodic protection system is installed to reduce corrosion in the reactor tank. The system consists of four graphite rods attached to aluminum tubes. The rods are suspended in the reactor water by nylon filament, so that they are just outside the corners of the reactor plat-fo rm. The rods are maintained at -10V with reference to the reactor tank with the help of a packaged direct current power supply unit.
9.2.5 Potable Water No potable water connections are provided either in the MCZPR Room or in the Reactor IAboratory. 9.2.6 Sanitary Water No sanitary water connections are provided in the Reactor Laboratory. 2 A utility sink is located in Room 221 outside the MCZPR Room in the northwest corner of the second floor of the Reactor Laboratory. l 9. 3 Floor Drainage Systems . There are no floor drainage systems either in the first floor or in the second floor of the Reactor Laboratory.
- 9. 4 Ventilation System The Reactor Laboratory is provided with a forced circulating ventilation system consisting of a blower and associated duct work which are designed so as not to return air from the laboratory back into the ventilation system of the Leo Engineering Building.
l A separate blower cont rolled by a switch located on the west wall of the MCZPR Room returns air to the atmosphere. i ( 9-2
l
- 9. 5 Other Auxiliary Systems
- 9. 5.1 Fire Protection System l
A conventional fire protection system is located in the Leo Engineering ' Building. In addition, carbon dioxide fire extinguishers are available on both floors of the Reactor Laboratory. l 9.5.2 Communications System A full-service telephone is installed at the reactor console within easy reach of the operator at the controls. This provides direct communica-tion within the Leo Engineering Building, outside the building to other te?ephones ( on and off campus) and provides access to the Reactor Supervisor, Reactor Administrator, Health Physicist, and Radiation Safety Officer. [
- 9. 5. 3 Lighting System The Leo Engineering Building, including the MCZPR Room and the Reactor Laboratory, is provided with overhead fluorescent lighting. All switches are inside the Reactor Laboratory.
4 4 9-3
10.0 STEAM AND POWER CONVERSION SYSTE_M The Manhattan College Zero Power Reactor operates at a maximum ) power level of 0. I watt. The reactor produces no steam or l electrical power and has no working fluid cycle. The power generation is absorbed by the water pool and can produce cnly a small temperature rise, insufficient to produce steam. T k e 10-1 l
. _ _ _ _ . - . . . _ _ . . _ - _ _ . - _ . _ . _ . . _ . _ . . . _ . _ _ . _ . _ , _ _ _ , _ . . - . . _ . . . _ . . . . _ _ _ . . . ~ . .
r-11.O RADIOACTIVE WAS'IE MANAGEMENT Because of its low operating power level (O. Iw maximum) and its design characteristics the Manhattan College Zero Power Reactor does not generate radioactive waste ordinarily produced by test reactors. The extremely low operating power does not result in significant fuel burnup, and thus it is not anticipated that it will ever be necessary to add additional fuel to the reactor or to remove and ship irradiated fuel elements for reprocessing. In addition, no radioactivity in the form of gases is found within the reactor facility so that there is no gaseous release to the surroundings. At the operating power level the water shield is ample to attenuate
- the maximum fission product activity.
, The following procedures are in effect to handle any small quantities l of solid or liquid waste that may be generced as a result of the laboratory experiments performed on the reactor. 11.1 Waste Disposal Criteria No radioactive effluent is released at any concentration and no waste is disposed of except as authorized by the Reactor Operations Committee. In any event, only concentrations at or below maximum permissible levels listed in Appendix B of 10 CFR20 in air and water would be allowed to escape continuously to the local environment. 11.2 Accumulation of Active Wastes
- 11. 2.'1 Dry Waste Cans marked CONTAMINATED WASTE, COLD WASTE and CONTAMINATED GLASSWARE are to be provided as needed. These cans are polyethylene-lined and are not filled so as to prevent closure of the polyethylene bag liner. They are foot-operated in order to reduce the possibility of spread of contamination by handling the lid.
Extreme care is exercised in keeping contam'nated waste out of the cold waste cans, and vice versa. - The cans are monitored regularly by the staff Health Physicist and marked with the normal radiation sign if the radiation field is greater than 2. 5 mR/hr at any point outside the can. Persons placing material in the can which has sufficient activity to produce auch a field must notify the Health Physicist.
- 11. 2. 2 Liquid Waste
. Five-gallon polyethylene bottles marked CONTAMINATED WASTE are provided as needed.. Liquid waste is kept in these containers and not mixed with other waste. A detailed record of the nature of the liquid and the amount and type of activity in the container is kept by the appropriate person. Physicalinventories are requested as needed. 11-1
l I l l 11.3 Waste Transfer The transfur and disposal of all radioactive wastes (if made) is supervised by a Health Physicist in accordance with policies adopted by the Reactor Operations Committee. Transfer and disposal of such wastes are not made without the knowledge and approval of the Health Physicist. The Health Physicist monitors all such wastes and decides on the appropriate method of disposal. Solid wastes found in contaminated waste cans will be packaged for off-site disposal. Liquid waste will be transferred to 50-gallon drums for storage, concentration and subsequent off-site disposal by a licensed q waste disposal contractor in accordance with current manufacturing
- and shipping requirements.
The Health Physicist keeps complete records of the condition and j location of all radioactive waste in storage and of final disposition thereof. 11.4 Disposal of Pool Water and Demineralizer Resin The pool would not be drained until the water has been assayed and shown to be at or below tolerance as specified in 10CFR20. The Health Physicist must be notified in advance as to this action. The deminerali'.er is a concentrator of radioactivity, notably short-lived Na-24 and Mg-27. Used resin can never be replaced without . Health Physicist coverage and notification. If assay of the resin shows it to be radioactive it will be disposed of in accordance with 10CFR20 , par. 20. 305, 304. It is not anticipated that this situation will arise. 11.5 Surveys 11.5.1 Wipe samples of the floor and such other areas as selected by the
- Health Physicist and/or the Chief Reactor Supervisor are performed.
l The floor areas include the ZPR, graphite, counting and lecture rooms as well as connecting corridors and upper level desk areas. Normally this is performed at six month intervals. 11.5. 2 Air sampling is taken of the areas considered in 11. 5.1 above. Samples are taken at a rate of at least 2. 5 cubic feet per minute for 1/2 to I hour at each location. Normally this is performed at six rnonth intervals. i i 11-2
J i
- 11. 5. 3 ZPR water is checked at six month intervals. This procedure is accomplished employing a multi-channel analyzer or a scintillation spectrometer. Air and water samples of the reactor area are obtained prior to operation of the reactor. T12ese are the control values. These values are then employed and used for comparison purposes of air and water samples taken at the conclusion of each semester in which the reactor has been operational.
If Iodine-131 is found, . Reactor Operator and the Health Physicist will be notified immediately. 11.6 Protective Supplies A supply of plastic bags are on hand at all times in the counting room. A supply of radiation tape is also maintained. 11.7 Logs The Health Physicist maintains a bound log book. These logs are maintained:
. radiation surveys
, wipe records
, air and water tests i
11-3 _ . ._ _ _ _ _ . _ _ . ~ . - . _ - _ - _ _ . _ . . - - . _ . - . _ . _ - . _ . _ _ _ _ _ _ _ _ _ _ _ _ . - . - _ _ _ . _ . _ _ . . _ _ . . - -
l 12.0 RADIATION PROTECTION Manhattan College is committed to conducting reactor operations and associated experimental activities in a manner that assures the protection of all individuals, both on-site and in the surrounding environs. Radiation protection is carried out in a manner that is consistent with the applicable rules and regulations of the Nuclear Regulatory Commission and the State and City of New York, and with the specific conditions defined in our Special Material and Facility Operating Licenses. The radiation protection program is based on the following premises:
- The College has a moral obligation to maintain personnel health and safety with respect to all radiological ordinances.which can never i be compromised.
f-l - The Manhattan College Zero Power Reactor (MCZPR) is inherently safe because of its low power operation and built in design features
- There is a need to inculcate reasonable and proper Health Physics procedures by requiring students to know and follow these regulations
.- Personnel safety must be the first consideration at all times, and no requirements will be allowed to override safety considerations
- An ALARA ( As Low As ReasonablyAchievable) program will be conducted in accordance with federal (NRC) guidelines The components of the Manhattan College radiation protection program relevant to the operation of the reactor are discussed in the following sub-sections.
12.1 Health Physics Program The objectives of the Manhattan College radiation protection program are accomplished through the implementation of the components of a health physics program. The primary purposes of this program are to assure the radiological safety of all College personnel, and to make certain that all sources of radiation are handled in accordance with Federal, State, and City Regulations. A Radiation Safety Manual (the complete text of the Radiation Safety Manualis included as Appendix A: much of Section 12. is drawn from the Manual) has been prepared that describes the components of the y health physics and related ALARA programs (section 12. 2). The Manual ) guides the activities of faculty members and students using the Reactor, the supporting radiation facilities,and radioactive materials in the Nuclear Engineering Facility. 12-1
l \ l The procedural and radiation safety aspects of the Zero Power Reactor and isotope program are administered by a Reaccor Operations Committee (ROC). The ROC, which is chaired by the ' Reactor Administrator, receives and evaluates all proposed operations and procedures in order to insure that the reactor facility is operated in a safe and competent manner. An appointed Radiation Safety Officer (RSO) is responsible for enforcement of the rules, regulations, and operating procedures which conform with the NRC regulations (i.e. 10CFR Part 20) and the license conditions. The specific safety responsibilities of the ROC and RSO relative to the ALARA program l are described in section 12.2. The services of a consulting Health Physicist are also employed to provide advice to the ROC and RSO in insuring radiation safety. 12.2 Insuring That Occupational Radiation Exposures Are As Low As l Reasonably Achievable (ALARA)
- 12. 2.1 Administration The Administration of Manhattan College and the Manhattan College Nuclear Engineering Facility are committed to the program described below for keeping exposures (individual and collective) as low as reasonably achievable (ALARA). In accord with this commitment, and as noted in section 12.1, an administrative organization for radiation safety has been established, and new written policy, procedures and instructions to foster the ALARA concept within our
- institution are being implemented. The organization includes _the Reactor Operations Committee (ROC) and Radiation Safety Officer (RSO).
A formal annual review of the radiation safety program, including ALARA considerations is required. This includes review of operating procedures and past exposure records, inspections, etc. , and cor.sultations with the radiation protection staff or outside consultants. Modification to operating and maintenance procedures and to equipment and facilities will be made where they will reduce exposures unless the cost, in our judgement, is considered to be unjustified by the benefits produced. We will be able to demonstrate, if necessary, that improvements have been sought, that modifications have been considered, and that they have been implemented where reasonable. Where modifica-tions have been recommended but not implemented, we will be prepared to describe the reasons for not implementing them. 12-2
i s In addition to maintaining doses to individuals as far below the limits as is reasonably achievable, the sum of the doses received by all exposed individuals will also be maintained at the lowest practicable level. It would not be desirable, for example, to hold the highest doses to individuals to some fraction of the applicable limit if this involved exposing additional people and significantly increasing the sum of radiation doses received by all involved individuals. 12.2.2 Reactor Operations Committee (ROC) Review of Proposed Users and Uses The ROC thoroughly reviews the qualifications of each applicant with i respect to the types and quantities of materials and uses for which he has applied to assure that the applicant is able to take appropriate measures to maintain exposure ALARA. When considering a new une of byproduct material, the ROC reviews I the efforts of the applicant to maintain exposure ALARA. The user should have systematized procedures to insure ALARA, and shall have incorporated the use of special equipment in his proposed use.
- The ROC insures that the user justifies his procedures and that dose will be ALARA (individual and collective).( The judicious delegation of ROC authority is essential to the enforcement of an ALARA program).
The ROC delegates authority to the RSO for enforcement of the ALARA conce pt. The ROC supports the RSO in those instances where it is necessary for the RSO to assert his authority. Where the RSO has been overruled,- the Committee records the basis for its action in the minutes of the Committee's semi-annual meeting. Review of ALARA Program The RSO encourages all users to review current procedures and develop new procedures as appropriate to implement the ALARA concept. The RSO performs a review of occupational radiation exposure with particular attention to instances where Investigational Levels in Table 12.1 (below) are exceeded. The principle purpose of this review is to assess trends in occupational exposure as an index of the ALARA program quality and to decide if action is warranted when Investigational Levels are exceeded. The RSO evaluates the Nuclear Engineering Facility's overall efforts for maintaining exposures ALARA on an annual basis. This review includes the efforts of the RSO, authorized users, and workers as well as those of the Administration of Manhattan College and the Nuclear Engineering Facility. 12-3
- 12. 2.3 Radiation Safety Officer (RSO)
Annual and Quarterly Review Annual Review of the Radiation Safety Program. The RSO performs an annual review of the Radiation Safety Progra for adherence to ALARA concepts. Review of specific procedures may be conducted on a more frequent basis. Quarterly review of Occupational Exposures. The RSO reviews at least quarterly the external radiation exposures of authorized users and workers to determine that their exposures are ALARA in accord-ance with the provisions of Paragraph 12.2. 6 of this program. Quarterly review of records of Radiation Level Surveys. The RSO reviews radiation levels in unrestricted and restricted areas to determine that they were at ALARA levels during the previous quarter. EducationResponsibilities for an ALARA Program The RSO schedules briefings and educational sessions as needed to inform workers of ALARA program efforts. The RSO assures that authorized users, workers and ancillary personnel who may be exposed to radiation will be instructed in the ALARA philosophy and informed that- administration, the ROC and the RSO are committed to implementing the ALARA concept. Cooperative Efforts for Development of ALARA Procedures Radiation workers are given the opportunity to participate in formulation , of the procedures that they will be required to follow. ! The RSO is in close contact with all users and workers in order to
- develop ALARA procedures for working with radioactive materials.
, The RSO establishes procedures for receiving and evaluating the suggestions of individual workers for improving health physics practices and encourages the use of those procedures.
Reviewing Instances of Deviation frerrLGood ALARA Practices The RSO investigates all known instances of deviation from good ALARA practice s; and, if possible, determines the cau=es. When the cause is known, the RSO requires changes in the program to maintain exposures ALARA. 12.2.4 Authorized Users . New Procedures Involving Potential Radiation Exposures The authorized user is required to consult with, and receive the approval of, the RSO and the ROC during the planning stage before using j radioactive materials for a new procedure. l l i 12-4
The authorized user is also required to evaluate all procedures ; before using radioactive materials to insure that exposures will be l kept ALARA. This may be enhanged through the application of l trial runs. Responsibility of the Authorized User to Those He Supervises The authorized user is required'to explain the ALARA concept and his commitment to maintain exposures ALARA to all of those he supervises. The authorized user is required to insure that those under his supervision who are subject to occupational radiation exposure are trained and e ducated in good health physics practices and in maintaining exposures ! ALARA. 12.2.5 Persons Who Receive Occupational Radiation Exposure I- The on-site worker is instructed in the ALARA concept and its relationship to his working procedures and work conditions. The on-site worker is required to know what recourses are available if he feels that ALARA is not being promoted on the job. 12.24 Establishment of Investigational Levels In Order to Monitor Individual Occupational External Radiation Exposures The Manhattan College Nuclear Engineering Facility has established Investigational Levels for Occupational external radiation exposure which, when exceeded, will initiate review or investigation by the Reactor Operations Committee and/or the Radiation Safety Officer. i The Investigational Levels that we have adopted are listed in Table 12.1 below. These levels apply to the exposure of individuals. TABLE 12.1 Investigational Levels - (mrems per calendar quarter) ' LEVEL I LEVELU
- 1. Whole body; head and trunk: 125 375 active blood-forming organs; lens of eyes; or gonads 2 Hands and forearms; feet 1875 5625 and ankles .
i
- 3. Skin of whole body
- 750 2250
- Not normally applicable to nuclear medicine operations except j those using significant quantities of beta emitting isotopes.
l 12-5 _ - _ . _ _ _ _ _ _ - , . . _ - - - _ . _ _ _ - _ . . . . _ _ , ~ - . _ _ _ _ . - _ _ - . _ - . . _ . - _ - - . _ _ _ . . _ . . - _ -
The Radiation Safety Officer is required to review and record on , Form NRC-5, Current Occupational External Radiation Exposures, l or an equivalent form (e.g. dosimeter processor's report), results of personnel monitoring, not less than once in any calendar quarter. The following actions will be taken at the Investigations 1 L2vels as stated in Table 12.1: Quarterly exposure of individuals to less than Investigational Level I. Except when deemed appropriate by the RSO, no further action will be taken in those cases where an individual's exposure is less than Table 12.1 values for the Investigational Level I. Personnel exposures equal to or greater than Investigational Level I, but less than Investigational Level .T.I. The RSO will review the exposure of each individual whose quarterly . exposures equal or exceed Investigational Level I. He will report the results of his reviews at the first ROC meeting following the quarter when the exposure was recorded. If the exposure does not equal or
- exceed Investigational LevelII, no action related specifically to the exposure is required unless deemed appropriate by the Committee.
The Committee will, however, consider each such exposure in comparison with those of others performing similar tasks as an index of ALARA program quality and will record the review in the Committee minutes. Exposure equal to or greater than Investigational Level IL l The RSO willinvestigate in a timely manner the cause(s) of all personnel exposures equaling or exceeding Investigational Level II and, if warranted, take action. A report of the investigation, actions taken, if any, and a copy of the individual's Form NRC-5 or its equivalent will be presented to the ROC at the first ROC meeting following completion of the investigation. The details of these reports will be recorded in the minute s. Committee minutes will be sent to the administration for review. The minutes, containing details of the investigation, will be made available for review. Re-establishment of an individual occupational worker's Investigational Level II Above That Listed in Table 12.1 ( In cases where a worker's or a group of workers' exposures need to exceed Investigational Level II, a new, Higher Investigational Level II may be established on the basis that it is consistent with good ALARA . practices for that individual or group. Justification for a new Investigational Level II will be documented. l 12-6
The Reactor Operations Committee will review the justification for, and will approve, all revisions of Investigational Levels II. 4 In such cases when the exposure equals or exceeds the newly established Investigational Level II, those actions listed above will be followed. l l 12.3 Personnel Monitoring , During routine Reactor and Laboratory operations, external personnel monitoring is accomplished by the use of film badges. Reactor operations personnel normally working in the reactor rooms wear beta-gamma-neutron film badges; students entering the reactor rooms wear beta-gamma film badges; and visitors are required to wear film badges that record gamma radiation. Badges are processed by a commercial vendor, and records of personnel exposures are maintained in the reactor area. In the event that any significant internal exposure is suspected to have occurred, bioassays of urine samples may be required. If analysis of the sample verifies overexposure, followup medical examinations including blood analysis may be performed. An investigation of the cause of overexposure will be conducted, the situation remedied, and verified by the ROC. All personnel performing maintenance and alterations in an area of actual or potential radiation exposure are monitored, and area contamination surveys made to assure that no dispersal of radie-active material has occurred. Administrative controls (special work permits) are required for outside contractor personnel wrking in these areas. Survey meters, located in the ZPR room, are used for area monitoring, and for monitoring of hands and clothing of individuals, suspected of picking up some contamination during the course of experimental activitie s. 12.4 Other Radiation Protection Measures In addition to the program described in sections 12.1- 12. 3, other radiation protection measures are routinely performed at the Manhattan College Nuclear Facility. These include:
. All personnel using the Facility are instructed in radiation protection '
prior to participating in any of the activities at the Facility. All students are required to familiarize themselves with the provisions of the Radiation Safety Manual. 12-7
l
. Each area, room, or enclosure in which radioactive materials exist is posted with the specified radiation sign, as defined by Appendix B of 10CFR 20 or NBS69.
. No beverages, smoking, foodstuff, or application of cosmetica is permitted in radiation zones.
. Protective clothing (e. g. gloves) and tools (e. g. tongs) are employed to avoid contact between radioactive material and the skin.
. A contamination control program exists involving the use of designated container and labels, controlled and labelled storage, cleanliness and maintenance standards for laboratory surfaces, and procedures for cleanup of spills, and for decontamination of equipment and structural surfaces.
E i l 12-8
. . _ _ _ . . _ _ _ . _ . _ ~ . . _ . . .._ _ ._ _ . _ _ - _ . , .. ... _ _ _ . _ _ .
13.0 CONDUCT OF OPERATIONS 13.1.1 Organizational Structure of the Applicant The operation of the Manhattan College Zero Power Reactor (MCZPR) is supervised by the Manhattan College Reactor Operations Committee. The members of the Reactor Operations Committee report to the Reactor Administrator. With the issuance of Amendment No. 4 to
, Facility License R-94, Docket No. 50-199 on March 16, 1977, the Chairman of the Mechanical Engineering Department is constrained to serve as the Reactor Administrator. The administrative reporting ;
line from the Chairman of the Mechanical Engineering Department proceeds to the Dean of the School of Engineering, the Provost, the Executive Vice President, the President of Manhattan College, and the Board of Trustees of the Manhattan College Corporation. The Corpora-tion owns the facility and has fina11egal and financial responsibility for the operation of the facility. Figure 13,1 shows the Organizational Structure.
. The Chief Reactor Supervisor, Radiation Safety Officer, and Health Physicist both report to and are part of the Reactor Operations Committee.
They have collateral responsibility with the Reactor Operations Committee for the review and evaluation of all proposed operations and procedures in order to assure that the reactor facility is operated in a safe and i competent manner. 13.1. 2 Operating Organization, Reactor Operations Committee The Reactor Operations Committee and its members have primary responsibility for the evaluation of the operations of the facility. The membership of the committee includes the Radiation Safety Officer, the Health Physicist, the Chief Reactor Supervisor, and all subordinate Reactor Supervisors, Reactor Operators, and Reactor Trainees. Because the primary purpose of the facility is to aid undergraduate instruction in nuclear engineering, lecturers in the nuclear engineering courses are also appointed members of the committee. Appointments of the Radiation Safety Officer, Health Physicist, Chief Reactor Supervisor, subordinate Reactor Supervisors and other members of the Reactor Operations Committee are made by the Reactor Administrator. The Reactor Operations Committee meets semiannually and at other i times if deemed necessary by the Reactor Administrator. The semiannual meetings are held in the Spring and Fall semesters during the Manhattan l Co11sge academic year. A formal agenda is prepared by the Reactor Administrator and minutes of each meeting are written. The task of taking minutes is rotated; however the draft version is reviewed by.the Reactor Administrator prior to issuance to the committee for the next meeting. The agenda has been standardized and reflects the duties and I 13-1
responsibilities of the committee. Each item in the agenda is considered and noted in the minutes. Figure 13. 2 shows a sample agenda and the topics that are covered at a-meeting. The duties of the Reactor Administrator, Reactor Operations Committee, Radiation Safety Office Reactor Supervisor, Chief Reactor Supervisor, and Reactor Operators are described in the Technical Specifications which form a part of this license renewal request. The Health Physicist performs all radiation surveys and samples under the supervision of the Chief Reactor Supervisor and other tests as requested by the Reactor Administrator or members of the Reactor Operations Committee. He also is responsible for monitoring records of exposure on film badges, maintenance of a log book on radiation tests and exposure records, and for review of the reactor log book. More detail on his duties can be found in Section 12 of this license renewal request and the appended
" Radiation Safety Manual".
12.2 Training The Chief Reactor Supervisor and Reactor Supervisors must hold a Senior Reactor Operator's License issued by the U. S. Nuclear Regulatory Commission. Regular operators must hold either a Senior Reactor Operator's License or a regular Operator's License also issued by the U. S. Nuclear Regulatory Commission. Training of applicants for i service as operators of the Manhattan College Zero Power Reactor is performed as needed for maintenance of a sufficient number of on-campus etaff to assure the safe operation of the facility. A detailed plan " Plan for Training Applicants to Prepare for a Reactor Operator's License Examination for Manhattan College Zero Power Reactor" has been prepared and is appended to this license renewal request. Since reactor operator's licenses are issued by the U. S. Nuclear Regulatory Commission for only two-year periods, re-evaluation of the ability of operators to continue service at the facility is done every two years. All applications
~
for operator license renewals require an endorsement letter from the Reactor Administrator and are discussed at the semiannual Reactor Operations Committee meetings. All Senior Reactor Operators and Reactor Operators must participate in a continuing requalifica-tion program. The program is detailed in Appendix J. - 13,3 Emergency Planning An emergency plan for the facility has been prepared independently of this license renewal request and is appended to this request. The i plan follows the guidelines stated in Appendix E to 10CFR Part 50, U. S. N. R. C. Regulatory Guide 2. 6 (Revision 1, March 1983), and l ANS 15.16-1982. l l 13-2 l
'~ ~ ' -
13.4 Review and Audit
- The members of the Reactor Operations Committee collectively and individually through the duties of their appointed positions-review and audit the current and proposed uses of the facility. The primary purpose of the facility is, to assist undergraduate instruction in the undergraduate nuclear engineering sequence offered by the mechanical engineering department. This sequence includes a laboratory with some experiments that use the critical reactor. Except for operator training sessions and required tests, the educational function constitutes the primary purpose of the facility. As noted on Figure 13. 2, the review of experi-ments is an agenda item at each semiannual meeting. Figure 13. 2 also shows that reports on log book review, compliance with periodic require-ments, required documentation and licensing matters, safety procedures, I and changes in Technical Specifications are provided semiannually to the Reactor Operations Committee. The Radiation Safety Officer also performs review and audit functions as part of his duties pertaining to the ALARA program. The Health Physicist and Chief Reactor Super-visor perform review and audit of periodic requirements prior to reporting to the committee.
j 13.5 Plant Procedures The Chief Reactor Supervisor has prime responsibility for the day-to-day operating procedures within the facility. . He maintains a log book which includes the history of all periods of reactor operation, including startup, criticality, and shutdown. Figure 13. 2, item 4 shows the type of in'or- ! matio- which must be recorded. The log book is maintained in a locked cabinet in the facility with records kept indefinitely. Maintenance and inspection records are also recorded in this log. l The procedures for startup, operation, and shutdown are detailed on the
" Reactor Console Checkout Sheets". These are appended to this license renewal request. The " Reactor Console Checkout Sheets" are based on the more general description in the Technical Specifications.
The Health Physicist also maintains a log book in which records of all radiation surveys and film badge exposures are kept. This log is up-dated every six months or sooner if needed. The log book is maintained in a locked file cabinet in the facility. Procedures for radiation protection are described in more detailin Section 12 of this license renewal request and in the appended " Radiation Safety Manual". j~ 13,6 Physical Security Plan A physical security plan has been prepared and approved independently
- i. of this license renewal request and is appended to this request.
13-3
ORGANIZATIONAL STRUCTURE (Effective July 1,1983) MANHATTAN COLLEGE CORPORATION BOARD OF TRUSTEES F William F. Mitty, Jr. , Chairman i PRESIDENT OF THE COLLEGE t l Bro. J. Stephen Sullivan, F.S.C. I
EXECUTIVE VICE-PRESIDENT Bro. John A. Muller, F.S.C. - f I PROVOST j i Bro. Francis R. Bowe rs, F. S. C. l I DEAN OF THE SCHOOL OF ENGINEERING Dr. Joseph F. Lestingi REACTOR ADMINISTRATOR j Chairman of The Mechanical Engineering Department i Dr. Ronald S. Kane
- REACTOR OPERATIONS COMMITTEE
- RADIATION SAFETY OFFICER Dr. Joseph Augustus CHIEF REACTOR SUPERVISOR I Mr. Robert E. Berlin , Mr. Robert E. Berlin < Bro. C. Gabriel Kane. F. S. C.
j _ Dr. -Jih-Perng Hu l
' HEALTH PHYSICIST Bro C. Gabriel Kane, F. S. C. l REACTOR SUPERVISORS l j Dr. Stanley J. Malsky Dr. Stanley J. Malsky l Dr. Robert A. Mayo l REACTOR OPERATORS l l
5 Mr. Manouchehr Niknam ~ I ,i Figure 13. I 13-4 i
= . . ..- - n - 6 AGENDA OF SEMIANNUAL REACTOR OPERATIONS COMMIT':ZE MEETING Reactor Operations Committee (Date)
- 1. Approval of Agenda
- 2. Approval of Minutes of (previous meeting date)
- 3. Committee Membership 4 Log book review a) Time duration of irradiation of Indium foils b) Signature of approval for irradiation c) Completeness of all entries relative to criticality d) Time and modes of shut-down of reactor 1
e) Time of securing reactor f) Hourly instrument recording during period when reactor is critical i 5. Check compliance with periodic requirements a) Periodic radiation survey b) Emergetcy procedures review (annual review in October) c) Scram time measurement (verification every 6 months and prior to operation of the facility if the facility is shut down for 2 months or more) d) Reactor moderator sample analysis (done each semester) e) Sample check for hold down rods I f) Calibration of survey instruments (annual calibration in October) g) Leak tests on plutonium sources (semi-annual tests in April and October) h) Material irradiation other than indium
- 6. Old Business (as needed, typical items below) a) Required documentation for facility b) Inspection status c) Review of experiments d) Other radiation tests, badges e) Student safety procedures, non-nuclear safety, access f) Budget items g) License status h) Unanswered or other correspondence i) Equipment or other acquisitions
- 7. Changes in Technical Specifications (if any) 8 New Business t
Figure 13. 2 13-5 e- - v-- ,-,,,,-r-me-~v w,,-, .,* --,-w,,,,,-r,-
, - - ---,,v w ,.-nw-,,,-.e,- - see,- e-e-e-e-e-.-----,- n-------v -, ,, -- w , es-,4,- ww--,m--a --------,v--w ww---e-,-
l__._.__u. 14.O INITIAL TEST PROGRAM Since the reactor has been licensed and in use since 1964, an initial test program is not needed for the purposes of this renewal reque st. Test programs will be developed as necessary, if operational changes are planned for the future.
14-1
15.0 ACCIDENT ANALYSIS 15, 1 Introduction This chapter discusses the response of the MCZPR facility to postulated disturbances to process variables and to postulated malfunctions and/or failures of equipment, and their effect on the safety of the facility. 15.2 Nuclear Excursions It is difficult to visualize any circumstances which would result in a reactivity increase of a magnitude sufficient to cause serious degradation of the core of this reactor. The maximum excess reactivity at the MCZPR is a very low 0. 29%. Nuclear excursions j during operation and during fuel loading may be postulated.
- 15. 2.1 Three possible methods of introducing maximum excess reactivity during operation may be visualized.
- 1. All the circuits of the reactor protection system were to fail simultaneously, and the operator withdraws both control rods completely. This is extremely unlikely to happen.
I
- 2. The operator deliberately withdraws both rods completely allowing the reactor to operate at a power level that would exceed the maximum allowable limit of 0. I watt.
Such behavior on the part of an operator is very unlikely to occur. In addition, the presence of a Reactor Supervisor, as required by the operational procedures, will prevent the occurrence of such an event.
- 3. A sample having very high cross section could be inserted into the core and both control rods could be withdrawn completely without exceeding the allowable power limit. If the sample is withdrawn without reinserting the control rods, maximum excess reactivity could occur.
l All experiments performed in the reactor are very closely monitored by the Reactor Operations Committee. No new experiment involving the reactor is allowed to be performed without the express approval of the Reactor Operations Committee. Thus, the. insertion of maximum excess reactivity during an experi- [. ment is unlikely. i 15 2.2 Nuclear Excursion During Fuel Loading Fuel replacement in the reactor at any reasonable time in the future l is not needed due to the very low power (O. I watt maximum) and the infrequent use of the reactor. However, if removal of fuel and l L 15-1
subsequent replacement is needed for purposes of maintenance, , the personnelinvolved will be under the supervision of a Reactor Supe rvisor. Nuclear excursion during this process (if it were
. needed) is unHkely.
15,3 Effects of Rapid Reactivity Insertion The rapid insertion of maximum reactivity could produce a power level of 147 KW. This was demonstrated in calculations submitted to Mr. Marvin K. Woodard, Division of Licensing and Regulation, dated October 6,1966. This communication is given as . Appendix G. 15.4 Loss of Coolant Accident There is no recirculating coolant system in the reactor. Any leaks from the tank would lower the water level which in turn would activate the " Low Water Level Scram" circuit shutting down the reactor.
- 15.5 Fission Products Release The MCZPR is designed to operate at a maximum power of 0. I watt.
3 The chances of the fuel elements melting and releasing fission products are very low. 15.6 Radiation Dose for the Maximum Hypothetical Accident The radiation dose for the maximum hypothetical accident was computed to be 18. 5 roentgens at the water surface above the core center line as reported to Mr. Roger S. Boyd, Research and Power Reactor Safety Branch, Division of Reactor Licensing as part of the communication dated November 15, 1966. This communication is reproduced here as Appendix H. It is noted that these results are l unchanged as a result of confirming excess reactirity measurements I made in 1967 for the MCZPR. The results of these tests are given in Appendix I. I 15.7 Conclusion The chances for an accident are very low at the MCZPR. Even if a l maximum credible accident is hypothesized, the effects are not ,. severe. r l l l l l
I I 15-2
16.0 TECHNICAL SPECIFICATIONS Section 50.36 of 10 CFR Part 50 requires that each operating license issued by the Nuclear Regulatory Commission contain Technical Specifications that set forth the limits, operating conditions, and other requirements imposed on facility operation for the protection of the health and safety of the public and other reasons. The Manhattan College Zero Power Reactor was licensed by the Atomic Energy Commission on March 24, 1964 under Facility License R-94. On the same day, the AEC approved the Technical Specifications for the Manhattan College Zero Power Reactor as an Appendix to Facility License R-94. Five amendments to the Facility License and eight changes in the Technical Specifications have been approved by the Atomic Energy Commission and the Nuclear Regulatory Commission since March 24, 1964. All of these changes have been incorporated into the Technical Specifications presented in this section. 16-1
l 1 16.O TECHNICAL SPECIFICATIONS FOR THE MANHATTAN COLLEGE ZERO POWER REACTOR 9 16-2
o ..._ TABLE OF CONTENTS Page A. Site 16-5 B. Building 16-5 C. Ventilation 16-6 D. Radiation Monitoring 16-6 E. Administration and Procedural Safeguards 16-7
- 1. Introduction 16-7
- 2. Reactor Management 16-7
- a. Organization 16-7
- b. Description of Duties 16-7
- 3. Operating Standards 16-11
- a. Operation Limitations 16-11
- b. Operating Personnel Requirements 16-11
- c. Fuel and Experiment Loading, 16-12 Personnel Requirements
- d. Records 16-13 l 4 Operating Procedures 16-13
- a. Checkout Procedures 16-13
- b. Startup and Operation 16-13
- c. Reactor Shutdown 16-14
- d. Use of the Reactor 16-14
- 5. Emergency Procedures 16-16 F. Design Specifications of Reactor 16-16 l G. Core Parameters 16-19 i
H. Nuclear Instrumentation 16-19 I. Safety System 16-21 1, Scram Circuits 16-21 j 2 Reverse Circuits 16-21
- . 3. . Bypass in Safety System 16-22 l 4. Scram Times 16-22 J. Operating Limits 16-23 l
l 16-3
Page Figure 1. MCZPR Laboratory 16-24 Figure 2. Table of Organization 16-25 Figure 3. Fuel Element Detail 16-26 l- Figure 4. Control Rod Assembly 16-27 Figure 5. Grid Plate Stand (Plan View) 16-28 Figure 6. Grid Plate Stand (Section View) 16-29 Figure 7. Grid Plate 16-30 i l l l l i 16-4
l A. Site l
- 1. The Manhattan College Zero Power Reactor (MCZPR) is located in the Leo Engineering Building of Manhattan College at 3825 Corlear Avenue, New York City, New York.
- 2. The laboratory room where the reactor is located (described in section B. 2. ) is considered a restricted area as defined in paragraph 20. 3 (a),14, of 10 CFR 20.
- 3. The principal activities carried on within the site are those related to the educational program of Manhattan College.
The reactor may be utilized in this program for instructional use and may be used in. experiments as described in ( seetion E. 4. d. l B. Building
- 1. The Leo Engineering Building of Manhattan College is a four story, brick building providing space for Engineering and Science Laboratories. The building provides classrooms, computer facilities, and laboratories for an estimated 1800 students at any one time, as well as office space for the Dean of the School of Engineering, chairmen, and faculty members using the building.
- 2. The laboratory housing the Manhattan College ZPR is completely separated from the remainder of the Reactor Laboratory as l shown in figure 1. Security locked doors provide the only access I
to the Reactor Laboratory.
- 3. The MCZPR laboratory has the following penetrations:
- a. Eleetrical conduits
- b. Air circulation system
- c. Door
- d. Window 4 The MCZPR is located in the laboratory as shown in figure 1.
l The reactor tank shall rest on a concrete slab in the first floor ! and shall extend upward through the second floor. The first floor L room housing the reactor shall have concrete walls extending from the floor to the ceiling on three sides and a metal partition from the retainer wall to the ceiling on the fourth side. The only access to the reactor from the first floor shall be through a metal door which shall penetrate the metal partition as shown on figure 1. The metal door shall be kept locked at all times when there is fuel in the reactor. The only access to the first i t
-e- - - , ~ , - , ~ ~ ~ > -- , - - , --- ,,
I .- .. . . floor of the MCZPR room when fuelis in the reactor
- shall be through a trap door in the reactor platform and )
down a vertical steel ladder adjacent to the reactor tank.
- 5. The reactor platform, described in section F.11, shall be located on the second floor above the tank whenever fuel is located in the reactor. The platform shall be surrounded by a link fence to prevent personnel from inadvertently approach-ing the open areas in the platform.
- 6. In addition to the concrete walls extending from floor to ceiling on three sides of the first floor room housing the reactor, a concrete berm has been constructed on the fourth side sufficiently i- high to contain all the water in the reactor tank.
- 7. The window to the MCZPR Laboratory shall have a window guard to prevent unauthorized entry into the room, and the door into l the facility shall be locked whenever a reactor operator is not
in attendance in the room.
- 8. During times when an operator is not in attendance in the
MCZPR Laboratory, the building shall be under the periodic . surveillance of members of the faculty or the campus security fo rce. C. V_ entilation i
- 1. The MCZPR Laboratory shall contain a forced circulating ventilation system consisting of a blower and associated i duct work. There shall be no connection between this system and any other part of the Leo Engineering Building.
- 2. A switch shall be provided in the reactor room to turn the ventilation system on and off.
D. Radiation Monitoring -
- 1. Two radiation monitoring channels shall be provided to measure gamma intensity. These channels shall also be used to monitor reactor operation and shall be used in the reactor safety system as described in Section I. A common strip chart recorder shall be provided with a selector switch for recording the output of either channel.
- 2. Each channel consists of a Gamma Detector and Gamma
! Indicator Unit. l 3. The Gamma Detector shall be a sealed unit containing a l Geiger-Mueller tube, transistorized count rate amplifier, and check source. The output from the Detector shall be logarithmic l 16-6
with respect to the radiation level. The check source shall be exposed to the Detector by a solenoid which is actuated by a pushbutton on the control chassis.
- 4. One of the Detectors (Gamma 1) shall be located on the reactor platform directly over the core area while the other Detector (Gamma 2) shall be mounted on the side of the reactor tank.
- 5. The Gamma Indicator shall contain the power supply for the system, the alarm reset check source control, and the output I connector for the Detector. Also contained on the front of the Indicator is a logarithmic meter relay for indication and alarm of the gamma level. The alarm shall be set to give audible annunciation whenever the radiation level exceeds 6mR /hr for Gamma 1 and 10 mR/hr for Gamma 2.
1
- 6. The range of both detectors shall be from . 01 to 100mR /hr.
The system shall be designed so that if the radiation intensity is greater than 100rnR/ hr the detector shallindicate full scale. ' Administration and Procedural Safeguards E.
- 1. Introduction The specifications pertaining to the management of the facility ,
and the operating standards and procedures to be used during startup, operation, and refueling of the reactor are in this section. Unless expressly excepted all operations of the reactor shall be in accordance with the provisions of all sections of ! these technical specifications. As used in these technical speci- ! fications, reactor operation shall include all actuation or mani-pulation of the reactor control and instrumentation systems while fuel is in the reactor tank, movement of reactor fuel or other components or apparatus within the .mactor tank, conduct l of experiments, and maintenance. 2 Reactor Management
- a. Organization The personne1 organization as shown on Figs re 2 shall
be in effect in order to insure safe operation of the l reactor. A staff member shall be assigned to each position to assume responsibility in each functional area. The duties and responsibilities in each area shall be as i follows.
- b. Description of Duties l (1) Reactor Administrator will provide final policy <
decisions on all phases of reactor operation and on regulations for the facility as a whole. He 16-7
will be advised in all matters concerning the safe operation of the reactor by the Reactor Operations Committee. The Reactor Administrator shall be responsible for the overall administration and supervision of the reactor facility. He shall appoint qualified members to the Reactor Operations Committee from time to time as necessary. He ' shall designate Reactor Supervisors and name the Chief Reactor Supervisor. The Reactor Administra-tor shall approve and promulgate all regulations, instructions, and procedures governing the operation of the reactor facility. (2) Reactor Operations Committee shall be responsible to the Reactor Administrator for the review and evaluation of all proposed operations and procedures t in order to insure that the reactor facility shall be operated in a safe and competent manner. Particular
- emphasis shall be placed on the examination of new and untried operations and procedures, and the Committee shall take action on all new experimental plans. The Committee shall review and evaluate all t proposed changes in the experimental plans which involve' changes in the reactor system. The Rea-tor Operations Committee shall advise on and be available for advice and assistance on any problems relative to the safe operation of the reactor facility.
(3) Radiation Safety Officer shall be responsible for the promulgation and enforcement of rules, regu-lations and operating procedures which conform with the regulations set forth in 10 C FR, Part 20. The Radiation Safety Officer in conjunction with the Reactor Operations Committee shall approve l suggested procedures for the purchase, possession, storage use and disposition of all radioisotopes, l consistent with general or specific licenses for use of by-product material issued by the Commission to Manhattan College. The Radiation Safety Officer l in conjunction with the Reactor Operations Committee, shall be available for advice and assistance on problems involving radiological safety arising from l the operation of the reactor facility. The Reactor Operations Committee shall evaluate and approve all proposed procedures leading to the production of l 16-8
l l l 1 radioisotopes with a half life longer than one (1) hour. All operations leading to the production of more than one (1) millicurie of radioactivity, with any half life, must receive prior approval of the Reactor Operations Committee. (4) Health Physicist shall be responsible for monitor-ing records of exposure on film badges, mainten-ance of a log on radiation tests and exposure records. He also shall review the reactor log. Periodic radiation surveys of the critical reactor laboratory, the suberitical laboratory and the counting room, and other areas where radioactive materials are being used, shall be made by the Health Physicist under the direction of the Chief Reactor Supervisor. The Radiation Safety Officer l shall be notified if an abnormal radiation problem is encountered. Results of these surveys shall be recorded or filed in the log. The Health Physicist shall also be responsible for proper disposal of sample s and radioactive materials. (5) Reactor Supervisors shall be appointed by the
. Reactor Administrator. These individuals shall have general competence in reactor technology and associated fields. Each supervisor shall hold a senior operator's license issued by the Nuclear Regulatory Commission. The Reactor Supervisors shall be responsible to the Reactor Administrator, through the Chief Reactor Supervisor, for the preparation and submission of complete detailed proposed experimental procedures, regulations and administrative rules to insure the maintenance, safe operation, proper and competent use, and security of the reactor equipment. Appointment as a Reactor Supervisor shallin all cases be accompanied by appointment to the Reactor Operations Committee.
The Reactor Supervisors shall be responsible for - the preparation and submission of operating schedules of the reactor facility, and shallinsure that all activities and experiments involving the facility conform to both local and Commission regulations. They shall establish in coordination with the Reactor Operations Committee, procedures 16-9
I for experiments to be performed with the ' reactor. They shall establish procedures and be responsible for the keeping of adequate, complete and currently accurate records for the operation and maintenance of the facility. A Reactor Supervisor shall be in charge of the facility and, except as provided in E. 4. d. (1), , shall witness the startup and intentional shutdown procedures. In addition, he shall be responsible for prompt execution of emergency procedures. (6) Chief Reactor Supervisor shall hold a valid senior operator's license issued by the Commission. He shall be responsible for the promulgation and enforcement of administrative rules, regulations and operating procedures. He shall inform the Reactor Operations Committee of any unusual operations proposed to be performed on the reactor, or any proposed changes in procedure. He shall not authorize the operation or proceed with the proposed changer until appropriate evaluation and approval has been made by the Reactor Operations Committee, and authorization given by the Reactor Administrator. The Chief Reactor Supervisor shall have the authority to authorize any experi-ments or procedures which have received prior (- approval of the Reactor Operations Committee. He shall be directly responsible for enforcing i operating procedures and insuring that the reactor L facility is operating in a safe, competent and authorized manner at all times. In addition, he shall be directly responsible for the preparation, authentication and storage of all prescribed logs and operating records. (7) Reactor Operators shall hold a valid operator's license issued by the Commission. They must conform to the rules, instructions and procedures for the start-up, operation, and shut-down of the reactor facilities as set forth in Section 4 a,b, e l of the Technical Specifications. They must also conform to the specifications of the Emergency Plan for the Zero Power Reactor. Within the constraints l of the administrative and supervisory controls out-l 3 16-10 l-
- i. -_ _.- _ . _ _ _ , _ _ _ _ . _ _ . . _ . _ - . - _ - . _ _ _ _ _ , _ - _ - , _ _ . _ . - - _ , . . _ -
lined above, a reactor operator shall be in charge of the control console at all times that the reactor is operating. The reactor operator shall be required to maintain complete and accurate records of all reactor operations in the operational logs. All personnel using the facility shall be instructed in the hazards involved, and given a copy of the laboratory regulations concerning use of radioactive material. All personnel working in the vicinity of the reactor ahall wear film badges.
- 3. Operating Standards The basic premise of all proposed operating standards is the safety of the reactor, its operating personnel, and the immediate surroundings.
- a. Operation Limitations (1) All operations which are conducted with fuel in the core, and that may change core reactivity, shall be conducted in accordance with approved 7 written instructions.
(2) Whenever fuelis present in the core tank and a
;
reactor operator is not in attendance, the control ! console shall be off and locked; if no one is in attendance, the ZPR Laboratory door shall also be closed and locked. The key to the reactor key switch shall be in the possession of a reactor superviso r. ( l b. Operating Personnel Requirements (1) The controls of the reactor shall be operated only (the reactor controls are to be regarded as operating if the " Reactor On" switch is turned to "ON" and fuel is present in the core tank) with the specific authorization of a reactor supervisor. The reactor operator shall be responsible for obtaining the authorizing signature of a reactor supervisor at the top of the checkout sheet. The reactor supervisor signing the authorization is j the supervisor " in charge". ( - 16-11 i _. _ _~ _ . _ . . . . _ _ _ . _ _ _ - _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ . - . _ _ _ _ _ _ _
(2) Whenever the reactor controls are operated, a licensed reactor operator shall be present and in - the immediate vicinity of the console. An up-to-date list of licens,ed reactor operators will be posted near the reactor console. A person is considered "present" if he is in the console room within view of the instruments on the console. (3) A Reactor Supervisor shall be present in the Leo Engineering Building at all times that the reactor controls are operated and shall be cognizant of the reactor operation at all times. If the supervisor in charge of the operation must leave the building, the reactor controls must either be turned off and locked or another supervisor must accept responsi- , bility. The reactor operator shall be informed of l such a transfer of authority. A list of Reactor l Supervisors will be posted near the reactor console.
- c. Fuel and Experimental I.cading, Personnel Requirements (1) Any movement of fuel elements or of materialinto or out of the reactor core can be done only on specific written authorization of or in the presence of a reactor supervisor.
(2) At least two persons, one a licensed reactor ope rato r, shall be in the ZPR laboratory when any fuel elements or any experiment is moved in the reactor core. One person shall be at the reactor console. (3) Whenever the final fuel element necessary for attainment of criticality is transferred into the j_ core, a reactor supervisor shall be present. ! (4) A reactor supervisor shall be present in the ZPR room during the loading of an experiment into the core for the first time, or its removal from the core. A supervisor shall be present in the ZPR room or give his written authorization for repetitive insertions of an experiment. Any object, other than a fuel element or handling tool, which is inserted into the volume formed by projecting the grid plate vertically to the tank surface, is to be regarded as an experiment in the core.
l l l 16-12
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- d. Records l (1) The reactor log shall consist of (1) completed checkout and operation forms, (2) completed fuel element transfer forms and (3) entries in the
. permanently bound log book.
(2) The following information shall be recorded in l the log: l (a) all changes in reactor instrumentation and equipment,- (b) all changes in the core, and (c) any unusual condition. t 4. Operating Procedures l Operating procedures for the facility shall be in accordance with j the following specifications: ! a. Checkoct Procedures (1) A check of the instrumentation shall be made prior to reactor operation on each day that the reactor is to be started. The checkout procedure shall be designed to show the presence of a malfunction in any of the safety circuit or interlocks, to test the response of the log N, linear, and area radiation meters, to check the scram levels, and to determine whether any unusual condition exists. A standard form to be followed shall be provided by the laboratory and becomes part of the reactor log. (2) In the event the checkout reveals any unusual condition of any instrument not functioning properly, the reactor operator shall inform the reactor superviso r,
- b. Startup and Operation (1) To start operations, the operator shall first turn on all instruments and recorders, marking the recorder chart to identify date and operator, and I
set the picosmmeter at its most sensitive on-scale ! range. The reactor key switch may then be turned on and magnet current may be established by
- pressing the RESET pushbutton. Magnet voltage shall be recorded. Warning shall then be made i
throughout the reactor area that the reactor is being started. i l i 16-13
i l (2) During operation with the reactor critical: !
- 1. Initial critical rod positions shall be recorded using the Fine Position Circuit; j 2 Readings of allinstruments shall be recorded hourly; and
( 3. Any unusual conditions shall be recorded.
- c. Reactor Shutdown (1) The reactor may be shut down by either running the i rods in under power by pressing the RUN-IN button or by intentionally testing the Linear Channel i High Flux or other scram circuits.
l. (2) The Linear Channel High Flux test may be performed
- by leaving the picoammeter on its existing range l and increasing the power level gradually until the trip level is reached.
- d. Use of the Reactor (1) Teaching Experiments All experiments except the following experiments for teaching purposes, shall be conducted in the presence of a Reactor Supervisor. The following experiments, while not requiring the presence of a Reactor. Supervisor, require the presence of a Reactor Operator.
! 1. Startup and Operation of Manhattan College Zero Power Reactor: Approach to Criticality
- 2. Critical Mass Determination i 3. Reactor Period and Reactivity 4 Void Coefficient Measurement
- 5. . Flux Distribution in the Manhattan College j Zero Power Reactor
- 6. Determination of Buckling
- 7. Measurement of Diffusion Length and Age i
- 8. Temperature Coefficient of Reactivity
- 9. Determination of Disadvantage Factor t
- 10. . Danger Coefficient Tests 1 1. - Gamma Ray Energy Spectrum in the Vicinity of the' Reactor Core i.
i
! 16-14
(2) Limitations on Experiments. Including Material Irradiations j
- 1. No experiment shall be installed in the l reactor in such a location that any part of ,
the apparatus will touch or in any way interfere with the action of the control rods. 2 No experiment shall be installed in the reactor that can shadow the nuclear instru-ments, thereby giving erroneous or un-reliable information to the reactor operator.
- 3. No experiment whichbas explosive properties shall be irradiated.
- 4. Experiments containing materials whose l release to the water could result in a violent chemical reaction (e. g. Sodium) or would result in chemical or corrosive attack to the reactor components (e. g. Mercury) sha11 not be irradiated.
- 5. Experiments containing materials whose release could result in overexposure of personnel to gaseous or particulat e radio-activity shall not be irradiated.
- 6. Each experiment, other than teaching experi-ments defined in E. 4. d. (1), shall receive the specific approval of the Reactor Operations Committee. In addition, all operations leading l
to the production of more than one millicurie of any radioisotope outside of fuel elements shall receive the approval of the Reactor Operations Committee.
- 7. A record of each materialirradiation must also be included in the reactor log. The record shallinclude at least the following data:
l
- i. Material irradiated ii. Position in core lii. Reactor Power iv. Irradiation time, time in, time out
- v. Dose rate on contact at time of removal vi. Supervisor's approval (signature) 1 16-15 l
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- 5. Emergency Procedures Written instructions governing emergency and evacuation procedures shall specify the necessary action to be taken in the l event of an emergency, such instructions shall be posted in easily accessible locations both inside and outside the ZPR room.
Personnel who are responsible for taking emergency action shall - be acquainte d with these procedures. The emergency procedures shall be reviewed at intervals of not more than once per year by the Reactor Operations Committee and shall be revised as necessary. F. Design Specifications of Reactor Whenever fuel is present in the ree.ctor tank, the facility design shall conform to the specifications of this section F. The reactor shall be heterogeneous, tank-type reactor moderated by light water. The principal components shall be the reactor vessel, core, control system, and the purification system. These components shall be as described below:
- 1. The reactor vessel shall consist of a cylindrical aluminum tank eight feet high and ten feet in diameter. The tank wall shall be one quarter of an inch thick. The' only tank wall penetration shall be a 3/4 inch diameter aluminum coupling located near the tank bottom with a 3/4 inch diameter short nipple and a 3/4 inch aluminum gate valve. The inlet to the demineralizer shall be connected to this gate valve. The outlet of the demineralizer feede into a pipe which shall rise vertically and form a gooseneck loop over the edge of the tank.
- 2. The reactor vessel shall be located as in Figure 1 and shall be
' held in place by five aluminum brackets welded to the sides of the tank near the bottom. These brackets shall be bolted to the concrete floor.
- l. 3. A grid plaite stand as shown in Figures 5 and 6 shall be welded j to the bottom of the reactor tank.
l
- 4. A grid plate shall be bolted to the grid plate stand. The design of the plate including attachments thereto shall be as shown in Figure 7. Fuel element hold down rods shall be threaded into the grid plate unless an approved experimental program requires their removal. The holes in the support cylinders for the incore fuel elements may be plugged.
l The shafts of these hold-down rods shall be made partly of ! aluminum and partly of lucite. The lucite portion shall consist l of a solid rod one inch in diameter. The threaded base of the l hold-down rod shall be made of aluminum tubing having a one-l eighth inch wall thickness. The broad top of the hold-down rod, l which extends over the top of the fuel element shall also be made of aluminum. The aluminum portions of the hold-down rod shall be securely fastened to the lucite by aluminum pins and epoxy cement.
- l. 1 6-16
l 5 The design of a fully loaded element shall be as shown on Figur? 3. The fuel portion of such elements shall consist of six concentric cylinders formed by mechanically joining and positioning eighteen curved fuel plates within grooves of
- 3 spacer webs. The fuel plates shall be mechanically held on the grooves by roll bonding; the bonding shall yield joint strengths of at least 200 pounds per linear inch. The fueled portion of the element shall be 24 inches long and shall be located within a 1/8 inch thick, 3,51 inch OD support clyinder which is 37 inches long. The support cylinder shall extend 6-1/2 inches beyond the fueled region on either end; this axial position shall be maintained by 3 plug welds joining the spacer
- webs and the support cylinder. Three lugs shall be provided on I
the inside of the support cylinder at each end. At one end, these lugs will position the cylindrical fuel element in the slots in the
" positioning lug" attached to the grid plate and at the other
- end will be used to mate with a fuel handling tool Partially loaded elements shall, except for the number of fuel plates, be designed in accordance with this paragraph.
- 6. The cylindrical fuel plate shall consist of 0. 020 inch thick U-Al alloy of 92% enriched uranium, clad on both sides with 0.015 inches of aluminum making the total plate thickness
- 0. 050 inches. The nominal U-235 content of each full fuel element shall be 200 grams.
. 7. A maximum of 15 fuel tubea described in F. 5 and F. 6 plus one partial fuel element which may have some of the fu6 pates missing, shall be used in the facility.
- 8. The critical assembly shall be controlled by two Y-shaped ontrol blades which pass in the clearance between adjacent fuel elements.
Construction details and dimensions shall be as shown in Figure 4.
One control rod (shim rod) shall be constructed so that the 4 blades are formed by sandwiching a.1/16 inch sheet of cadmium between 1/16 inch layers of stainless steel. The other control rod shall be an all stainless steel regulating rod. Either one
- of these control rods shall be capable of preventing the reactor from becoming critical.
i 9. Each control blade shall be guided by a guide assembly for the full iength of the control rod stroke. These guide assemblies shall prevent any bearing of the control blades on the fuel elements. l The guide assemblies, which shall be positioned on the grid by
pins, shall also act as sway bracing for the guide tubes. Details
- of the guide assembly, the methods for positioning on the grid
- plate, and the method for connection to the guide tube shall be as shown in Figure 4. The guide tube shall be bolted at the i
upper end to the control rod drive units. 16-17
4
- 10. Each control rod; shall be attached to its associated drive mechanism by an electromagnet and shall fall by gravity to the least reactive position upon decrease of magnet current as a
, result of scram action. A system shall be provided to give indication at the control console that a control rod is in
; contact with the magnet.
- 11. A reactor platform shall be located over the reactor tank on the second floor of the ZPR laboratory. The platform shall be bolted to the concrete floor of the room. The neutron and gamma- '
ray detectors described in Section H shall be suspended from this platform. The control rod drive mechanisms described in F.12 shall be bolted to the structural members of the reactor platform. 12 The control rod drive system shall be designed in accordance with the specifications in this subsect.on. Each control rod drive system shall be the standard American Machine and Foundry (AMF) designed cantilever drives with a design drive speed no greater than 12 inches per minute. Rod motion shall be controlled from the console by individual momentary contact toggle switches having an IN-OFF-OUT selection. Driving the control rods into the core by a reverse action as described in section I. 2 shall override any manual selection. Each drive shall also have position indication from the " full-in" to the " full-out" position. The position sensing element shall be a potentiometer located in each rod drive mechanism. Coarse position readout shall be provided on the control console in the form of two indict.Lors reading from 0% (full-in) to 100% (full-out). The system shall l indicate rod position with an accuracy of 2fo. A fine position indication system shall also be provided to indicate rod position with an accuracy of 0.1%.
- 13. The control console for the reactor shall be located as shown on Figure 1. The control console shall contain all the necessary switches, lights, and indicating instrumentation required to operate the reactor. Motion of the control rods out of the reactor shall be possible only by actuation of console control switches.
- 14. A moderator demberaliser system shall be located in the basement of the reactor laboratory. The system shall be a closed loop containing a pump and demineralizer. The flow rate through the demineralizer bed shall be valve controlled between 5 and 20 gallons / min /ft2 ,
15 The startup source shall be a Pu-Be source encapsulated in tantalum. The minimum source strength shall be one (1) curie (approximately 106neutrons per second). i l l 16-18
k G. Core Parameters Fuel shall be loaded into the reactor tank so as to conform to the specifications of this Section G.
- 1. The core shall be comprised of no more than fifteen standard fuel elements and one partial element. The number of fuel plates contained in the partial element shall be adjusted so that the most reactive core configuration possible will result in an excess reactivity, with both control rods completely l withdrawn, no greater than 0. 44% delta k/k.
l-l 2. No reflector elements, additional fuel, or other material shall l be installed or placed in the reactor s a as to increase the excess reactivity above that specified in G.1. l 3. No special nuclear materials other than those specified in ! Section F shall be placed in the reactor tank except the following:
- a. U-235 in foils or fission chambers not to exceed two (2) grams.
- 4. The core configuration shall be such that the calculated void coefficient shall be negative and shall have minimum absolute -
values as follows:
- a. Center of core 6. 8 X 10-6 ak/cc
- b. Edge of core 1.7 X 10-6 Ak/cc
- 5. The temperature coefficient of reactivity attributed to heating the moderator within the fuel elements shall be negative with a
( calculated absolute value not less than 1. 5 X 10-4 delta k/k ! per *C.
- 6. Core configurations shall be such that the minimum control rod worths shall be:
- a. Cadmium shim rod - O.025
- b. Stainless steel rod -0.009 Both control rods shall be installed and fully inserted before fuel is initially loaded in the core, and subsequently, whenever any component or fuel element is moved that will increase i core reactivity. ,
H. Nuclear Instrumentation L Whenever fuelis present within the reactor tank the design of the nuclear instrumentation system shall conform to the speciffLcations j of this section. i 16-19
- 1. The following channels of instrumentation shall be functioning when the reactor is operated in the ranges listed or core components are being moved. These channels shall be of the type and range as specified below:
Channel Type Detector Range Count Rate Log Count Rate BF 3Proportional Source Level to Channel Meter and Period Counter 150 milliwatts Meter Linear Piconmmeter Uncompensated Source Level to Channel Ion Chamber 200 milliwatts Gamma Area Radiation Geiger-Mueller . 01 watts to 10 watts Channel # 1 Monitor Probe (.01-100 mR/hr) Gamma Area Radiation Geiger-Mueller . 01 watts to 5 watts Channel # 2 Monitor Probe (. 01-100 'mR/hr) .
- 2. The count rate channel shall consist of a BF 3 Proportional counter, a preamplifier, high voltage power supply, scaler, log count rate meter, log count rate recorder, period detector, and a period indicator. The count rate channel detector shall be suspended from the reactor platform in the vicinity of the core such that a count rate of at least 2 counts per second are indicated as a result of subcritical multiplication with both control rods fully inserted.
l (- 3. The linear channel shall consist of an uncompensated ion chamber, high voltage power supply, picommmeter, and a linear recorder. The linear channel detector shall be suspended from the reactor platform in the vicinity of the core such that a current greater than 5% of full scale as indicated on the recorder with the most sensitive scale selected on the amplifier will result with both rods fully inserted. The highest scale setting on the picoammeter shall be physically set such that 100% of full scale shall be less than 0. 2 watts.
- 4. The gamma channels shall be located as described in section D.
1 l l 5 The control console shall contain the following indicators for the nuclear instrumentation:
- a. A scaler, log count rate meter, period indicator, and a log count rate recorder for the count rate channel.
- b. A picommmeter and linear recorder for the linear channel.
l c. A gamma indicator for each of the gamma channels and a l gamma recorder to record the intensity from either channel. _ _ _ ._ _.__._,16-20_ ___ ___ _ _,__,__.,__ _ _ __
I. Safety System The following circuits shall be functioning whenever fuelis in the reactor and power is available to the control drives.
- 1. Scram Circuits A scram system shall be provided that will cause interruption of the magnet current to the electromagnets supporting the control rods whenever a scram trip is exceeded. Power to the magnets shall be available when the " reactor on" switch is on and there are no scram trip signals. A scram trip shall be provided for each of the conditions below, with the trip setting as specified:
- a. High neutron flux - Count Rate Channel electronic trip set for 400% or less of Full Power (Full power shall be equal to 0. I watt).
I b. High neutron flux - Linear Channel electronic trip set for 200% or less of Full Power.
- c. High gamma activity - high level signal from either of
' the two Gamma Channels electronically set for 10 mR/hr or less.
- d. Manual scram - operates upon actuation of the manual scram button on the console.
- e. Low water level - operates when the tank water level drops one foot below the tank full position.
- f. Reactor key switch off - operates when the " REACTOR ON" switch is turned to the off position.
- g. Power failure - operates whenever the power supply to L
the console or to the nuclear instrumentation fails.
- 2. Reverse Circuits A reverse system shall be provided that will cause both control rod drives to drive the control rods into the reactor whenever a reverse trip is exceeded. The reverse action shall override any rod selection made by an operator and shall persist as long as a reverse trip levelis exceeded. Reverse trips shall be provided for each condition as below with the trip setting as specified:
- a. A Count Rate Channel reverse trip shall occur for any of the following conditions:
(1) Count Rate recorder off. l '(2) Count Rate recorder down scale - shall occur when the recorder indicates less than 2 counts l per second. (3) Count Rate recorder up scale - shall occur when the recorder indicates greater than 50,000 counts per second. 16-21
- __ _ .. . - . . . - _ _ _ . . _ . _ . _ . _ - . _ . . - . ~ _ _ . - - . . _ _ _ . _ . . - _
- b. Linear Channel reverse trip shall occur for any of the following conditions:
(1) Linear recorder off. (2) Linear recorder down scale - shall occur when the linear recorder is less than 5% of full scale. (3) Linear recorder up scale - shall occur when the linear recorder is greater than 95% of full scale.
- c. Gamma Channel reverse trip shall occur for any of the following conditions:
(1) Gamma recorder off. (2) Gamma recorder down scale - shall occur when the recorder indicates less than 0.2mR/hr. (It should be noted that the minimum reading on the recorder is 0. I mR/hr while the minimum reading on the instruments on the Gamma Channels for Area Radiation Monitoring is
. 01 mR/hr).
(3) Gamma recorder up r:cale - shall occur when the recorder indicates greater than 95 mR/hr.
- d. Any scram condition shall cause the control rod drives to drive in the electromagnets.
- e. External reverse trip shall actuate for any external reverse conditions which may be added to the reverse circuit.
- f. Manual run-trip - shall occur upon actuation of the "Run-In" switch on the control console.
- 3. Bypass in Safety Systems The only bypasses in the scram or reverse circuits shall be those described below. The bypasses shall be key operated switches located on the console.
- a. A bypass to eliminate a reverse as a consequence of the gamma recorder being down scale may be utilized during startup until the gamma recorder reads on scale.
- b. A bypass to eliminate a reverse as a consequence of the linear recorder being down scale may be utilized in the initial fuel loading while conducting experiments to ' determine suberitical multiplication.
4 Scram Times The following limits shall be verified every 6 months of operation and prior to operation of the facility if the facility is shutdown for 2 months or more. '
- a. Tne maximum time for total inserSon from the full out
, position to the fullin position as measured from the I generation of the scram signal shall be less than
- 1. 0 second.
16-22
J. Operating Limits
- 1. Reactor Power - The maximum steady state power shall be less than 0. I watt. When performing tests as described in Section E. 4. c.1. , transient power shall not exceed O. 2 watt.
- 2. Reactivity Addition Rate - The maximum reactivity insertion rate by control rods shall be less than . 001 A k/k per second.
- 3. A rod containing sufficient boron, cadmium, or other neutron absorber so as to have a minimum reactivity worth of 0. 030 A k/k when placed in the most effective core position shall' be available on the reactor platform to be inserted manually between the fuel elements.
- 4. The reactor moderator shall be sampled for fission product activity once per semester employing a multi-channel analyzer i for analysis.
- 5. Fuel elements shall be permanently stored on the reactor grid plate with the exception that three furl plates may be permanently stored in a locked steel container fastened to the floor of the first floor of the MCZPR Laboratory.
- 6. A ' sample check of the lucite hold-down rods shall be made for evidence of radiation damage once each semester.
- 7. All fuel elements may be temporarily removed from the core for purposes of preventive maintenance. All elements shall be placed only in the original shipping containers located on the reactor floor. The reactor Supervisor shall be present -
during removal and reloading of the fuel elements. I i L l* l l 16-23
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i l l l i REACTOR ADMINISTRATOR Chairman of Mechanical Engineering Department RADIATION REACTOR OPERATIONS SAFETY OFFICER COMMITTEE HEALTH PHYSICIST CHIEF REACTOR SUPERVISOR REACTOR SUPERVISORS CHIEF REACTOR OPERATOR STUDENT OPERATORS MAINTENANCE l l i I l . l l Figure 2. Table of Organization 16-25
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- 17. QUALITY ASSURANCE Since the Manhattan College Zero Power Reactor has been licensed since 1964 and no plans for new construction and design changes are included in this license renewal request, the requirements of 10CFR Part 50 for a description of a Quality Assurance Program for design and construction are not applicable. The organizational structure and the duties of the Reactor Operations Committee provide assurance that all procedures are adhered to and proper documentation is maintained.
1 i i t 17-1
REFERENCES ; l 1-1 " Facility License, No. R-94, Docket No. 50-199", i March 24, 1964, signed by Robert H. Bryan, Chief, Research and Power Reactor Safety Branch, Division of Licensing and Regulation, Atomic Energy Commission. 1-2 " Amendment No. I to Facility License No. R-94", Docket No. 50-199, attachment to September 18, 1973 letter from Donald J. Skovolt, Assistant Director of Operating Reactors, Directorate of Licensing, Atomic Energy Commission. l l 1 l R-1 l f
u._._..__. i l l APPENDIX A RADIATION SAFETY MANUAL l A-1 l l l
Manhattan College Nuclear Engineering Facility RADIATION SAFETY MANUAL l Rev. 0
~
I January 1,1983
PREFACE This Radiation Safety afanual replaces Part IV of the 1964 hianha,ttan College Reactor Manual. ( ii
TABLE OF CONTENTS l Pajte Title Page i Preface il Table of Contents ill
- 1. INTRODUCTION 1-1 1.1 Policy 1-1 1.2 Responsibilities and Authority 1-1 1.3 Reactor Operations Committee 1-2 1.3.1 Functions 1-2 1.3.2 Frequency of Meetings 1-2 1.3.3 Qualifications of Licensed Isotope Users 1-2 1.3.4 Procurement and Inventory of Radioisotopes 1-2 1.3.5 Records of Committee Meetings 'l-2
- 2. PERSONNEL SAFETY 2-1 2.1 Definitions 2-1 2.1.1 Units of Radiation 2-1 2.1.1.1 Roentgen 2-1 2.1.1.2 Rad (Radiation - Absorbed - Dose) 2-1 2.1.1.3 Rem (Roentgen - Equivale'nt - Man) 2-1 2.1.1.4 Dose Equivalent (H) 2-1 2.1.1.5 Quality Factor (Q) 2-2 2.1.1.6 Relative Biological Effectiveness (RBE) 2-2 2.1.1.7 Linear Energy Transfer (LET) 2-2 2.1.1.8 Kerma 2-2 2.1.1.9 Absorbed Dose Index (Di) ~
2-2 2.1.2 Summarization 2-2 l 2.1.3 Systeme Internationale (SI) 2-3 l 2.2 External Radiation ' 2-5 l 2.2.1 Permissible doses 2-5 2.2.2 NVT 2-5 2.2.3 Personnel Monitoring 2-7 2.2.3.1 Beta-gamma film badges 2-7 2.2.3.2 Beta-gamma-neutron film badges 2-7 2.2.3.3 Visitors film badges 2-7 l 2.2.4 Special Protection Procedures 2-7 2.2.5 Maintenance and Alterations 2-7
- 2.3 Internal Radiation 2-8 l 2.3.1 Permissible Dose 2-8 2.3.2 Control of Internal Radiation Hazards - Conditions 2-8 2.3.2.1 Use and Storage of Radioactive Materials 2-8
- 2.3.2.2 Food stuffs 2-8
2.3.2.3 Smoking 2-8 , 2.3.2.4 Pipetting 2-8 2.3.2.5 Special handling equipment 2-9 l 6M
l CONTENTS (Cont'd) P.ajte 2.3.2.6 Contact with hands 2-9 2.3.2.7 Air contamination 2-9 2.3.2.8 Movement of radioactive materials 2-9 2.3.2.9 Accidental contamination 2-9 2.3.2.10 Bioassays 2-10 2.3.2.11 Blood counts 2-10 2.3.2.12 Student Limitations 2-10 t 2.4 ALARA 2-10 2.5 References Cited 2-10 l
- 3. ALARA PROGRAM 3-1
[ 3.1 Administration Commitment 3-1 3.2 Reactor Operations Committee (ROC) 3-1 3.2.1 Review of Proposed Users and Uses 3-1 3.2.2 Delegation of Authority 3-2 3.2.3 Review of ALARA Program 3-2 3.3 Radiation Safety Officer (RSO) 3-2 3.3.1 Annual and Quarterly Review 3-2 3.3.2 Education Responsibilities for an ALARA Program 3-2 3.3.3 Cooperative Efforts for Development of ALARA Procedures 3-3 3.3.4 Reviewing Instances of Deviation from Good ALARA Practices 3-3 3.4 Authorized Users _ 3-3 3.4.1 New Procedures Involving Potential Radiation Exposures 3-3 3.4.2 Responsibility of the Authorized User to Those He Supervises 3-3 3.5 Persons Who Receive Occupational Radiation Exposure 3-3 l 3.6 Establishment of Investigational Levels In Order to Monitor ! Individual Occupational External Radiation Exposures 3-4 3.7 Signature of Certifying Official 3-5
- 4. CONTROL OF CONTAMINATION 4-1 4.1 Containment 4-1 4.2 Radiation Areas 4-1 4.3 Laboratory Control 4-2 4.3.1 Special Regulations 4-2 4.3.1.1 Containers 4-2 4.3.1.2 Contaminated glassware 4-2 4.3.1.3 Cleanliness 4-2 4.3.1.4 Spills 4-2
----m- -- -...,-n -v - - s, m - ~ - - - , - - - - - - - - - ,
CONTENTS (Cont'd) A'
- 5. DECONTAMINATION 5-1 5.1 Equipment 5-1 5.2 Hands and Other Body Parts 5-1
- 6. WASTE STORAGE AND DISPOSAL 6-1 6.1 Waste Disposal 6-1 6.2 Accumulation of- Active Wastes 6-1 6.2.1 Dry Waste 6-1 c 6.2.2 Liquid Waste 6-1 6.3 Waste Transfer 6-1 6.4 Manuals and Codes 6-2 6.5 Survey Instrumentation 6-2 6.6 Surveys 6-2 6.7 Protective Supplies 6-2 6.8 Disposal of Pool Water and Demineralizer Resin 6-3 6.9 Logs 6-3 6.10 Activation Estimates 6-3 6.11 Example Problems 6-5 Tables 2.1 UNITS 2-3 2.2 SI UNITS - DEFINITION 2-3 2.3 RAD TO GRAY (Gy) CONVERSIONS 2-3 2.4 - SI PREFIXES 2-4 2.5 CURIE TO BEQUEREL CONVERSIONS 2-4 2.6 RELATIONSHIP OF SIEVERT (SV) TO REM 2-5 2.7 RADIATION LIMITS IN SI UNITS 2-5 2.8 NEUTRON ENERGY - NEUTRON FLUENCE & NEUTRON FLUX DENSITY 2-6 3.1 INVESTIGATIONAL LEVELS 3-4 6.1 ACTIVATION DATA 6-4 m -- - , .- . - . .- _ - .. . . . . . . -
Manhattan College Nuclear Engineering Facility RADIATION SAFETY ~ MANUAL Stanley J. Malsky, Ph.D.
- 1. INTRODUCTION 1.1 Policy This mantal has been prepared to guide the activities of faculty members and students using the reactor, the radiation facilities, and radioactive materials in the Manhattan College Nuclear Engineering Facility. A number of general rules and procedures have been adopted, intended to safeguard all personnel. The Reactor Administrator will approve significant changes after review by the Reactor Operations Committee. The rules and procedures are designed to protect all individuals with a minimum of interference in their activities, consistent with the applicable rules and regulations of the Nuclear Regulatory Commission (NRC),
with the terms and conditions of Manhattan College'sIlcense for Special Material, with the Manhattan College Reactor Facility License and with applicable regulations of the State and City of New York. This manual is based on the following assumptions: r - the moral obligation to maintain person iel- health and safety with respect to all radiological ordinances car. never be compromised;
- the low power and inherent safety of the Manhattan College Zero Power Reactor (ZPR);
l - the need to inculcate reasonable and proper Health Physics procedures by requiring students to know and follow these regulations;
- personnel safety must be the first consideration at all times, and no requirements will be allowed to override safety considerations.
- An obligation to initiate an ALARA (As Low As Reasonably Attainable) program in keeping with federal (NRC) guidelines.
j 1.2 Responsibilities and Authority No set of rules can hope to cover all situations. Administration of and adequate [ provision for radiation protection and contamination control are the prime
' responsibilities of the Health Physicist to assure that all radiation protection and contamination control regulations are observed and that the procedures set forth herein are followed. The Health Physicist is responsible for recommending changes in any operation which he feels has not been evaluated realistically, for bringing the situation to the attention of personnel concerned and to the Reactor Administrator for correction.
The Health Physics - staff is available to advise and make recommendations I l l 1 l J l-1
l 1 regarding radiological protection. They will initiate radiation surveys, wipe tests, air sampling, Zero Power Reactor water and_ such other sampling and environmental analysis as may be requested by the Chief. Reactor Supervisor, ! Reactor Administrator, or by the NRC, either as a directive or as part of revised procedures. 1.3 Reactor Operations Committee 1.3.1 Functions l The Reactor Operations Committee shall administer the Manhattan College Zero i Power Reactor and isotope program. . All on-site radioisotope production in the reactor and disposals will be reviewed in advance for conformity with policies adopted by the committee and will be recorded. All proposed procedures for noncoutine or unusual operations, handling and experiments involving radioisotopes shall be reviewed from the point of radiation safety. All radioactive waste disposal procedures shall be determined by this committee. ! 1.3.2 Frequency of Meetings The Reactor Operations Committee will routinely meet once a semester or as necess,ary. 1.3.3 Qualifications of Licensed Isotcpe Users ,~
-Persons proposing te work with radioactive materials must prepare an outline of qualifications and cxpeelence in the Sandling and use of _ radioactive materials.
The information submitted will _ be reviewed by the Reactor Operations i- Committee. Committee members will be available as consultants to users, and will directly supervise or_ arrange for supervision of the use of radioisotopes where considered necessary or advisable. Personnel who are approved to work with radiation shall be placed in one of. two categories: 1) certified to work with radioactive materials without supervision; and ' 2) certified to work. with radioactive materials only with supervision. Faculty members and research . collaborators who use byproduct materials, in exempt or non-exempt quantities, as [ defined in Article 175 of the New York City Health Code, must submit and file this information. Students taking courses where radiation is used in the , laboratory are exempt from this regulation. Students shall be under the control of qualified faculty when working in the reactor area or with radioactive isotopes.- 1.3.4 Procurement and Inventory of Radioisotopes The Reactor Administrator - will authenticate the inventories of licensed radioisotopes in the reactor facility. This will be accomplished through c- comparison of the written records of the persons in possession of isotopes with L those of. the ' Reactor Operations Committee. Confirmation of the records by physical inventory of the licensed radioisotopes in the Reactor Facility will be requested at least annually by the committee. 1.3.5 Records of Committee Meetings I. The' committee secretary will prepare a permanent written record of committee proceedings for committee approval, such written record to be maintained and
. presented at the following meeting for approval.
l 1-2
I
- 2. PERSONNEL SAFETY 2.1 Definitions 2.1.1 Units of Radiation Each type of ionizing radiation has its own degree of biological hazard depending on its energy, intensity, and specific ionization ability. The roentgen is a unit which is an Indication of the expo.sure to X and gamma radiation up to 3 MEY.
2.1.1.1 Roentaen A roentgen is that quantity of X or gamma radiation such that the associated corpuscular emission per 0.001293 gm of air (1 cc of dry air at STP) produces, in air, ions carrying i esu of quantity of electricity of.either sign corresponding to
- the absorption of 84 ergs of energy in 1 gram of dry air. The specific
! absorption of tissue is greater than that of air, so 1 R (of X or gamma radiation) imparts 93 ergs of energy to 4 gram of tissue rather than 84 ergs. The roentgen is also equal to 2.58 X 10 coulombs per kilogram of air. Since radiations other than X and gamma radiation are frequently encountered, more generalized units are required. The most . frequently used is ~ the radiation absorbed dose (rad). 2.1.1.2 Rad (Radiation - Absorbed - Dose) A rad is the amount of radiation which imparts 100 ergs of energy to 1 gram of material. Other radiations have biological effects which do not depend entirely de on the amount roentgen of energy equivalent absorbed, man (rem). and it is useful to_y I rad .= 0.01 J kg
= fine 0.01aGy further unit, the of absorbing l material.
2.1.1.3 Rem (Roentgen - Equivalent - Man) i i The rem accounts for differences 'in biological effect due to the differences in qualities of the various, radiations. The rem is a measure of the actual biologic effect produced by radiation and as such, is a more practical unit than the i roentgen. The rem is the special unit of dose equivalent (H). The rem is related to the absorbed dose (rad) by a quality factor (Q). 2.1.1.4 Dose Equivalent (H) Dose Equivalent is the product of the absorbed dose (D), quality factor (Q) and the product of any modifying factors other than Q (N) at the point of interest in tissue. For this discussion N = 1. The special unit of dose equivalent is the rem with D expressed in rads, H in rems. 2.1.1.5 - Quality Factor (Q) A factor which is used in radiation protection to weigh the absorbed dose with regard to its presumed biological effectiveness insofar as it depends upon the LET of the charged particles. The quality factor is a function of the LET of the charged particles that deliver the absorbed dose. l 2-1
2.1.1.6 Relative: Biological Effectiveness (RBE) Biological potency of one radiation as compared with another, in terms of the inverse ratio of the respective absorbed doses that produce the same biological effect. The use of this term is to be restricted to radiobiology, and it should be distinguished from the Quality Factor (Q), which is employed in radiation , protection. 2.1,1.7 Linear Energy Transfer (LET) A measure cf the ability of biological material te absorb ionizing radiation; the radiation energy lost per unit length of path through a biological material. In general, the higher the LET value, the greater is the relative biological l effectiveness (RBE) of the radiation in that material. 2.1.1.8 Kerma l The sum of the initial kinetic energies of all the charged particles liberated by indirectly ionizing particles per unit mass of specified material. The special unit of Kerma is the rad. 2.1.1.9 Absorbed Dose Index (Di) The maximum dese within a 30 centimeter diameter sphere centered at the point of intere5t and e nst ting of material equivaient to soft tissue with a density of 1 gm/cm 2.1.2 Summarization The concept of dose equivalent (H) has been defined as the product of absorbed dose (D), quality factor (Q), (formerly called the relative biological factor, same as RBE) dose distribution factor and other necessary modifying factors: H = D x Q x DF x . . . . . The unit of dose equivalent is the rem. i l Average Q Values for Different Types of Radiation l EXTERNAL EXPOSURE INTERNAL EXPOSURE 3 Radiation Q Radiation Q X & gamma rays 1.0 X & gamma rays 1.0 beta (except of very low b+, b , electrons energy) 1.0 E > 0.03 MeV 1.0 Thermal neutron 3.0 b+, b , electrons i Neutrons, E = 0.0001 MeV 2.0 E < 0.03 MeV
~
1.7 Neutrons, E = 0.005 MeV 2.5 - Alpha particles 10.0 l Heavy particles 20.0 Other heavy particles 20.0 o i 2-2
2.1.3 Systeme Internationale (SI)
"The currently ured radiation units - roentgen, curie and rad - are scheduled for obsolescence. To provide a common set of units for these in all branches of the physical sciences, an extension of the metric system termed Le Systeme International d' Unites (SI, The International System of Units) was adopted in 1960." [1,2] The International Commission of Radiological Protection'(ICRP) has adopted radiological units based on the metric system. All countries are expected to be using these units by 1986, and drop the present units. Table 2.1 below identifies the old and new units.
Table 2.1 UNITS QUANTITY OLD UNIT NEW UNIT Activity Curie (Cl) Bequerel (Bq)
< Absorbed Dose (D) rad Gray (Gy)
Dose Equivabnt (H) rem Sievert (SV) Exposure (E) Roentgen (R) Exposure (E)
-nct named The definitions of the SI units in metric units are presented in Table 2.2 Table 2.2 SI UNITS - DEFINITION QUANTITY S.I. UNIT DEFINITION
~1 Activity Bequerel (Bq) sec =
Absorbed Dose (D) Gray (Gy) joule /kg of medium Dose Equivalent (H) Sievert (SV)* joule /kg of medium , Exposure (E) Exposure coulomb /kg of air l l *Although the units for the Gray and Sievert are the same, the Sievert is calculated as follows (this is the same relationship as between rems and rads): Dose Equivalent (H) = Absorbed dose in Gy (D) x Quality Factor (QF) x ' Modifying Factors (MF) Only for the case where QF = MF = 1 will the number of Steverts equal' the number of Grays. This is the case only for gamma rays, x-rays or beta rays. The rad to Gray conversions appear in Table 2.3 below. Table 2.3 RAD TO GRAY (Gy) CONVERSIONS l 1 mrad = 10pGy = 0.01 mGy i 10 mrad = 100pGy = 0.1 mGy l 100 mrad = 1000pGy = 1.0 mGy 1 rad = 10.0 mGy 10 rad = 100.0 mGy 100 rad = 1.0 Gy __. _2 _ . - _ .._ _._ _.___-.. _ ._.-.._-,
For radionuclides, certain prefixes are convenient multiples when describing activity. For example, megabequerels (MBq) are used in the microcurie (uCl) and millicurie (mCl) levels. Terabequerels (TBq) are used in the kilocurie (kcl) level. Table 2.4 S1 PREFIXES FACTOR PREFIX SYMBOL 18 10 exa E 10 peta P f 10 tera T 10l giga G 10 mega M 3 l 10 2 kilo k 10 hecto h 10 deka da 1 deci d 10 2 10
-3 centi e 10 milli m 10 micro p 10-9 nano n
-12 pg, p 10
-15 10 femto f
-18 10 atto a Table 2.5 demonstrates the relationship between curies (Cl) and Bequerels (Bq).
Table 2.5 CURIE TO BEQUEREL CONVERSIONS CI Bo Bo Ci l- 1 nCi 37.00 Bq 1 Bq 27.0 pCi i pCi 37.00 kBq 10 Bq 270.0 pCi 10 pCi 370.00 kBq 100 Bq 2.7 nCi 30 pCI 1.11 MBq 1 kBq 27.0 nCi 100 pCi 3.70 MBq 10 kBq 270.0 nCi 1 mci 37.00 MBq 100 kBq 2.7 pCi 10 mci 370.00 MBq 1 MBq 27.0 pCi 100 mci 3.70 GBq 10 MBq 270.0 pCi 1 Ci 37.00 GBq 100 MBq 2.7 m Ci 10 Ci 370.00 GBq 1 GBq 27.0 mci 100 Ci 3.70 TBq 1 TBq -27.0 Ci l 1 kCi 37.00 TBq 1 PBq 27.0 kcl 1 MCI 37.00 PBq 100 PBq 2.7 M CI l 30 mci 1.11 EBq 1 EBq 27.0 MCI 2-4
I The sievert (SV) is the term for dose equivalent. The relationship of sievert to rems is presented in Table 2.6. Table 2.6 RELATIONSHIP OF SIEVERT (SV) TO REM 1 mrem = 10 pSv. = 0.01 mSv. 10 mrem = 100 pSv. = 0.1 mSt. 100 mrem = 1000 pSv. = 1.0 mSv. I rem = 10.0 mSv. 10 rem = 100.0 mSv. 100 rem = 1.0 Sv. . To summarize: 1 rad = 0.01 JKg-I = 0.01 Gy 1 curie = 3.7 x 10 10 3-1 = 3.7 x 1010 Bq Table 2.7 presents the current radiation protection guidelines in SI units as recommended by the National Council on Radiation Protection (NCRP). Table 2.7 RADIATION LIMITS IN SI UNITS Body Organ Annual Limit (mSv) Inferred Weekly Limit (mSv) Total body, head and trunk, bone marrow, gonads or eye lens 50 1.0 Hands and feet 750 (250)* 15.0 (5)* Forearms and ankles 300 (125)* 6.0 (2.5)* Any other organ (including skin) 150 3.0 Fetus in gestation period (9 months) 5 0.13 ! *ICRP has proposed reducing extremity limits to values shown in parentheses. NCRP will probably accept them. l 2-5
- _ . . ~ _ - . . _ _ _ . - _ _ _ _ . . - . ~ . _ _ . . _ . . - , _ _ - _ _ _ _ - _ , .
2.2 External Radiation 2.2.1 Permissible doses The Maximum Permissible Dose (MPD) of radiation, as established by the NRC in regulations appearing in the Federal Register, Title 10, Chapter 1, Part 20,
" Standards for P otection Against Radiation" (herein-after referred to as 10CFR20), and as recommended by the NCRP in National Bureau of Standards Handbook 69, " Maximum Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure" (NBS69), will govern at Manhattan College, whichever is lower. Exposures are- stated in rems for the present; future dose values will be presented in sieverts (SV).
2.2.2 NYT 2 NVT represents the neutron fluence (n/cm ), which is tpe time integral of the l neutron flux density. (n = neutron flux density; n/cm , y = neutron velocity, cm/sec. and t = time of exposure in seconds). jany neutron survey meters are
- calibrated against the neutron flux density (n/cm -sec). Table 2.8 presents the relationship between neutron energy and either neutron fluence or neutron flux density for a particular dose equivalent. [3,4]
Table 2.8 NEUTRON ENERGY - NEUTRON FLUENCE & NEUTRON FLUX DENSITY f Neutron Flux Density for Neutron Energy Neutron Fluence fqr 2.5 mrems/hr (n/cm -sec) (MeV) 100 mrems (n/cm") (40 hrs = 100 mrems) 5 Thermal 970 x 10 5 670 [ 0.0001 720 x 10 500 0.005 820 x 10 5 570 0.02 400 x 10 5 280 0.10 120 x 10 80 ! 0.50 43 x 10 5 30 ( 1.0 26x10j 18 2.5 29 x 10 5 20 5.0 26 x 10 3 18 7.5 24 x 10 II 10.0 24 x 10 55 17 10-30 14 x 10 10 4 2 A NVT of 1.4x10 peutrons/cm shall be considered equal to 1 mrem (therefore,
- sec equals 1 mrem /hr) unless there exists sufficient
- a flux of 4n/cm l
Information to establish with reasonable accuracy the approximate distribution in energy of the neutrons in which case a higher flux per mrem ,may be authorized by Health Physics in accordance with 10CFR20, Paragraph 20.4. From the above-referenced sources, the whole body limits currently in effect, including any internal dose, are: 100 mrems per week,1250 mrems per 13 weeks, and 5000 mrems per year (i.e., approximately 100 mrem per week continuous exposure). It must be stressed that the minimum possible dose commensurate with efficient l working conditions must be a prime objective of - all personnel: see ALARA l program. 2-6 . _ _ , .
i 2.2.3 Personnel _flonitorinst l Personnel monitoring devices are required. Body type film badges, as supplied by a commercial vendor, shall be issued to those individuals working with radiation. Records indicating absorbed doses fr;;m radiation received on the site will be maintained in the reactor area for review by the Chief Reactor Supervisor, the Health Physicist and by the Reactor Operations Committee. A record of personnel exposures, similar to that provided by NRC Form 5, will be maintained or incorporated in the film badge record sheets. 2.2.3.1 Best-gamma film badges These badges contain beta-gamma film only and are developed regularly. They l are worn by student personnel who normally enter the reactor rooms. , 2.2.3.2 Beta-gamma-neutron film badges l These badges contain both beta-gamma and neutron film and are developed regularly. They are worn by all reactor operator personnel normally working in the reactor rooms. 2.2.3.3 Visitors film badges j Each group of visitors will have body gamma badges distributed within the group. The escort shall wear a special film badge to be worn only while escorting visitors. One badge shall be issued per 10 visitors. 2.2.4 Special Protection Procedures l Normally no special precautions are necessary for personal safety in radiation l fields where the total body dose rate is less than 1 mrem /hr. However, it must l be remensbered that the field at a short distance from a radioactive source will i be much greater than the field at normal working distances. Some sources must be handled with tongs or other remote handling equipment. It is also recommended that no person should plan to work for extended periods of time in a field where total body dose rate is greater than 1 mrem /hr. Any field of 2.5 mrem /hr must be clearly defined and posted with signs containing the radiation symbol and the words, " CAUTION - RADIATION AREA". The Health Physicist shall be notifiec of any changed circumstances which may be expected to alter the radiation field. 2.2.5 Maintenance and Alterations When maintenance and alteration is planned, the Health Physicist will be notified , in advance, so that radiation and contamination surveys can be made, and [ planning for necessary film badges, monitoring, tool decontamination, protective ! clothing, etc., can be carried out. ? Special work permits may be required when a person is working in an area where l actual or potential radiation or contamination hazaM exists. Such permits will be issued only for outside contractor personnel. l 2-7
t I 2,3 Internal Radiation 2.3.1 Permissible Dose The permissible occupational averaged annual dose for internal radiation is limited i to 5,000 meem (100 mrem per week) for those isotopes which tend, when . Ingested, to distribute themselves to the whole body,15,000 mrem (300 mrem per week) for those isotopes which tend to concentrate in any one critical organ, and to an amount of bone seeking isotopes which releases the sanie energy to the bone as 0.1 pg Ra-226 plus daughters (approximately 25,000 mrem / year or 500 mrem / week). Appendix B, Table I,10CFR20, and also NBS Handbook 69 list most of the harmful isotopes with maximum permissible occupational and non-
. occupational concentrations in air and water and their maximum body burdens.
The lowest concentration listed in either of these sources will be used at Manhattan College. The dose from internal exposures will be considered additive to dose received from external radiation when calculating total whole body j exposures. See ALARA section dealing with reduction of exposure concepts. i 2.3.2 Control of Internal Radiation Hazards - Conditions The list of radioisotopes given in Appendix B of 10CFR20 and in NBS 69 show a wide verlety of substances and range of tolerance levels involved in the control
, of internal radiation. Toxicity is only indirectly related to measured activity since the degree of absorption into a critical organ is dependent for some substances on the method of entry into the body, e.g., ingestion, inhalation, contamination of wounds, or absorption through the skin, (specially when solvents
- are involved. For these reasons, it is not possible to set up general rules to cover all situations and Health Physics must be consulted whenever the possibility of the intake of more than 1/10 maximum body burden of any isotope exists or is anticipated. The following regulations must be observed as a basic niinimum for the control of internal radiation hazards.
2.3.2.1 Use and Storage of Radioactive Materials Each area or room in which radioactive material is used or stored and which contains ' an amount exceeding ten times the quantity of such material as specified in Appendix B of 10CFR20 or greater than the maximum body burden shown in NBS 69, whichever is lower, shall be posted with a sign or signs bearing the radiation symbol and the words, " CAUTION - RADIOACTIVE MATERIALS". 2.3.2.2 Food stuffs No beverages, foodstuffs, or application of cosmetics are allowed in the ZPR, graphite or counting areas. 2.3.2.3 . Smoking Smoking is allowed per College regulations in certain designated areas, -but is specifically prohibited in all radiation zones. I 2.3.2.4 Pipetting No radioactive liquid is to be pipetted by mouth. 2-8
2.3.2.5 Special handling equipment Some special portable equipment, such as long-handled tongs, remote pipetters, lead carriers, etc., are available for general use in the Counting Room. 2.3.2.6 Contact with hands Rubber gloves are to be worn in cases vihere radioactive material or solutions of , radioactive material may come in cor. tact with the hands unless their use introduces a greater hazard or extreme inconver.!cace. Persons with breaks in the skin must not attempt to work with radioactive substances without consulting with the Health Physicist for suitable protective measures. 2.3.2.7 Air contamination , Any room, enclosure, or operating area in which radioactive material exist in concentrations in excess of the amounts specified in Appendix B, Table I, Column I,10CFR20, or in NBS 69, or in which they exist in concentrations which, averaged over the number of hours in any week during which individuals are in the area, exceed 25 percent of the amount specified in 10CFR20 or NBS 69 shall be conspicuously posted with a sign or signs bearing the radiation symbol and the words, " CAUTION - AIRBORNE RADIOACTIVITY AREA". No person is to enter a room or area where it is known or suspected that the permissible limit for airborne activity is exceeded. No operation is to be performed which might cause radioactivity to become airborne in excess of permissible levels. 2.3.2.8 Movement of radioactive materials ! No radioactive material is to be moved from the Engineering Building in such a l manner that is possible for the material to escape from the container. Liquids, gases, and dispers.ible solids must be transported in suitable vessels with a protective sheath of shatterproof material. Surface contamination on articles for decontamination or waste disposal can usually be contained by wrappings of polyethylene sealed with adhesive tape. The outside surface of packages which are to be transported must be free from removable contamination so as to smear below 10 alpha dpm and 100 beta dpm on a standard smear. Materials and
- equipment to be transferred from a designated shoe' cover area must carry HP-2
" Approved for Cold Areas" tags. These tags will be issued by the Health Physicist if surface contamination is below 100 dpm beta and 10 dpm alpha for standard wipe smear and if object has no activity detectable with a survey i
meter. 2.3.2.9 Accidental contamination l Any person who believes that he may have absorbed radioactive materials into his., l body should immediately consult the Health Physicist, who will initiate l appropriate bloassay samples and summon medical aid, if these procedures are l deemed necessary. Absorption through the unbroken skin is possible when large l amounts of active material are involved. L.__.__.__ 2-9
2.3.2.10 Bloassays 1 Reactor personnel other than students my be required to submit urine samples for radioactive analysis. Such samples will be requested at the discretion cf the Health Physicist or Reactor Operator when any signif! cant internal exposure of radioisotopes is suspected to have occured. If the sample or samples indicate an overexposure to internal radiation, the Health Physicist will investigate and a report of findings will be prepared. This report will also include recommen-dations to remedy the situation. The report is to be submitted to the Reactor Operations Committee for review and implementation. 2.3.2.11 Blood counts - Personnel described in part 2.3.2.9 above may be required to provide a blood sample. The results of the blood count will be received by the Health Physicist and included in the documented report mentioned in part 2.3.2.9. above. 2.3.2.12 Student Limitations Student irradiation of samples will be restricted to solids. This regulation may i be modified to include gas or liquid samples. Such modifications are provided by the Reactor Operations Committee, which will review the reasons for the modification and rhall demonstrate the radiological safety of the procedures. 2.4 ALARA The NRC has introd'uced tne ALARA program as a further measure for reduciq radiation exposure to radiological worieers. The ALARA program is a commitment on the pert of each radiological facility to closely monitor all dosimetry values and seek methods or techniques to further reduce the radiation levels that their staff may receive. The Manhattan College Nuclear Engineering Facility subscribes to this program. Section 3 presents the ALARA program as it relates to the Manhattan College Nuclear Engineering Facility. 2.5 References Cited
- 1. Wyckoff, Harold 0; The International System of Units (SI). Editorial, Radiology 128:833-835, Sept 1978.
- 2. The International Commission on Radiation Units & Measurements, Washington, D.C. Mar 31,1978.
- 3. New York State Sanitary Code, Part 16.2 4.10CFR20.3(CX4) l 2-10
- 3. ALARA PROGRAM 3.1 Administration Commitment 3.1.1 We, the Administration of Manhattan College and the Manhattan College Nuclear Engineering Facility are committed to the program described below for keeping exposures (Individual and collective) as low as reasonably achievable (ALARA). In accord with this commitment, we hereby describe an administrative organization for radiation safety and will develop the necessary i written policy, procedures and instructions to foster the ALARA concept within
- our institution. The organization will include the existing Reactor Operations Committee (ROC) and an appointed Radiation Safety Officer (RSO).
3.1.2 We will perform a formal annual review of the radiation safety program including ALARA considerations. This shall include reviews of operating l procedures and past exposure records, inspections, etc., and consultations with the radiation protection staff or outside consultants. ; 3.1.3 Modification to operating and maintenance procedures and to equipment and facilities will be made where they will reduce exposures unless the cost, in our judgement, is considered to be unjustified. We will be able to demonstrate, if necessary, that improvements have been sought, that modifications have been considered, and that they have been implemented where reasonable. Where modifications have been recommended but not implemented, we will be prepared to describe the reasons for not implementing them. i 3.1.4 In addition to maintalriing doses to individuals as far below the limits as is reasonably achievable, the sum of the doses received by all exposed individuals will also be maintained at the lowest practicable level. It would not be desirable, for example, to hold the highest doses to individuals to some fraction of the applicable limit if this involved exposing additional people and significantly. increasing the sum of radiation doses received by all involved l Individuals. 3.2 Reactor Operations Committee (ROC) 3.2.1 Review of Proposed Users and Uses 3.2.1.1 The ROC will thoroughly review the qualifications of each applicant with respect to the types and quantitles of materials and uses for which he has applied to assure that the applicant will be able to take appropriate 1 measures to maintain exposure ALARA. 1 L 3.2.1.2 When considering a new use of byproduct material, the ROC will review the' efforts of the applicant to maintain exposure ALARA. The user should have systematized procedures to ensure ALARA, and shall have i incorporated the use of special equipment in his proposed use. 3.2.1.3 The ROC will ensure that the user justifies his procedures l and that dose will be ALARA (individual and collective). _ _ _ . - - _ . __ _, _ _ . _ 3 -1
3.2.2 Delegation of Authority (The judicious delegation of ROC authority is essential to the enforcement of an ALARA program.) 3.2.2.1 The ROC will delegate authority to the RSO for enforcement of the ALARA concept. 3.2.2.2 The ROC will support the RSO in those instances where it is necessary for the RSO to assert his authority. Where the RSO has been overruled, the Committee will record the basis for its action in the minutes of the Committee's semi-annual meeting. 3.2.3 Review of ALARA Program 3.2.3.1 The RSO will encourage all users to review current procedures and develop new procedures as appropriate to implement the ALARA concept. 3.2.3.2 The RSO will perform a quarterly review of occupational radiation exposure with particular attention to ' instances where Investigational Levels in Table 3.1 (below) are exceeded. The principle purpose of this review is to assess trends in occupational exposure as an index of the ALARA program quality and to decide if action is warranted when Investigational Levels are exceeded (see paragraph 3.6). 3.2.3.3 The RSO will evaluate our Nuclear Engineering Facility's overall efforts for maintaining exposures ALARA on an annual basis. This review will include the efforts of the RSO, cuthorized users, and workers as well as those of the Administration of Manhattan College and the Nuclear Engineering Facility. 3.3 Radiation Safety Officer (RSO) 3.3.1 Annual and Quarterly Review 3.3.1.1 Annual Review of the Radiation Santy Program. The RSO will perform an annual review of the Radiation Safety Program for adherence to ALARA concepts. Reviews of specific procedures may be conducted on a more frequent basis. 3.3.1.2 Quarterly review of Occupational Exposures. The RSO will review at least quarterly the external radiation exposures of authorized users and workers to determine that their exposures are ALARA in accordance with the provisions of Paragraph 3.6 of this program. 3.3.1.3 Quarterly review of records of Radiation Level Surveys. The RSO will review radiation levels in unrestricted and restricted areas to determine that they were at ALARA levels during the previous quarter. 3-2
i 4 3.3.2 Education Responsibilities for an ALARA Program 3.3.2.1 The RSO .will schedule briefings and educational sessions as needed to inform workers of ALARA program efforts. 3.3.2.2 The RSO will assure that authorized users, workers and ancillary personnel who may be exposed to radiation will be instructed in the ALARA philosophy and informed that administration, the ROC and the RSO are committed to implementing the ALARA concept. 3.3.3 Cooperative Efforts for Development of ALARA Procedures
i Radiation workers will be given opportunities to participate in formulation of the procedures that they will be required to follow. 3.3.3.1 The RSO will be in close contact with all users and workers in order to develop ALARA procedures for working with radioactive materials. 3.3.3.2 The .RSO will establish procedures for receiving and evaluating the suggcetions of individual workers for improving health physics practices and encourage the use of those procedures. . 3.3d Reviewing Instances of Deviation from Good ALARA Practices The RSO will investigate all known ' instances of deviation .from good ALARA practices; and, if possible, determine the causes. When the cause is known, the l RSO will require changes in the program to maintain exposures ALARA. 3.4 - Authorized Users 3.4.1 New Procedures Involving Potential Radiation Exposures 3.4.1.1' The authorized user will consult with, and receive the approval of, the RSO and the ROC during the planning stage before using radio-active materials for a new procedure. 3.4.1.2 The authorized user will evaluate all procedures before using radioactive materials to ensure that exposures will be kept ALARA. This may be enhanced through the application of trial runs. 3.4.2 Responsibility of the Authorized User to Those He Supervises 3.4.2.1 The authorized user will explain the ALARA concept and his commitment to maintain exposures ALARA to all of those he supervises. 3.4.2.2 The authorized user will ensure that those under his supervision who are subject to occupational radiation exposure are trained and educated in good health physics practices and in maintaining exposures ALARA. ! 3.5 Persons Who Receive Occupational Radiation Exposure 3.5.1 The worker will be instructed in the ALARA concept and its relationship to his working procedures and work conditions.
,_._. .-.. ._ ~. _ _ _ 3. -3, _ _ , _ _ _ ___ ,_,_ _ _,, _ _ ___ -
3.5.2 The worker will know what recourses are available if he feels that ALARA is not being promoted on the job. , 3.6 Establishment of Investigational Levels In Order to Monitor Individual Occupational External Radiation Exposures The Manhattan College Nuclear Engineering Facility hereby establishes Investigational Levels for Occupational external radiation exposure which, when exceeded, will initiate review or investigation by the Reactor Operations Committee and/or the Radiation Safety Officer. The Investigational Levels that we have adopted are listed in Table 3.1 below. These levels apply to the exposure of individuals. TABLE 3.1 ( Investigational Levels-(mrems per calendar quarter) LEVEL I LEVEL U
- 1. Whole body; head and trunk; 125 375 active blood-forming organs; lens of eyes; or gonads
- 2. Hands and forearms; feet and 1875 5625 ankles
- 3. Skin of whole body
- 750 2250
- Not normally applicable to nuclear medicine operations except those using significant quantitles of beta emitting isotopes.
The Radiation Safety Office will review and record on Form NRC-5, Current Occupational External Radiation Exposures, or an equivalent form (e.g. dosimeter processor's report), results of personnel monitoring, not less than once in any calendar quarter. The following actions will be taken at the Investigational Levels as stated in Table 3.1: 3.6.1 Quarterly exposure of individuals to less than Investigational Level I. Except when deemed appropriate by the RSO, no further action will be taken in ' those cases where an individual's exposure is less than Table 3.1 values for the Investigational Level I. ! 3.6.2 Personnel exposures equal to or greater than Investigational Level I, but less than Investigational Level II. The RSO will review the exposure of each individual whose quarterly exposures equal or exceed Investigational Level I. He will report the results of his reviews at the first ROC meeting following the quarter when the exposure was recorded. If the exposure does not equal or exceed Investigational Level II, no action i related specifically to the exposure is required unless deemed appropriate by the l 3-4
i l Committee. The Committee will, however, consider each such exposure in comparison with those of others performing similar tasks as an index of ALARA program quality and will record the review in the Committee minutes. 3.6.3 Exposure equal to or greater than Investigational Level II. The RSO will investigate in a timely manner the causes of all personnel exposures equaling or exceeding Investigational Level II and, if warranted, take action. A report of the investigation, actions taken, if any, and a copy of the individual's Form NRC-5 or its equivalent will be presented to the ROC at the first ROC meeting following completion of the investigation. The details of these reports will be recorded in the minutes. Committee minutes will be sent ( to the administration of this institution for review. The minutes, containing details of the investigation, will be made available for review. 3.6.4 Re-establishment of an individual occupational worker's Investigational Level II Above That Listed in Table 3.1. In cases where a worker's or a group of workers' exposures need to exceed InvestigationM Level II, a new, higher Investigational Level II may be established on the basis that it is consistent with good ALARA practices for that individual or group. Justification for a new Investigational Level II will be documented. The Reactor Operations Committee will review the justification for, and will approve, all revisions of Investigational Levels IL In - such cases, when the exposure equals or exceeds the newly established Ir.restigational Level II, those actions listed in paragraph 3.6.3 above will be followed. 3.7 Signature of Certifying Official I hereby certify that the Manhattan College Nuclear Engineering Facility has implemented the ALARA Program set forth above. i _Thet Stephen Sullivan, F.S.C.
/*< h / fa f3 Date President, Manhattan College l
l l r I 1 1 3-5 l
- z
- 4. CONTROL OF CONTAMINATION 4.1 Containment All radioactive material must be contained in an appropriate vessel, when not in use and in such condition is known as a source of radiation.
Each container in which there is transported, stored, or used a quantity of radioactive material greater than the quantity shown in Appendix C of 10CFR20 or greater than the maximum body burden shown in NBS 69, whichever is lower, shall bear a durable, clearly visible label bearing the radiation caution symbol and the words, " Caution - Radioactive Material". However, such a label shall not be required: r If the concentrction of the material in the container does not , exceed that specified in Appendix B, Table I, Column 2, 10CFR20, or in the occupational RPC for 40 hour week shown in NBS 69. For laboratory containers such as beakers, flasks and test tubes used transiently in laboratory procedures, when the user is present. When containers are used for storage, a " Caution, Radioactive Material" tag or equivalent shall state also the quantities and kinds of radioactive materials in the container and the date of the measurement of the quantities. In addition to the cbove requirements, encapsulated sources and any other vessels inside such a container will also be labelled whenever practicable and whenever there is any reasonable possibility of the source or vessel being left outside its container or of being separated from it in transit. The label of sources in transit for use outside the laboratory shall also certify that there is no contamination on the outside of the container. The person dispatching a source is responsible for planning a safe method of transport and for ensuring that adequate warnings are given to all personnel likely to come in contact with the source until it reaches its destination and is turned over to the custody of the recipient. Sources not in current use should be shielded so that the radiation field at one , foot anywhere outside the shield does not exceed 2.5 mrem /hr. l The . Manhattan College Reactor Operations Committee shall provide properly j controlled and labelled storage for sources larger than those which can be stored l In the laboratories. The radiation field at any accessible point outside the l storage area shall not exceed 2 mrem /hr. All containers containing radioactive ' sources shall be labelled with the source strength, 'and type of source in accordance with 10CFR, Part 20. 4.2 Radiation Areas The Manhattan College Reactor Operations Committee is responsible for requesting the Health Physicist for surveys so that properly marked radiation signs and tags are prominently displayed in all radiation areas. The necessity and i 4-1
r extent of isolation and type of radiation sign will be determined by the Health Physicist in accordance with Title 10, Chapter 1, Part 20, Section 20.203 of the Nuclear Regulatory Commission Guidelines. 4.3 Laboratory Control The Chief Reactor Supervisor or other persons approved by the ROC shall be responsible for the control of contamination in the facility. Working surfaces, walls, and floors must be " clean on wipe" i.e., there must not be removable contamination in excess of 100 dpm beta or 10 dpm alpha per standard smear. Fixed contamination must not exceed 2.5 mR/hr on contact. Since fixed contamination will be gradually liberated by wear of surfaces, the following should be considered: 4.3.1 Special Regulations The following regulations are useful for general laboratory conditions. 4.3.1.1 Containers Containers of active material and all possible equipment shall be placed in auxiliary containers such as pans or trays, lined with absorbent materials. 4.3.1.2 Contaminated glassware Contaminated articles such as used pipetters or stirring rods shall not be laid on a table. They shall _be placed in a stainless steel or enamel tray or other suitable container, lined with absorbent material. 4.3.1.3 Cleanliness - Good general laboratory and plant housekeeping shall be maintained. Practices l which are . undesirable in an ordinary laboratory shall not be tolerated in a laboratory containing radioactive material. i i 4.3.1.4 Spills In the event of a spill, place, do not drop absorbent material on the spill. Advise others in the area to leave the immediate area . Use a survey meter (Geiger-Mueller type) to determine areas of contamination and undertake personnel decontamination action if necessary. The area shall be surveyed and the contaminated area closed off. The spread of contamination will be arrested and then decontamination procedures effected. The area will not be opened until wipes indicate no contamination. l l l e 4-2
' ~
f
- 5. DECONTAMINATION 5.1 Equioment ,
Equipment that has been surveyed, wipe tested and found to be contaminated shall not (mandatory) be used until decontamination procedures are performed. The specific decontamination procedure will depend on the type of equipment and extent of contamination. All equipment, apperatus or tools that are contaminated shall be placed in plastic bags and sealed. Other articles too large ' for bags shall have plastic sheeting applied about each item and all running edges shall be sealed with tape. Personnel performing decontamination are to wear gloves and other protective apparel as recommended by the Health Physicist. The Health Physicist shall perform such surveys and wipe tests to determine the level of radioactivity and several decontamination procedures may have to be performed be.See equipment is released for use. All materials and water or detergents use In the decontamination procedures shall be retained until surveyed by the Health Physicist and appropriate disposal modes approved. In all cases the Health Physicist shall decide upon either a suitable method of decontamination or disposal. Decontamination of all contaminated materials that are not disposed of shall be performed by personnel responsible for the articles. 5.2 Hands and Other Body Parts 5.2.1 Survey meters located in the ZPR room shall be used for monitoring of hands and clothing of individuals suspected of being contaminated. 5.2.2 If hands or face are contaminated: then carry out thorough washing with water and a mild detergent. This may have to be repeated a number of times. Each time (after washing) survey the areas that were contaminated. 5.2.3 If clothing only has been contaminated remove the item in question and wash down the material. When washing, use plastic gloves and take care not to splash any of the rinsing water onto the body. This may have to be repeated a number of times. After each washing survey the contaminated area. t l 5-1 . - - . . - . - - . . . - . - . . - - . . . - - . . _ . -
- 6. WASTE STORAGE AND DISPOSAL 6.1 Waste Disposal
~
The chief cause of radiation exposure to the public is contamination of air and water and great care must be taken in the disposal of radioactive waste. Appendix B of 10CFR20 lists the maximum permissible concentrations of radioisotopes -in air and water for discharge to the environment. No effluent shall be released at any concentration and no waste shall be disposed of except as authorized by the Reactor Operations Committee. In any event, only concentrations at or below - maximum permissible levels listed in Appendix B in air and water will be allowed to escape continuously to the local environment. 6.2 Accumulation of Active Wastes 6.2.1 Dry Waste Cans marked CONTAMINATED WASTE, COLD WASTE and CONTAMINATED GLASSWARE will be provided as needed. These cans shall be polyethylene-lined and shall not be filled so 'as to prevent closure of the polyethylene bag liner. They should be foot-operated in order to reduce the possibility of spread of contamination by handling the lid. Extreme care should be exercised in keeping contaminated waste out of the cold waste cans, and vice versa. The cans will be monitored regularly by the Health Physicist and shall be marked with the normal radiation sign if the radiation field is greater than 2.5 mR/hr at any point outside the can. Persons placing material in the can which has sufficient activity to produce such a field must notify the Health Physicist. 6.2.2 Liquid Waste Five-gallon polyethylene bottles marked CONTAMINATED WASTE shall be provided as needed. Liquid waste should be kept in these containers and not mixed with other waste. A detailed' record of the nature of the liquid and the amount and type of activity in the container must be kept by the appropriate ) supervisor. Physical inventories will be requested. 6.3 Waste Transfer Health Physicist will supervise the transfer and disposal of all radioactive wastes in accordance with policies adopted by the Reactor Operations Committee. Transfer and disposal of such wastes must not be made without the knowledge and approval of the Health Physicist. The Health Physicist will monitor all such wastes and will decide on the appropriate method of disposal. Solid wastes found in contaminated waste cans will be packaged for off-site disposal. Liquid waste will be transferred to 50-gallon drums for storage, concentration and subsequent off-site disposal by a licensed waste disposal contractor. The Health Physicist will keep complete records of the condition and location of all radioactive waste in storage and of final disposition thereof. 6-1
l 6.4 Manuals and Codes Each person, student or faculty, certified to work with radioactivity shall acquire a copy of this manual. - Copies of 10CFR20,10CFR50, and the codes of the State and City of New York, as well as copies of this manual, will be available for inspection at all times upon request. This material will be maintained in the office of the Reactor Administrator or in the Nuclear Facility files. 6.5 Survey Instrumentation Survey instruments shall be maintained in operating condition at all times in the counting room and/or in the zero power reactor room (ZPR room). The equipment shall include:
- low level beta-gamma Geiger-Mueller survey meters;
- cutie pie ionization chambers, (portable), calibrated to read in mR/hr having a range of 1 mR/hr to 20 R/hr;
- one portable neutron survey meter for both facilities.
Equipment shall be calibrated once per year. 6.6 Surveys 6.6.1 Wipe samples of the floor and such other areas as selected by the Health Physicist and/or the Chief Reactor Supervisor shall be performed. The floor areas include the ZPR, graphite, counting and lecture rooms as well as ' connecting corridors and upper level desk areas. Normally this is performed at six month intervals. 6.6.2 Air sampling shall be taken of the areas considered in 6.6.1 above. Samples shall be taken at a rate of at least 2.5 cubic feet per minute for 1/2 to I hour at each location. Normally this is performed at six month intervals. 6.6.3 ZPR water shall be checked at six month intervals. This procedure shall be accomplished employing a. multi-channel analyzer or a scintillation spectrometer. Air and water samples of the reactor area will be obtained prior to operation of the reactor. These will be control values. These values will then be employed and used for comparison purposes of air and water samples taken at the conclusion of each semester in which the reactor has been operational. If lodine-131 is found, Reactor Operator and the Health Physicist will be notified immediately. l 6.7 Protective Supplies A supply of plastic bags shall be on hand at all times in the counting room. A supply of radiation tape will also be maintained. _.___._____-2_-, 6
6.8 Disposal of Pool Water and Demineralizer Resin The pool shall not be drained until the water has been assayed and shown to be at or below tolerance as specified in 10CFR20. The Health Physicist must be notified in advance as to this action. The demineralizer is a concentrator of radioactivity, notably short-lived Na-24 and Mg-27. Used resin can ne.ver be replaced without Health Physic'st coverage and notification. If assay of the resin shows it to be radioactive it will be disposed of in accordance with 10CFR20 par. 20.303, 304. 6.9 Ms The Health Physicist will maintain a bound log book. All entries will be in ink. No erasures are ever to be made. Incorrect entries are to be crossed out, (they must still be legible), and the correction noted above. These logs will be maintained:
- radiation surveys
- wipe records
- air and water tests 6.10 Activation Estimates The literature contains a number of tables and short cut procedures enabling one to make rapid calculations of induced activity as a function of irradiation time andfgx. Vapes for several materials are given below for irradiation in a flux of 10 ng/cm -sec. These values are based on data reported by Kohl, Zentner and Lukuns. [1]
r E l ! i
;
6-3' . . . . . _ . . . . . . _ _ . . .
TAdLE 6.1 Isotope 2200 m/s Specific Fractional activetion eross baturation Saturation section , (barns) Activity . (6) (d/sec gr) 5 min I hr A 1. 2 1.8 x 10 3. 2~ 3~ Ag 30 8. 7 x 10 7. 8 1. 0 Ag ' % 2.6 x 10 1. 0 1. 0 Ag
~
- 2. 3 6.2 x 10' 1'~
1 A1 0.18 4.0 x 10 7.7"' 1. 0
~
Au % 2.9 x 10' 9 1.1
~ ~
Cl 53 6. 9 x 10' 2. 5 ' 3
~
Cl 0. 6 2.4 x 10 9. 2" 6. 7 '
~ ~
Cu 4. 3 2.8 x 10 4. 5 5. 4
~
Cu 2.1 6.0 x 10 5. 4 ' 1. 0
~
Dy 2700 2.71x 10 9. 4 1. 0
2700 2.71x 10 2. 4~ 2. 5
~
Dy Fe 2. I 1.4 x 10 2~ 2. 2 Fe 0.32 1.0 x 10 $'
~
6.1
~
~
H' O.00065 3.I x 10 6. 2 7. 7 in" 61 1.4 x 10 5'~ ~
- 6. 4 *
~
In' 2 4. 5 x 10 9. 5 ' 1. 0
~
in 145 7.0 x 10' 6. 4~ 5. 3 ' In" 52 2.6 x 10' 't. 0 1. 0 Mn 12.8 1.4 x 10' 2. 2~ 2. 4 No 0. 5 - 1.3 x 10 4~ 4. 6~
~
Pb O.00045 6.8 x 10 ' 1. 7~ 1.9"'
~ ~
S 0.26 1.9 x 10 3. 3 ' 3. 3 S 0.14 3.7 x 10
~
5'~
- 1. O
~
P 0. 2 3. 9 x 10 1. 7~ 2
~
Cd 1. 0 6. 9 x 10 8 1
~ ~
Cd ' ' 0. 2 1.4 x 10 7 5. 7 ' Cd O.14 2.1 x 10 6'~ 7
~
Cd 1. I 1.7 x 10 l' 1. 2"
~ ~
Cd 1. 4 5.5 x 10 2 2. 2 I J Radioisotope Appilcations Engineering by Kohl, Zentner and Lukens, D. I Van Nostrand Nuclear Science Series 1961 Values apply for a flux of 106 n th / cm2 ,, 6-4
6.11 Exampla Probitms 1 An example will illustrate the use of this table. One gram of natural In is 6 irradiated for one hour in a flux of 10 . What is the activity due to 54 min 116m immediately post irradiation? In I Solution: One gram of In contains 0.9562g of the parent isotope In . From the 5 above table, the specific saturation activity is 7 x 10 dps/g and the fractional 116m saturation 0.53. The In activity is then: (7 x 10 5)(9.5~62 x 10-1)(5.3 x 10-1) = 3.55 x 105 dps The curiage is: 3.55 x 10 510 = 9.59 x 10 -6 C1 3.7 x 10 116m It is the curie value which must be reported. or 9.6 pC of In . These-tables can and should be used to arrive at an estimate of count rate. The best irradiation time can then be computed and scheduled. Example: The above Indium specimen will be counted 54 minutes post irradiation using a NaI(TI) well crystal and a single channel analyzer set to "see" only the 0.87 MEV gamma, (28% abundant). What is the anticipated count rate per minute if the detector efficiency is 24%? Solution: , Let CR = Count rate.
' 5 1 CR = (3.55 x 10 )(5 x 10-1)(2.8 x 10-1)(2.4 x 10-I)(6 x 10 )
CR '= 7.158 x 10 5/ cpm = 715,800 cpm. I. r I 65 . . . - . . - - - . . - - - . . . , .
-a 6,11 Example Problems (cont'd)
The table should also be used to estimate dose rate. This 1:: an excessively high count rate. Under certain conditions deadtime corrections may be necessary and spectrum distortion is possible in scintillators at high count rates. Since only the amount of radioactivity necessary to achieve a given goal should be generated, the activity of the Indium specimen should be reduced. The variables controlling induced activity are: irradiation time; flux; and exposure time. If a milligram of Indium is exposed instead of one gram, the count rate will drop to 716 epm. Under the stipulated counting conditions, assuming a background of 10 epm, the sample can be easily counted. The sample percent error as a function of a background and the total counts should be calculated and an optimum count determined using the curve published by Loevinger & Mones, (Nucleonics, July 1951). Example: 6 10 g of Al are irradiated for ene hour in a flux of 10 and removed 2.3 minutes after irradiation ceases. What is the dose rate? Solution: Assume a point source and no flux depression in the target. Apply the formula: D = 6CE where C is in curies, E in MEV and D in R/hr. 28 is formed by the (n, gamma) reaction with 100% abundant A127; the half A1 28 28 life is 2.3 minutes. A1 decays by beta emission to stable Si emitting a 1.8 j MEV gamma in 100% abundance. From the above table, the saturated activity of A1 28 will be 4 x 103dps/g. 3 C = (4 x 10 )(1 x 10 )(5 g 10-1) = 1 2 x 10 4 g 3.7 x 10 3.7 x 10 C = 5.4 x 10'I Ci D = 6CE = (6)(5.4 x 10'I)(1.8) D = 5.8 x 10 R/hr. 6-6
6.11 Example Probinms (cont'd) D = 5.8 x 10 -3 mR/hr. l 28 The 10g of'A1 do not represent an external hazard and a good count rate even ] for 1% efficiency and the lapse of two additional half lives can be obtained, (3,000 epm). 1 Inhalation hazards may also be estimated. Problem: A 1 cu. in. chamber containing air is irradiated for one hour in a thermal l 6 flux of 10 and opened immediately post irradiation in a confined space ! providing a volume dilution of 100. Does an inhalation hazard exist due to A 417 Solution: Air contains 0.94% by volume of A, (density is 1.78 g/l at STP). At STP, the 4 chamber contains 2.74 x 10 g of A. The saturatfor. activity is 1.8 x 10 d/see-g or (1.8 x 104)(2.74 x 10 )(3 x 10-1) = 1.479 dps. The unit volume activity is 9.03 x 10 -2 dps/ce. Since the dilution factor is 100,
-14 this becomes 9023x 10 dps/ce. The unit volume curiage is 2.44 x 10 Ci/cc ,
or 2.44 x 10 -8 pc/cc. The MPC for A 41 as given in Table II of Appendix B of 10CFR20 is 4 x 10 pc/ml and 2 x 10 in Table I of this reference. Assuming one mi equals one ec, a non-occupational hazard exists while an occupational one l does not. l I 1 l 6-7
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l 1 l APPENDIX B PLAN FOR TRAINING APPLICANTS TO PREPARE FOR A l- REACTOR OPERATOR'S LICENSE FOR MANHATTAN COLLEGE ZERO POWER REACTOR I l l i. ! B-1 f 1
t . - Plan for Training Applicants to Prepare for :: Reactor Operator's License Examination for Manhattan College Zero Power Reactor TABLE OF CONTENTS Page
' Preliminary Phase 1
!~ Familiarity with all Physical Aspects of 1 the Manhattan College Zero - l Power Reactor Operational Training 1 Reactor Console Checkout 1 Achievement of Criticality 2 Shutting Down and Securing Reactor 2 4 Bypass switch for Gamma Ray Recorder 3 Reactor Period and Reactivity 4-Preparation for the Written Examination 4 l NRC Operator Licensing Guide 4 Facility License No. R94 and 5 Technical Specifications t Application Procedure -5 j l Final. Preparation for Examination 5 l Plan for Training Applicants to Prepare for a Senior 6 Reactor Operator's License Examination for MCZPR T l. L i I
-- . . ~ . . . -
if' Manhattan College Zero Power Reactor Preliminary Phase If the applicant has not had a course in Nuclear Reactor Engineering, he should be guided through an intensive study of " Elementary Introduction to Nuclear Reactor Physics" by S. E. Liverhant, (Wiley, 1970). This study should include multiple problem solving as well as theory. (It should
- be noted that some of the units used by Liverhant are obsolete). The study l
of Liverhant's text should be complemented by a study of chapters 5, 6, 7, and 9 of " Introduction to Nuclear Engineering" by John R. Lamarsh, (Addison-We sley, 1975 ). When the instructor is satisfied that the applicant I has sufficient mastery of the above material, the applicant may proceed with the exercises indicated below. If the applicant has already completed a course in Nuclear Engineering, he may pursue the following exercises and studies without the preliminary
- procedure outlined above.
Familiarity with all Physical Aspects of the Manhattan College Zero Power Reactor The applicant should become so familiar with all the physical aspects
- of the Manhattan College Zero Power Reactor as to be able to diagram any component or set of components from memory. To achieve this end, the following printed n aterial on file should be used as guides: (1) The lecture demonstration experiment for M. E. 433 entitled, "Startup and Operation Procedures of the Manhattan College Zero Power Reactor"; and (2)%eactor Console Checkout Sheets".
l l Operational Training The operational training should be conducted by a licensed . Senior Reactor Operator. Reactor Console Checkout It is very important not to hurry the candidate during the early stages
- of his training. Thoroughness of understanding rather than speed of comprehension -
l should be stressed during this period. At least four sessions should be spent l- on the Reactor. console using the checkout sheets before any entry is made in the i
i Reactor Operations log book. Each of these sessions should carry the candidate a little further in the checkout until he is able to complete the entire checkout in one session. Achievement of Criticality . After the candidate has been able to complete the entire checkout in one session, one or two additional periods should be devoted to nothing more than this with entries made in the Reactor Operations log book. i l Next, there should be two periods devoted to making the reactor critical with the picoammeter reading about 5.0 X 10-9 amperes. This current reading will guarantee that the needle of the picoammeter and the pen of the linear strip chart recorder are both near the middle of their respective scales, thus guarding against a high or low trip causing an unintentional scram or reverse. After having completed the checkout and before starting to raise the control rods the stamp marked " Reactor Critical" should be i used on the Reactor Operations log book, each of the strip chart recorders ' should be initialed, marked with the date and time and the chart drive turned on. As the control rods are raised, the picoammeter will indicate an increase in the reactor power. When the needle goes above 7 on the upper scale, the scale selector should be raised to the next higher setting; as for instance, from 10 X 10-10 amp to 3 X 10-9 amp, from 3 X 10-9 amp to 10 X 10-9 amp. Close attention should be paid to recording the times for i " Source Out" and " Source In". The Reactor will be considered critical when the neutron source has been withdrawn and the pen mark on the linear strip chart recorder has continued in a vertical direction for at least one l quarter inch. l
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Shutting Down and Securing Reactor After criticality has been achieved, the supervisor will direct the trainee to shut down the Reactor. This will be done by pushing the "Run In" button and flipping the toggle switch for the Source Control to the "Down" po sition. As the control rods are inserted, the picoammeter will indicate a decrease in reactor power. When the needle reaches a point slightly above 2 on the upper scale, the scale selector should be switched to the next lower setting; as for instance, from 10 X 10-9 amp to 3 X 10-9 amp, from 3 X 10-9 amp to 10 X 10-10 amp, etc. When the green "Down Limit" lights go on, the time should be recorded in the Reactor Operations log book with the notation: Reactor shut down by "Run In". The supervisor should then direct the trainee to secure the Reactor. This is done by first turning off
l 3 - the " Reactor On" key, then the " Power" switch and all other switches including the Master switch and finally locking the doors on the back of ' the console. 'After delivering the key to these doors and the " Reactor On" key to the supervisor, the trainee should record the time in the Reactor 4 Operations log book and enter the notation: " Reactor secured". The i supervisor should then enter his approval and signature in the Reactor Operations log book. ! Bypass Switch for Gamma Ray recorder l
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The next exercise for the trainee goes one step beyond the simple achieving of criticality with the pi'coammeter reading about 5 X 10-9 amperes. After criticality has been achieved at this setting, the reactor is made j supercritical and again made just critical with the picoammeter reading about 1. 5 X 10-8_ amperes. The trainee should be alert to raise the scale
. selector to the next higher setting as the reading rises above 7.0 X 10-9 ampere s. , The selector switch is set so that the Area Radiation Monitor #2 feeds into the Gamma Ray strip chart recorder. The low level trip on the recorder is at. 0. 2 mr/hr. In order to avoid a reverse during the early stages of operation, the gamma recorder low value reverse bypass switch is turned on as specified in B-2 of the Reactor Console Checkout Sheets It will be noticed that when the picommmeter reading is about 1. 5 X 10 g amperes, the reading on the Gamma Ray . ecorder is considerably above 0.2 mr/hr.
Technical Specifications 13a states: " A bypass to eliminate a reverse as a consequence of the gamma recorder being down scale may be utilized during startup until the gamma recorder reads on scale". The clear implication 4 here is that once the recorder pen " reads on scale", the bypass switch must be turned off. However, this cannot be safely done as soon as the average position of the pen passes above the 0. 2 mr/hr mark,- since there would still be considerable " noise" below the 0. 2 mr/hr mark. Therefore, the operator must wait until he judges that all of the " noise" is also above the 0. 2 mr/hr l mark before turning off the bypass switch. After pressing the "Run In" button
- to shut down the Reactor, the opposite situation holds. The operator must be careful to turn on the bypass switch before the " noise" reaches the 0. 2 mr/hr i mark. _
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4 - This exercise involving criticality with a reading of about l 1.5 X 10-8 amperes on the picoammeter should be repeated at least three times. , i Reactor Period and Reactivity The next series of exercises for the trainee is based on the experiment for M. E. 434 entitled, " Reactor Period and Reactivity". There are Ifiree steps in'
~~
l the Procedure of this experiment. Step 1 should be followed during two training periods; Steps 1 and 2 should be followed during two additional training periods; and Steps 2 and 3 should be followed during another i two training periods. Steps 2 and 3 should be repeated many times during l the preparation for the written examination. Preparation for the Written Examination NRC Operator Licensing Guide The Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission has prepared an "NRC Operator Licensing Guide", which is "A Guide for the Licensing of Facility Operators, Including Senior Operators". Pages 4 to 6 and 18 to 23 of this Guide (1976 Edition) describe in general terms the content of an Operator written examination. The applicant should read over this material without attempting to memorize any of it. Pages 90 to 98 of this Guide contain typical sample questions for Operator examinations. The applicant should write the answers to all of these questions in a notebook, including the questions marked with asterisks. To
- obtain the answers to these questions, the following references may be used
Introduction to Nuclear Engineering by John R. Lamarsh (Addison-We sley, 1975) Basic Nuclear Engineering (second edition) by Arthur R. Foster and Robert L. Wright, Jr. (Allyn and Bacon, 1973) The Elements of Nuclear Reactor Theory by' Samuel Glasstone and j Milton C. Edlund ( Van Nostrand,1952) ! Nuclear Reactor Engineering by Samuel Glasstone and l Alexander Sesonske (Van Nostrand,1967) 10 CFR Part 20, Standards for Protection Against Radiation 3
. - . = - . -
After the applicant has written the answers to all the questions contained on pages 90 to 98 of the Guide, these questions should be used repeatedly by the supervisor in catechising the applicant. I Facility License No. R94 and Technical Specifications , j l The applicant should 'also be thoroughly familiar with the contents of the Facility License No. R-94, the Technical Specifications for the Manhattan College Zero Power Reactor, and all of the changes which have been made in these two documents. Application Procedure ! The following letters should be sent to Mr. Paul F. Collins, Chief of the Reactor Licensing Branch, Division of Project Managemet.t, U. S. Nuclear Regulatory Commission, Washington, D. C. 20545. From the applicant stating that he wishes to take the Reactor Operator licensing examination. From the Chief Reactor Supervisor, stating that the applicant has received sufficient training and is qualified to take this examination. From the Reactor Administrator stating that the services of the applicant are needed for the efficient operation of the Reactor facility. The applicant and his physician must fill out the Certificate of Medical History, which he will receive from NRC. The date for the examination is fixed to suit the convenience of the applicant and the NRC examiner. Final Preparation for Examination Shortly before the time for the Reactor Operator examination, the applicant should be quizzed on all aspects of the examination by someone
competent in Nuclear Engineering other than his training supervisor. During the week prior to the examination, he should perform three times
. steps 2 and 3 of the Procedure of the experiment " Reactor Period and i Reactivity".
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Plan for Training Applicants to Prepare for a Senior Reactor Operator's License Examination for MCZPR The following directives are in addition to those ma'd e for the Reactor Operator examination. Pages 6 to 8 of the Guide describe in general terms the content of a Senior Reactor Operator written examination. The applicant should read over 'J21s material without attempting to memorize it. Pages 99 to 106 of the Guide contain typical sample questions for Senior Reactor Operator examinations. The applicant should write in a notebook the answers to the following questions: Section H Nos. I thru 4, 7a, 7c,and 8 Section I Nos. 1, 2, 5, 6, 7, and 8 Section J Nos. 4, 5, and 7 Section K Nos. 2, 4a, 5, 6, and 7 Section L Nos. 4, 5, 6, 7 and 8 The questions omitted are intended for operators of nuclear power plants. l
APPENDIX C CURRENT OPERATOR'S-LICENSES I i C-1
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U.S. NUCLEAR REGULATORY COMMISSION E E I I SENIOR OPERATOR LICENSE I9 I l li Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 & I (Public Law 93-438), and subject to the conditions and limitations incorporated herein, the Nuclear E l Regulatory Commission hereby licenses: I
* * (RE!!&!AI.)
LICENSE NO. S 0 P - 1420-6 Brother Cabriel Kane l s l I'.anhattan College DOCKET NO. 55 - 292S i Bronx,!!ew York 10471 ,1 EFFECTIVE l11 DATE trovenbar 18, 1982 ll b l AMENDED DATE
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to direct the licensed activities oflicensed operators at, and to manipulate all controls of, the following facility or facilities: l i i l'.anhattan College Zero Power Reactor, Facility License flo. R-94 i i located at Bronx. !!ew York I e This license is subject to the proIrisions of Section 55.31 of the U.S. Nuclear Regulatory Commission's REGe, !
'N regulations, Title 10, Code I as if fully set forth hereind,o'ffecTeral Regulations, # Chapter 1, Par'i35', with the sam l
t - In directing the licensed activities oflicensed operators and in manipulating the, controls of the above
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facility or facilities the licenDee'shall observe the operating procedures 'an'd other conditions specified in I - the facility licens[wliich authorEzes c'peration of the facility'or' facilities, and shall comply with the following conditions: 8llT k.5
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SN [\ @ I# f) 3 E gThe licensee shalf wear correctiire efegla/sses while performing the activities for which he is licensed f' O I~~ d$ %(b L 3E0' , / .' % g h$k3 $ ) The issuance of this licenseis basedtpon examination of'the licensee's qualifications, including the i ! !. r f- .
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representations and'iliformathn[ccin'tain[lTn his app [lication for licensIfiled under the docket numberf indicated above. yE. , .; r e . ;..,- < - ., Unless sooner terminated, this license shall exp.. : ire two years from the effective date. .
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-A A copy of this license has been made available to the facility licensee indicated below.
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g.anhattan College For the Nuclear Regulatory ATTH: Reactor Ailinistrat4r mmission
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Physics Departraent Sronx. flew York 10471 - ' L N O . rect + =. Chief *
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___._____________________________.__._.___________..c.m_; . U.S. NUCt. EAR REGULATORY COMMISSION i SENIOR OPERATOR LICENSE l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 438), and subject to the conditions and limitations incorporated herein, the Nuclear Regulatory Commission hereby licenses: 3551-1 Dr. Joseph Augustus 110 Delaware Road DOCKET NO. 55 - 6366 Yonkers, NY 10710 EFFECTIVE December 7, 1982 DATE l AMENDED DATE to direct the licensed activities of licensed operators at, and to manipulate all controls of, the following facility or facilities: Manhattan College Zero Power Reactor, Facility License No. R-94, located in the Bronx, New York R
'cns ofAB REGf l Thislicens is subject to the grp Section 55.31 of the . Nuclear Regulatory Commission's I regulations, Title 10, Code.oUb ral Regulations, Chapter 1, Pa . ph the same force and effect as if fully set forth here' .
In directing the licensed crivities oflicensed operators and in man
- ulating controls of the above I arIf otherIonditions specifiedin b l facility or faciliti Ncens e'shk 1 observe the operating procedu l the facility lice dich authon*zck ation of the facili [o[aciNties, andjhall comply with the following condit - 5 -
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@Thelicensee s wearco ecti e sses.w ildperforming e,activities for which he is licensed. g D h j &
'cens<e 3 based'bpon b t r D The issuance of th mation oi!xam.k e licens' s qualifications, including the ~
representations an forma' tionc# IntaineOn hi'slip'plicatio'n for licdiise filed urider the docket number Unless sooner terminate (this license shall expirgtwo years from the efrec ve date. l
% 4 A copy of this license has been made available to the facility licensee indfcated below, o
Manhattan College h3d 8
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- d For the Nuclear Regulatory y
ATTN: Reactor Supervisor Commission J Mechanical Engineering Department / f i l Manhattan College Parkway u/ M' f Bronx, New York 10471 ,, Don H. Bec Chief lp RfXHNXRdHfGkHHfRMXhfDX iF XuxunnknRxnnRxdx:en 5 Operato_ r Licensing Branch [ TavaT.ITaT.T.T aT sat.T ET.T.T.T.T.:r T'saTaus.rsTa? e : 5"
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C1*1Tri'1*1T1*iT'li. ETAT 1*.EST1TA%T1W1Ti^1*EITET1WITAEWi#14%%% i U.S. NUCLEAR REGULATORY COMMISSION k h h OPERATOR LICENSE g d Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and subject to the conditione and liraitations incorporated herein, the Nuclear Regulatory ( Commission hereby licenses: h N (RENUPIL) LICENSE NO. O P - 5270-1 l Dr. Robert A. Mayo y 62 Noodland Avenue DOCKET NO. 55 - 7287 5 Veronas New Jersey 07044 W EFFECTIVE h D6TE July 15s 1902 l b AMENDED DATE l i to manipulate all controls of the following facility or facilities: Manhattan College Zeroe Power Reactor, Facility License No. R-94s located in Riverdale s New York , 7
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v-This licenso is subject to the provisions of Section 55.31 of the U.S. Nuclear Regulatory Commission's I
; regulations. Title 10. Code of rederal Regulations. Chapter 1. Part 55, with the same force and effect as l if fully set forth herein.
hi ll In manipulating the controls of the above facility or facilities, the licensee shall observe the operating l procedures and ot'aer conditions specified in the facility license which authorizes operation of the l facility or facilities and shall comply with the following'condi' ions: le l r y l b The licensee shall wear corrective eyeghasses hile performing the activitics for which he is licensed. b B . l ..
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g ,-r ..g 72 4 , s The issuance of this license is based ujzon examination of the licensce's qualifications, including the k g representations and information contained in his application for license filed under the docket number indicated above. "
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l Unless soenar terminated, this license shall expire two years from the effective date. A copy of this license has been made available to the facility licensee indicated below. y . . Manhattan Colle e vor the Nucicar Regulatory ATTN: Reactor dministrator . Commusion ) l N q Mechanical Engineering Departrlent Manhattan College Farbfay '
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~ % _. ~ . s c1.[ t lI Riverdalee New York 10471 Don H. Reck! Lam. Chief l kkkkkkkkkkkkkkkYkkkkkkk d q Operator Licensing Branch h j h m T Zr y >= 5--G r.r m ~r2r.r a r m rJiC @ M 2.r s r.T.r a a. G M iEr a A Y a a_ M d l FACIUTY UCENSEE S COPY
9 i APPENDIX D REACTOR CONSOLE CHECKOUT SHEET l l l l I D-1 . l
l MANHATTAN COLLEGE ZERO POWER REACTO'R REACTOR CONSOLE CHECKOUT SHEETS (Revised: July 1983 - ) Reactor console checkout is to be performed once on each day during which the reactor is to be operated (f.e. with control rod movement more than 10%) and before all reactor operation.
' At the end of these checkout sheets, space hs.s been provided for notations on CORRECTIVE ACTIONS AND ADDITIONAL COMMENTS.
Any variation from normal conditions for a particular entry in the checkout sheets should be marked with an asterisk (*). This asterisk will signify: See ' CORRECTIVE ACTIONS AND ADDITIONAL COMMENTS. Date Checkout i Checkout started
- Authorizing Supervisor Reactor Operator on duty Pre-checkout - Groups A, B, C and D
- (REACTOR key switch off)
Group A. General . Check / Note A-0. Check the Operation and Maintenance Record Book A - 1. Turn on the console circuit breaker and all instrument power A-2. Make an inspection tour of the reactor to l check that !- (a) the tank water level is normal (about 7') t (b) all physical facilities of the. reactor normal (c) ch'eck that the reactor basement door is closed and latched l
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c A-3. Record loading number. The core loading shall be #13, #13A or any other loading specifically approved by the reactor supervisor on duty
' A - 4. Check that the portable radiation survey instruments
. are functioning properly A - 5. Check that the neutron source is in the most effective position (IN).
A-6. Record , (a) UIC (uncompensated ion chamber) voltage (normal reading 28 corresponding to 270 V) (b) BF-3 counter voltage V.D.C. (c) Water temperature deg.F (d) Reactor water resistivity Mil-cm Group B - Magnet Power and Annunciator Lights M- 1. Turn POWER switch on. The audible alarm should sound. Silence it by pressing the ' green ACKNOWLEDGE button. All annunciator lights should go on. B-2. Turn the gamma recorder low value reverse ' l bypass switch on l Reset the two gammh radiation AREA 'RADIATON MONITORS (the two large red ALARM lights
.should go out).
Press the black RESET button. All annunciator lights should go off except the SCRAM light. If the REVERSE light stays on, press the red RUN-IN button once. l_ The 2 green DOWN LIMIT lights should be on. B-3. Record the magnet power supply voltage (normally 24 V). VDC e
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l 1 1 Group C - Calibration of Rod position Indications C - 1. Set the FINE POSITION INDICATOR TO 00.0%. While pressing the black button under the coarse indicator for the Reg Rod, adjust the ZERO ADJUST potentiometer R2 so that the NULL INDICATOR indicates zero (center of scale).' Adjust the REG. ROD ZERO ,, ADJUST potentiometer R6 so that the REG. ROD l
. coarse indication indicates 0%.
NOTE: Sometimes it may be necessary to re-cycle the above several times. Under certain conditions, the use of the potentiometers R8 and R9 may be necessary. C-2. Repeat C-1 for the SHIM ROD using , potentiometers R12 and R16. C-3. Drive the magnets to the uppermost position (the UP LIMIT amber lights should go on) while setting the FINE POSITION INDICATOR TO 100. 0%. While pressing the black button under the coarse indicator for the Reg Rod, adjust the REG. ROD SPAN ADJUST potentiometer R1 do that the NULL INDICATOR indicates zero. Adjust the REG. ROD SPAN ADJUST potentiometer R3 so that the REG. ROD corase indicator indicates 100% NOTE: Sometimes it may be necessary to re- ~ cycle the above several times. Under certain conditions, the use of the potentiometers ~R8 and R9 may be necessary. C-4. Repeat C-3, for the SHIM ROD using potentiometers R11 and R13. 1- C-5. Press RUN-IN button and check that the REVERSE I light comes on and that the magnets are driven down until the DOWN LIMIT green lights come on. Re-store the REVERSE circuit to normal by pressing i the RUN-IN button. 4 i
- . - , - . -. -.. . - - . . _ - ~ . . - . - . - - . . - - - . . - _ . - - - _ - - - . . . - - . --,
Group D - Instrument Calibration and Readings D- 1. Linear Channel With the picommmeter range switch at the most . sensitive position for on-scale reading (3 x 10-10A), press the ZERO CHECK button while turning the ZERO dial so that the red pointer of the meter indicates zero. Meter reading after zero check. 1. D-2. Scaler Turn the TEST switch on (up). Reset the scaler. (Press the black button first, then reset the
' register). Take a one-minute count (normally about 3600).
Turn off (dowq the TEST switch. Reset the scaler. With the source in the most effective (IN) position take a one-tninute count. , D-3. I.og count rate meter Check that the range . switch is on 10 counts /sec. Push CAL switch lever to 100 (right). The stable meter reading will be close to 100. If it is not exactly 100, use the adjustment screw in the slot below "F. S. AOJ", to bring it to this position. Push CAL switch lever to 10 (middle). Record the stable meter reading (it should be close to 10). Do not use the , adjustment screw here. . ! Turn the CAL switch lever to INPUT l l D-4. Gamma monitor Check that the meters on the two AREA RADIATION MONITORS indicate nearly zero. i Checkout - Groups E, F and G (REACTOR key switch on) j Group E - Control Rods E - 1. Turn the REACTOR key switch on. The REVERSE l light will go on. Press the RESET button. 'The ! SCRAM and REVERSE lights should go out. The 2 MAG CURRENT meters should indicate a current. The 2 white ON MAGNET lights should . be on. I
i
- 5'-
E- 2. Drive the two control rods up 10% (DOWN LIMIT lights out, ON MAGNET lights on) by pushing the two DRIVE CONTROL switches up. Turn the MAG. ADJUST potentiometer for the REG. ROD counterclockwise until the control rod falls off by gravity. Record the minimum rod holding l magnet current. Repeat the same for the SHIM ROD Drive the magnets back to the lowest position. Increase the magnet current to approx. 25 ma above the minimum holding current. E-3. Drive the control rode up 10%. Press the 6 ROD RELEASE button for the REG. ROD. Note the dropping of.the rod. The ON MAGNET light should go out. Repeat the same for the SHIM ROD - Press the RUN-IN button once. When the magnets reach the down position, press the button again. REVERSE light should go out.. Group F - Scram Circuit Tests In each test, press RESET button, drive both j rods to 10%, initiate the particular scram condition and note the dropping of the two control rods. When the scram condition is removed, the magnet drive is automatically put on REVERSE. i Scram condition Test OK F- 1. Loss of magnet power: Turn REACTOR switch off. After the rod drop, turn it on. (Audible alarm does 2.ot sound)'. i
F-2. Manual scram: Press the red SCRAM button. 0
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F-3 Water level low: Using a rod, push lightly dcwnward the float switch in reactor water. F-4. Gamma channels intensity high: Turn the alarm setting on the meter of the #1 gamma monitor to 1 mIVh. . Press the CalECK button and hold until the meter indicator reaches 1 mR/h and sets off the scram. After pressing the ACKNOWLEDGE buttag presa the RESET button on the #1 gamma monitor. Return the alarm setting of the meter to 6 mIVh. Repeat the same for the #2 gamma monitor.- Return the alarm setting of the meter to 10 mWh. F-5. Linear channel flux high: By use of microwave switch in back of console, disconnect the input cable to the Keithley picoammeter and connect the current source for linear channel testing to the input. Turn the potentiometer connected with Current Source fully counterclockwise. While pressing the blac k button on the Current Source. press the Reset button on the console and drive the rods to 10% While continuing to press the black button on the Current Source, increase the current indicated on the picoammeter by turning the potentiometer on the current source clockwise until.the reactor is scrammed. The scram should occur at 90% point of the meter range. Ahee+he test disconnect the current source and connect the cable to the picommmeter by means of the microwave s' witch. F-6. Log count rate channel flux high: Turn on the two toggle switches of the Heath Audio Oscillator in back of console. With OSCILLATOR FREQUENCY on front of console fully counte. clockwise, press the RESET button on the console and drive the rods to 10% Incrck the indication on the log count rate meter or L4e LCR recorder by using the OSCILLATOR FREQUENCY and OSCILLATOR ' AMPLITUDE controls until the reactor is scrammed. The scram should occur at 10,000 cps. l T'urn the two toggle switches on the Heath Audio Oscillator to the OFF positions
Group G - Reverse Circuit tests Three reverse conditions for each recorder are to be tested: a) I.oss of power to the recorder: This is simulated by turning INST. POWER switch off. b) Recorder indication too low - A backset switch is actuated. c)' Recorder indication too high - A backset switch is actuated. The last two conditions can be obtained by turning the MAIN DRIVE GEAR (See Instruction Manual Electronik 18 Strip Chart Recorder) manually when the recorder power is off. But to test the corresponding reverse circuits, 'it is necessary to bypass the REVERSE interlock contact due to the condition a). This is achieved by flipping down a bypass switch in the rear of the console. ISwitch K101 for LCR recorder, K102 for LIN recorder. K103 for GAMMA recorder). , In each test, press RESET button, drive both rods to.10%, initiate the particular reverse ::ondition and note the driving in of the two control rods. After the test's, the bypass switches should be returned to normal (up) po sition. G- 1. Log count rate channel (a) (OFF) (b) (2 cps) (c) (50,000 e ps) G-2. Linear channel recorder (a)(OFF) (b) (5%) (c) (95%) G-3. Gamma channel recorder (a) _(OFF) (b) b. 2 mR/h ) (c)(95 mR/h) Have the bypass switches been flipped back to normal position? K101 K102 K103 - Camma Recorder
- 8-i i
If the reactor is not to be operated right after the checkout ! and the operator has to leave reactor room, secure the reactor by turning off (a) the REACTOR ON switch and remove the key (b) the POWER switch (c) all instrument power switches, high voltage switches, chart drive switches (d) the console power circuit breaker and locking the console doors. Surrender all reactor keys to the Reactor Supervisor in charge. CORRECTIVE ACTIONS and ADDITIONAL COMMENTS (Refer to group letter and number for all entries). l Checkout completed at
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Record the completion of checkout on the log book, i I Approved by Reactor Supervisor 9
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i i I APPENDIX E EMERGENCY PLAN: ST. JOSEPH'S HOSPITAL AGREEMENT (St. Joseph's Agreement is Appendix 3A of Emergency Plan) I I E-1 [ t
1 1 THE EMERGENCY PLAN ! FOR THE MANHATTAN COLLEGE ZERO POWER REACTOR Facility Operating License: R-94 Ibcket No: 50-199 August 1983 e h w w - w ~ ---.-.,-,n .,,,.,.,,-,,-,n- , , , . - , . z-.- ..g.e, , . . , , , c.-,,n...g.,.., , . , . , n.,,,,-+,w, - ,- , ,
l TABLE OF CONTENTS I Page
- 1. 0 Introduction 1
- 2. O Definitions 6
- 3. 0 Organization and Responsibilities 12
- 4. 0 Emergency Classification System 17 5.0 Emergency Action Levels for 22 Notification of Unused Events 6.0 Emergency Planning Zone 23
- 7. 0 Emergency Reaponse 24 8,. 0 Emergency Facilities and Equipment 27
- 9. 0 Recovery 29 10.0 Maintaining Emergency Preparedness 30
LIST OF FIGURES Figure No. Page 1.1 Map of Area Surrounding the Leo Engineering Building 2
- 1. 2 Location of Leo Engineering Building 3
- 1. 3 Plan of First Floor of the Leo Engineering Building 4
- 1. 4 Plan of Second Floor of the Leo Engineering Building 5 2.1 Plan of First Floor of the Leo Engineering Building 7 showing the ZPR Room (Cross Hatched) 2.2 Plan of Second Floor of the Leo Engineering Building 8 showing the ZPR Room (Cross Hatched)
- 2. 3 Plan of First Floor of the Leo Engineering Building 9 showing the MCZPR Facility (Single Hatched)
- 2. 4 Plan of Second Floor of the Leo Engineering Building 10 showing the MCZPR Facility (Single Hatched)
- 2. 5 Plan of Second Floor of the Leo Engineering Building 11 showing Emergency Support Center (Cross Hatched) 3.1 - MCZPR Normal Operating Organization 13
- 3. 2 MCZPR Emergency Organization Chart 14 7.~ 1 Location of Emergency Organization Chart 25 8.1 Emergency Support Center (Shown Cross Hatched) 28 7
I- . - - . . . - _ -- . . - . . - -- - - _ . . . . . . _ _ . . _ - _ , _.
( ,m. 1 -
- 1. 0 INTRODUCTION 1.1 This Emergency Plan applies to the Manhattan College Zero Power Reactor (MCZPR). The reactor is owned a'nd operated by the Manhattan College Corporation of Bronx, New York,10471. Under Facility Operating License R-94, Docket No. 50-199.
- 1. 2 The objectives of this plan are to designate responsibility among the reactor personnel and establish guidelines of action in the event of an accident or incident at the reactor that may present undue risk to the health and safety of individuals, or result in damage to the property. The plan also identifies off-site support '
organizations that may be activated if required.
- 1. 3 The MCZPR is a U-235 fueled light water moderated open pool type heterogeneous reactor with plate type fuel elements. The l
reactor tank is 8 ft. high and 10 ft. in diameter. The core consists of 15 full fuel elements and one partial fuel element. Each full 4 element consists of six fuel plates containing 200 gm of uranium and the partial element contains 25 gm making a total of 3025 gm of uranium. The reactor is licensed to operate at a continuous maximum power of 0. I watt. Because of the very low power level, no recirculating cooling system is provided.
- 1. 4 The MCZPR is a research reactor. The major functions of the reactor are training of reactor operators and for experimentation as l
part of Nuclear Engineering courses offered at Manhattan College.
- 1. 5 The reactor is operated whenever needed for training or for class experiments. All experiments performed on the reactor require prior approval of a Reactor Operations Committee. The Committee closely monitors all experiments performed on the reactor. Based on the operating history of the past three years, the reactor was made critical about 34 times a year with each critical operation lasting an average of 16 minutes. The power levels were raost often well below
. the licensed level of 0. I watt. ' ;
- 1. 6 The MCZPR is located in the Bronx, New York. It is easily accessible from Interstate Highway 87 and the ' Henry Hudson Parkway by connecting roads. An area map is given in Figure 1.1. The reactor is housed in the Leo Engineering Building on Corlear Avenue between 238 Street and 240 Street. Figure 1. 2 shows the location of the Leo Engineering Building. The reactor facility occupies portions of the first and second floors of the Leo Engineering Building. The floor l
, plans are shown in Figures 1. 3 and 1. 4. Access to the facility is either through door D ion the first floor or through D4 on the second floor. Access door D is 3 kept locked and bolted from inside at all times.
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- 2. O Definitions 2,1 MCZPR MCZPR stands for the Manhattan College Zero Power Reactor located in the Leo Engineering Building of Manhattan College.
- 2. 2 ZPR Room or Reactor Room Consists of rooms on the first and second floors in the Leo Engineering Building in which the reactor is built. The area is
- shown cross hatched in Figures 2. I and 2. 2
- 2. 3 MCZPR Facility or Reactor facility Consists of the ZPR room and rooms 107, 108 and 109 on the first floor and room 221 on the second floor which are shown single hatched in Figures 2. 3 and 2. 4.
- 2. 4 Emergency Support Center Consists of the platform area of room 221. This is shown in Figure 2. 5.
- 2. 5 Reactor Operations Committee (ROC)
The ROC consists of the Reactor Administrator who acts as the Chairman of the Committee, the Chief Reactor Supervisor,
. Health Physicist, Radiation Safety Officer and others who might be helpful in the operation of the reactor and appointed to the Committee by the. Reactor Administrator.-
- 2. 6 NRC Nuclear Regulatory Commission.
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12 -
- 3. 0 Organization and Responsibilities The Manhattan College Zero Power Reactor Emergency Plan is designed to provide a means of meeting the additional demands that would be encountered if an emergency situatim arises. To effect this goal an Emergency Organization drawn primarily from the normal operating personnel is identified. One single individual is assigned the responsibility to direct all emergency related activities.
3.1 Normal Organization Structure Figure 3. I shows the normal operating organization of the MCZPR. 3.2 Emergency Organizatim Structure Figure 3.2 shows the Emergency Organization. This organizatimis formed from the normal operating organization so that a smooth transition is possible. 3.2.1 Emergency Director The Reactor Administrator will be the Etnergency Director. In his absence, the Chief Reactor Supervisor, Reactor Supervisor on duty or the Reactor Supervisor to arrive first on the scene will be the Acting Emergency Director, in that order. Basic Function The Emergency Director is responsible for taking all action necessary to manage any reactor related emergency. Primary Responsibilities The Emergency Director
- 1. Coordinates and directs activities of the MCZPR Emergency Organization.
- 2. Classifies and declares an emergency when needed.
- 3. Assures notification of College, local and federal agencies as delineated in the procedures required. The actual notifica-tion of outside agencies will be made, if time allows, only by the Reactor Administrator.
4 Issuing instructions to the Emergency Organization and assuring that appropriate action is taken.
- 5. Insures health physics activities on campus.
- 6. Declares termination of emergency.
- 7. Authorizes re-entry into the ZPR Room after an emergency.
- 8. Authorizes volunteer emergency workers to incur radiation exposure in excess of 10CFR20 limits.
Manhattan College President i 1 l Provost 1 Dean of Manhattan College 1 Engineering Radiation Protection Council I I Reactor g Operations --
" ** L--
Reactor [ l Administration .
- Reactor Reactor l
Health Radiation . Physicist Safety Officer Chief Reactor Supervisor Reactor Supervisor Reactor Operators MCZ.PR GA IZATION CHART
- 13 -
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Manhattan College Pre sident Provo st Dean of _ _ _ _ _ _ _ , Emergency Engineering News Center Off-Site , _ _ _ Emergency Support 8 Director Organizations Health Radiation Physicist Safety Officer Emergency Operations Supe rvisor . Emergency Operators Figure 3. 2 MCZPR Emergency Organization Chart
. _ _ _ . . _ , . . _ . ,_ .._-- _ . . _ . . ~ . _ _ _ . . . . _ . . - _ . . _ _ _ _ _ _ . _ _ _ . _ . .
- 9. Prepares news releases to the public when requested by the Dean of Engineering.
- 10. Reports to the Dean of Engineering.
3.2,2 Emergency Operations Supervisor The Chief Reactor Supervisor will be the Emergency Operations Supe rvisor. In his absence, the Emergency Director will appoint one of the reactor supervisors to act as the Emergency Operations Supe rviso r. Basic Functions The Emergency Operations Supervisor is responsible for the implementation of activities connected with safe shutdown and maintaining of conditions that would minimize the effect on health and safety of the public. The Emergency Operations Supervisor 1 Reports to the Emergency Director 2 Implements reactor emergency procedures
- 3. Supervises reactor emergency personnelin work at the reactor connected with the emergency 4 Supervises recovery operations 3.2.3 Emergency Operators Emergency Operators are drawn from the Reactor Operating personnel.
Basic Function The basic function of the Emergency Operators is to assist the Emergency Operations Supervisor in his activities connected with an emergency. They report to the Emergency Operations Supervisor. 3.2.4 Radiation Safety Officer The Reactor Radiation Safety Officer will continue to function as the Radiation Safety Officer during an emergency. Basic Function The basic function of the Radiation Safety Officer during an emergency is to advise the Emergency Director on matters of radiation safety during an emergency. He reports to the Emergency Director. - 3.2.5 Health Physicist The MCZPR Health Physicist will continue to function as the health physicist during an emergency.
16 - Basic Function The basic function of the Health Physicist during an emergency is to implement procedures that would minimize the radiological effects on the health and safety of the personnel involved in an emergency work and that of the public. The Health Physicist
- 1. Reports to the Emergency Director
- 2. Develops plans and procedures for checking for 3
contamination 3.2.6 Emergency News Center . The College Relations office of Manhattan College will serve as the Emergency News Center. Any news pertaining to an emergency will come to the Emergency News Center for the Dean of Engineering or his designate. 3.3- Off-Campus Service Support To assist Manhattan College Emergency Organization, outside agencies may be called to actionby the Emergency Director.
- 3. 3.1 Medical Assistance St. Joseph's Medical Center, Yonkers, New York has medical facilities needed to render immediate treatment to contaminated and non-contaminated injured personnel. Appendix 3A is a copy of the letter of understanding between Manhattan College and St. Joseph's Medical Center.
3.3.2 Ambulance Service St. Joseph's Medical Center will provide ambulance service when neededi 3.3.3 Police The Manhattan College Security Department will provide routine security for the reactor. If additional security is needed, the Blice Department of the City of New York will provide the needed extra se curity. 3.3.4 Fire Assistance The Fire Department of the City of New York may be called for assistance if the need arises. 3.3.5 Nuclear Regulatory Commission f. If the need arises assistance may be sought from the Nuclear Regulatory Commission, Region I office in King of Prussia, Pa. 1
- APPENDIX 3A- PAGE1 p*' N* St. Joseph's fg+.
\$M, Medical Cent _e_
127 South Orcodway, Yontw.% New Ycrk 10701 June 13, 1983 Dr. Ronald Kane Director of Mechanical Engineering Manhattan College Manhattan College Parheay Rivordale, N.Y. 10471 Daar Dr. Kane, This letter is to confirm St. Joseph's Medical Center's ability to handle potential radiation hazards from your college due to its reactors. Currently our department along with the hospital's Radiation Safety Committee is updating and modifying both the internal and external Radiation Safety policies and orocedures. Once this process has been completed, I will forward a copy to your office for your records. Again, St. Joseph's has procedures and protocols designed to handle most Radiation Emergencies 24 hours per day, seven days per week. Our Nuclear Medicine and selected Radiologic technical personnel are trained in Radiation Emergencies. The Emergency Room personnel also have procedures to follow in case an accident occurs during evening and weekend hours. In the meantime, I have supplied you some information that may be beneficial in case an emergency occurs (attached) . If after reviewing this letter you have additional questions or concerns, please call me. A copy of our final report will be sent to you when completed. Sin ce, rely , l / h -- ~ Robert Kleinbauer 's_ Administrator-Radiology Services St. Joseph's Medical Center BK/sr CC: Dr. Puljic Dr. Marsden Mr. Hyde Radiation Safety File BK File Hospitol (914) 9656700 Nursing Home (914) 9656400
..~
, APPENDIX 3A - PAGE 2 i ATTACHMENT I NUCLEAR MEDICINE DEPARTMENT: HOURS OF OPERATION: MONDAY - FRIDAY 7:30 AM - 5:30 PM EMERGENCY COVERAGE: CALL ADMINISTRATOR ON CALL OR RADIOLOGIST ON CALL PHONE NUMBERS: (914) 965-6700 EXT. 687,688 PERSONNEL: MS. JEANINE WYKA - NUCLEAR MED. TECHNICIAN MR. GENE TOLENTINO - NUCLEAR MED. TECHNICIAN MR. ROBERT KLEINBAUER - ADMINISTRATOR DR. SMILJAN PULJIC - DIRECTOR OF RADIOLOGY IN CASE NUCLEAR MEDICINE. DEPARTMENT IS CLOSED CALL RADIOLOGY DEPARTMENT (EXT. 683) OR EMERGENCY ROOM (EXT, 471) , EXPLAIN SITUATION , LEAVE NAME AND PHONE NUMBER; THEY WILL CONTACT ALL APPROPRIATE STAFF.
_ ;. ; _ . - - - . -- , _. I l
- 17
- 4. 0 Emergency Classification System 4.1 Conceptually, all possible emergencies at any research and test l reactor have been classified into four groups. Appendix I of the i Standard Review Plan [1] (repeated on the next feve pages) lists them as
- 1. Notification of Unusual Events
- 2. Ale rt
- 3. Site Area Emergency 4 General Emergency For the MCZPR licensed at O. I watt and with no recirculating cooling requirements, only the first class of emergency, viz: Notification of Unusual Event is hypothesized as the most severe credible accident.
- 4. 2 Notification of Unusual Events The emergency class " Notification of Unusual Events" is hypothesized to exist at MCZPR if events are in progress or have occurred which indicate potential degradation of the safety of the reactor. Specific action levels are detailed in Section 5.0, Emergency Action Levels
- for Notification of Unusual Events.
[1] E .F. Bate s, B. K. Grimes and S. L. Ramos Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors U. S. Nuclear Regulatory Commission NUREG-0849, May 1982
4 __,.- ,- - ' - _ J n ._ _ - - , - ma_;a --4_,_ ,=_. - - . c.. 4 18 - APPENDIX I EMERGENCY CLASSES AND EXAMPLE EMERGENCY ACTION LEVELS Emergency Class Example Action Levels Notification of- 1 Actual or projected radiological effluents at the Unusual Events site boundary exceeding 10 MPC for unrestricted areas when averaged over 24 hours or 15 mrem whole body accumulated in 24 hours. 1./
~
2 Report or observation of severe natural phenomenon that are imminent or existing such as: (1) earthquakes that could adversely affect the reactor safety systems, (2) high or low natural water sources that could adversely affect i reactor safety systems and: (3) tornado or hurricane winds that could strike the facility.
- 3. Threats to or breaches of security.
- 4. Fuel damage accident that could release radio-nuclides to confinement or containment.
- 5. Fire within the facility lasting more than 10 minutes.
-1/
It should be noted that the radiation dose levels of the emergency action levels established for the variouc emergency classes are slightly different from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e. g. , pool water leveln and area radiation monitors). 4
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19 - Emergency Class Example Action Levels Alert . 1. Actual or projected radiological effluents at the site boundary exceeding 50 MPC for unrestricted areas when averaged over 24 hours or 75 mrem whole body accumulated in 24 hours. 1_/
- 2. Radiation levels at the site boundary of 20 mrem /hr for 1 hour whole body or five times this level to the thyroid. _1_/
- 3. Abnormal loss of water used for shielding or coolant to irradiated reactor fuel at a rate which either exhausts the initial backup system capacity or exceeds makeup capacity.
- 4. Loss or radioactive material control that causes radiation dose rates or airborne radionuclides to increase ambient exposure levels by a factor of 1000 throughout the reactor building.
5 Fire that may affect any reactor safety system (s).
- 6. Other imminent or existing hazards such as (1) miss'les impacting on the reactor facility, .,.
(2) explosion that affects facility operation, and (3) uncontrolled release of toxic or flammable gases into the facility environs.
- 7. Radiation dose rates in the reactor building i requiring evacuation of all personnel (e. g. ,
100 mrem /hr for one hour throughout the reactor building. 1_/ It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different
' from those specified for pows * ?cactors. However, in the judgment of the NRC staff, the radiation de te wels specified are adequate for the credible accidents associated wM i .e eration of research and test reactors, and the specified action leg a M -s de reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e. g. , pool water levels and area radiation monitors).
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- 20 -
Emergency Class Example Action Levels Site Area 1. Actual or projected radiological effluents at the Emergency site boundary exceeding 250 MPC for unrestricted areas when averaged over 24 hours or 375 mrem accumulated in 24 hours, l/
- 2. Actual or projected radiation levels at the site boundary of 100 mrem /hr for 1 hour whole b ody or five times this level to the thyroid. l_/
- 3. Abnormal continuing loss of reactor coolant, to fuel requiring coolant, at a rate greater than the capacity of the backup system (s).
- 4. Imminent loss of physical control of the reactor.
- 5. Several natural events being experienced.
Examples include: a) earthquake that is causing observable damage to the reactor safety equipment within the building, b) high or low natural water levels that are affecting the operability of any reactor safety system; and
- c) tornado or hurricane winds that are damaging the reactor structure.
1/ It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e. g. , pool water levels and area radiation monitors).
21 - Emergency Class Example Action Levels General 1. Sustained actual or projected radiation 2 Emergency _/, levels at the site boundary of 500 mrem /hr.
- 2. Actual or projected doses radiation levels at the site boundary in the exposure pathway of 1 rem whole body or 5 rem thyroid.
- 3. Loss of reactor coolant that could lead to fuel melt.
- 4. Loss of physical control of the reactor building or reactor control room and areas housing vital equipment.
- 5. Events that have caused or will cause massive facility or reactor system damage that could lead to fuel melt.
2/ Generally not specified for facilities with authorized power levels less l than or equal to 2 MW thermal and determined on a case by case basis above the level. l
l 5.0 Emergency Action Levels for Notification of Unusual Events
- 1. Indication of fuel damage by increased concentration of radionuclides in the reactor water
- 2. Loss of Confinement integrity
- 3. Threats to or breaches of security l
- 4. Fire within the facility lasting more than 10 minutes
- 5. Report or observation of severe natural phenomenon that are imminent or are existing such as:
a) earthquake b) hurricane c) flood
- 6. Other hazards or events at the facility such as:
a) aircraft crash b) explosion c) release of toxic or flammable gas
- 7. Injury to personnel (contaminated or not) that requires transportation to an off-campus medical facility It is recognized that the above items have very low probability of occurrence at the MCZPR facility.
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- 23 -
6.0 Emergency Planning Zone No radiological emergency that could result in off-site plume exposures exceeding 1 rem whole body or 5 rem thyroid is plausible at MCZPR and hence no Emergency Planning Zone is identified for MCZPR.
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24 - 7.0 Emergency Response Emergency classes of Alert, Site Area Emergency and General Emergency are not postulated to occur at MCZPR. Hence, the emergency response is given only for the emergency class, Notification of Unusual Events. 7.1 . Activation of Emergency Organization The Emergency Organization will be activated by the following steps:
- 1. If and when a MCZPR staff member becomes aware of or is informed of the possible existence of an emergency, he notifies the Reactor Administrator, the Chief Reactor Supervisor or a Reactor Supervisor, whoever he can reach in that order.
l 2 The first person who is entitled to act as the Emergency Director to reach the Reactor Facility verifies the existence of an emergency, declares an emergency and assumes the role of the Emergency Director.
- 3. A Reactor Supervisor who assumes the role of the Emergency Director will relinquish that role to the Chief Reactor Supervisor when the latter reaches the facility. The Chief Reactor Supervisor will relinquish the role of the Emergency Director when the Reactor Administrator arrives at the facility.
- 4. The Emergency Organization is activated by the Emergency Director. The call-out roster of the members of the Emergency Organization with their telephone numbers (both home and office) shall be posted at the Control Console of the reactor and at the Emergency Support Center. These locations are shown in Figure 7.1.
The roster will also contain telephone numbers of the off site -- agencies such as NRC, ambulance, hospital, police and fire department that may be activated if necessary. P Telephones are provided at the Reactor Control Console and at the Emergency Support Center. Telephones are also available in faculty and department offices and in the Dean's office.
- 7. 2 Assessment Action The reactor operations staff are provided with film badges. Extra badges are also available . These may be used to assess radiation doses, if any, to personnel during an emergency.
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FIGURE 7 1 , LOCATION OF EMERGENCY ORGANIZATION CFART I.
- 26 -
Calibrated portable radiation meters are available at the reactor facility. An assessment of radiation levels may be made using these instruments. If deemed necessary, the health physicist will take wipes and air samples and assess the extent of the contamina-tion, if any.
- 7. 3 Notification
" Notification of an Unusual Event" shall be made no later than the next working day to NRC, Region 1, King Of Prussia, Pa. by the Reactor Administrator. If this cannot be accomplished by the Reactor Administrator in the allotted time due his absence, then the Emergency Director who acts in that capacity on behalf of the Reactor Administrator will accomplish the notification process.
- 7. 4 Leaving the Facility Before the Termination Of An Emergency If the Emergency Director has to leave the facility for any reason, he may do so only after appointing a qualified substitute to act as the Emergency Director.
7.5 Termination of Emergency When appropriate, the Emergency Director shall declare the termination of emergency.
- 7. 6 Emergency Log An Emergency Log will be maintained by the Emergency Director.
The log should contain the time date of the declaration of every emergency, the name of the Emergency Director, action taken during an emergency, time and date of the declaration of the termination of the emergency. The Emergency Log should be kept at the Emergency Support Center. I
- 27 -
- 8. 0 Emergency Facilities and Equipment 8.1 Emergency Support Center The platform in Room 221 (shown double hatched in Figure 8.1) will serve as the Emergency Support Center.
- 8. 2 Emergency Equipment Portable Radiation Servey meters are available in the ZPR room.
- 8. 3 First Aid Facilities First aid supplies are available in cabinets at the Emergency Support Center.
- 8. 4 Communications Equipment Telephones are provided at the Reactor Control Console and at the Emergency Support Center. Additional phones are available in the offices of the Dean of Engineering and faculty and department offices.
- 8. 5 Decontamination Equipment Decontamination equipment is provided at the Emergency Support Cente r.
- 8. 6 Handling of Injured and/or Contaminated Personnel Arrangements have been made with a medical center (Appendix 3A) for the handling of injured and/or contaminated personnel.
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l l 29 - l
- 9. O Recovery 9.1 - Recovery Manager The Chief Reactor Supervisor, or in his absence, a Reactor Supervisor will act as the Recovery Manager.
The Recovery Manager will:
- 1. See that the facility is brought back to . normal for the normal operation of the reactor
- 2. Perform the normal checkout procedures of the reacto r.
- 3. - Enter in the Reactor Operations Log book that the reactor has been recovered after the emergency and that the reactor is ready for normal operation.
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30 - 10.0 Maintaining Emergency Preparedness
- 10. 1 Annual Review These emergency plans shall be reviewed by the Reactor Operations Committee at least once a year.
10.2 The Emergency Organization chart and the call out roster shall be corrected whenever necessary and the updated charts should be posted and distributed as needed. 10.3 Implementing procedures affected by any emergency plan changes shall be revised, approved and distributed to authorized recipients within30 days after the revised plans have been issued.
, - , , ., - - - - . , ~ , . - ~ , . . . , , , . _ , , - , , - , ..
e APPENDIX J OPERATOR REQUALIFICATION PROGRAM J-1 l ..
i OPERATOR REQUALIFICATION PROGRAM Since the Manhattan College Zero Power Reactor is 2 a research and test reactor licensed only for 0. I watt maximum, the requalification program is guided by paragraph 7 of 10CFR55, Appendix A. The requalification program will be operated by Bro. Gabriel Kane, FSC, ' Ph. D. who has been reappointed Chief Reactor Supervisor, effective July 1, 1983. Bro. Gabriel Kane had been Chief Reactor Supervisor until June 30, 1980. Dr. Joseph Augustus served as Chief Reactor Supervisor from July 1, 1980 to June 30, 1983. In order to requalify Bro. Kane , Dr. Augustus (who remains on the Reactor Operations Committee) will evaluate any necessary requalification examinations administered to Bro. Kane. The requalification examination f or Bro. Kane will be administered on September 1, 1983. We note that Bro. Kane holds a Doctorate in Physics from the Catholic University of Americt., has held
- a Senior Reactor Operator's License from November 6,1968 to the present, and served as Chief Reactor Supervisor from November 6,1968 to January 13, 1972 and again from May 4,1973 to June 30, 1980.
On successful e ompletion of the requalification examination by Bro. Kane, Bro Kane will then operate requalification programs there-a fte r. In accordance with paragraph 7 of 10CFR55, Appendix A, the requalification program will conform generally but will not be identical to paragraphs 1 through 6 of 10CFR55, Appendix A. i
- 1. Schedule. The requalification program will be conducted continuously over two year cycles. The program will be revised as needed for each succeeding cycle to account for changes in equipment or operating procedures. For any individual whose operator or senior operator license approaches expiration during the two year cycle, a written examination illustrating the effectiveness of the program will be administered.
- 2. Le cture s. In consideration of the primary use of the Manhattan College Zero Power Reactor (MCZPR) as a teaching and demonstration tool for nuclear engineering courses, each licensed operator or senior operator normally must prepare and present lectures each semester on the theory, operation, and safety features of the MCZPR and nuclear facility. As part of the requalification program, the preparation and presentation of at least one lecture each semester on these subjects will be required of each licensed operator or senior operator. ,
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- 2 -
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- 3. On-the-Job Training. Since the MCZPR is a small research and test reactor, the requalification program requirements for production or utilization facilitics do not strictly apply. However all licensed operators and senior operators will be required to make a complete checkout of the reactor and bring it to criticality at 1 cast once every four months. As has been the practice, all licensed operators and senior operators will serve on the Reactor Operations Committee. This insures that each licensed operator and senior operator is cognizant of facility design changes, procedure changes, facility license changes and is aware of emergency procedures.
The Reactor Operations Committee meets at 1 cast once each semester and maintains complete records of its meetings and activities.
- 4. Evaluation. Each licensed operator and senior operator shall be required to submit biennially to a written examination.
The examination will include the following topics: a) Fundamentals of reactor theory, including fission process, neutron multiplication, source effects, control' rod effects, and criticality indications. b) General design features of the core, including core structure, fuel elements, control rods, and core instrumentation. c) General operating characteristics including effects of temperature and reactivity changes, d) Design, components and functions of safety systems, , including instrumentation, signals, automatic and manual feature s. e) Components, capacity and functions of reserve and emergency systems. f) Standar 1 and emergency operating procedures for the facility. g) Purpose and operation of radiation monitoring system including survey equipment. h) Radiological safety principles and procedures.
- 1) Conditions and limitations in the facility license .
or authorization. j) Facility license procedures required to obtain authority for design and operating changes in the facility.
)
c l
- 3 -
- 4. (continued) k) Reactor theory, includin'g details of fission process, l neutron multiplication, source effects, control rod effects, and criticality indications.
- 1) Procedures and limitations involved in initial core loading, determination of various internal and external effects on core reactivity.
Any licensed operator or senior operator who scores less than 80% in the biennial examination will be required to take a make-up examination. All examinations will be kept on file for at least two years. As administrator of the requalification program, the Chief Reactor Supervisor will be exempt from the requirement to submit to an annual examination. However, a newly appointed Chief Reactor Supervisor must submit to a written examination (administered by the outgoing Chief Reactor Supervisor) at some time during the first three months of his appointment. Operators or senior operators possessing at least a Master's Degree in Nuclear Engineering and who have taught an under-graduate or graduate nuclear engineering course during the preceding or current academic year may be exempted by the Chief Reactor Supervisor from the theoretical part of the written examination. Licensed operators or senior operators shall be observed by the Chief Reactor Supervisor,at least once every four months, in checking out the reactor and bringing the reactor to criticality. A newly appointed Chief Reactor Supervisor, upon certification by the previous Chief Reactor Supervisor that his performance in checking out and operating the reactor is satisfactory, shall be exempt from further observation.
- 5. Records. Records documenting the participation of each licensed operator and senior operator in the requalification program will be maintained for a minimum of two years from the date of each recorded event. The records shall contain copies of all examina-tions and evaluations.
- 6. Alternative training programs. Such programs are not required for the MCZPR.
l b 1.
l APPENDIX G OCTOBER 6,1966 CORRESPONDENCE G-1 l
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- .ta .. - ;. : u: nsi..: a: t i.t . . i October 6,1966 Mr. Marvin K. Woodard Division of Licensing anil Regulation f U.S. Atomic Energy Commission '
Washington, D. C. 20025
Dear Mr. Woodard:
As of our letter of October 29, 1965, we submitted a proposal to your Division for a change in technical specifications for the oper-f ' ation of our reactor facility under License R-94. We requested then that Section G-1 of Appendix A be changed to read:
"The core shall be comprised of no more than sixteen standard fuel elements and one partial element. The number of fuci plates c ;;tained in the partial element shall be adjusted such that the excess reactivity at 60 F shall not exceed .003 and at U
75 F shall not exceed .0035 with both control rods " full out". We proposed also at tha't time that a limitation of 80 F be placed on the maximum operating temperature except during an experiment to determine the temperature at which the turn around to a negative tempeiature reactivity coefficient takes place. In order to substantiate our proposal, the MCA of the Hazards Summary Report had to be reevaluated based on the assumption that the MCA would occur at the turn around temperature when the core had the mrodmum excess reactivity. It was necessary, then, to deter-mine this maximum reactivity by an experiment which would require us to heat the pool water to approximately 120 F. The cost of the re
- quired heating units was prohibitive at that time and we suggested the possibility of a correlative study of the MZPR with IRL for which temperature coefficient data was available.
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Mr. Marvin K. Woodard We wish~to submit for your study at this time, such conclusions as we have drawn from the data available from the operational log of MZPR and the experimental data obtained from IRL. Submitted by: .
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g tfy Y Y. ,l h ~ j'iit h ;. l. c" .y .';, -t.j: Brother B. Francis Rolston, F.S.C. @ Reactor Supervisor ( . Approved: f .* .-T l~ /
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I'./~ Brother C. Gabriel Kane, F.S.C.
. Chairman, Committee for Nuclear Science and Engineering C
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r .._, v/. CERTIFICATE V 7 . The applicant and any officini exceuting this certificato on bohalf of the appli-A._.i cant certify that these applications are prepared in conformity with Title 10, ) Code of Federal Regulations, Party 50 and 70, and do so solemnly swear (or affirm) that all information contalped herein, including any supplements attached hereto, is true and correct to the best of our knowledge and belief. Manhattan College, New York, N. Y. -
. Applicant By Brother Gabriel Kane, Chairman Committee for Nuclear Studies
.../ .
]' 4 proved: Brother C. Stephen, F. S. C. Academic Vice President State of New York County of Bronx Subscribed and sworn to before me this day of Notary Public r v's' ' ~ '"' '"-
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itdws ms.unm:.vr zu n us Void Coefficient Measurement Detailed information regarding the void coefficient m.iasuremeni :J ine IRL core was available thru the courtesy of Mr. Richard Canfield. IRL Reactor Supervisor. It was possible for us, then, to make a similar me'ssrs.. a mont of the reactivity effects of voids in the MZPR core and correlate the results with IRL. A special lucite hoId-down rod was prepared which had a void volunw. cf approximately 164 cm3. This replaced the ordinary hold down roc when the void effect was being measured for a particular core position. T.ie resula: for the MZPR are tabulated below and indicated on the accompanying core digran.. Core Position 4k x IC
-6 -
t ( 34 -7.24 12 -4.3 22 -5.7 Core Position 2k -6 3 L. x 10 /cm - 35 -4. 9 55 -6. 7. . 45 -5. 5 46 -3.7 44 -7.3 24 -6.1 _c 4 3- ," Average Void Coeff. -5. 83 x 10 s The average void coefficient measured for the IRL core loading .; was -5.94 x 10 4k . It would be reasonable to assume, then, t!:at i.. _.. k event of an excursion, the MZPR will respond in a fashion similar to the pool reactor and the void effect will help to terminate the excursion. With a water volume of 3237 in3 in the core, a volume coef.'cie".t ci expansion of 1.95 x 10-4/0C and a void reactivity coefficient of -5. F x 10-0 4h -
/cm 3, there will be a total negative reactivity effect of .3G% k in the
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YOltK 10171 l'11).wH.S 1*P.\RT\lf.Ni' 212.b4d lMAI Void Coefficient Measurement (cont'd) of an excursion of the MZPR. This is approximately the same amount of . positive reactivitg we assumed would result from the positive temperatu' o offect betvecen'60 F and 110 F. Again it is seen that we can rely upon the negative void coefficient to assist in shutting down the reactor. ,, Prompt Temperature Coefficient of'IRL and MZPR
,Using the Method of Meem, the prompt temperature coefficients for the IRL and MZPR were calculated. For the MZPR the calculated temperature coefficient was -1.31 x 10-4 .4 k / F and for the IRL reactor
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-1.135 x 10 / F. '
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l i 1 f .# g j m y> ty October 6,1966 i h MANH w.,____.___.ATTA_N __ COLLEGE
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PliY5lCS DEPARTMENT 212. rA3 1".00
- 1. Conclusions drawn from data obtained from the Operational Log Book of M ZPR.
The following excess reactivity measurements were made on the MZPR. It must be borne in mind that since these measurements were made at different times during the year by different experimental group.s, the error involved might be appreciable. Calibration of the fine position indication system of the Regulating Rod was made before cach measure-ment, but this adjustment is a.very delicate operation and could vary ap-preciably over several weeks or months. Temperature % Ok k Date 60 F .290 2/18/65 63 F .314 3/18/65 63 F .323 3/18/65 L- 630 F .295 3/16/65 72 F .340 8/5/65 750 F .350 8/6/05 75 F .355 8/12/65 68 F .321 10/8/65 This data is represented on the following graph where the reactisity is plotted as a function of pool water temperature and normalized at a nominal room temperature of 700F for a comparison with the behaviour of the IRL pool reactor. As the graph seems to indicate the variation in reactivity peaks at a value of .030 and at a temperature of 1100 F, Since the curve is normal-ized at 700 F this would indic te that the excess reactivity in the core will not exceed .369 % [ . II. Reevaluation of MCA based upon M ZPR data. (a) Assuming that the M a maximum of .450 %(this %gA occurs allows for somewhen the error possible excess in thereactivity has estimated experimental value of .369 % O ) at 110 F, we first calculated k y the peak power rise from a steady operational power of .1 watt. This was done assuming the following reactor constants:
u, l 71 Q October 6,1966 M.._-_A.. . NII.ATTA.N C.O_L.I EG. E
..7. . . . . _. . . . BitONX. NEW YORK.1.0471 PHWI(: DEPAllTMENT 212. M 3 1400 II. Reevaluation of MCd based upon M ZPR data (cont'd).
-4 4 k P g= .1 watt x (T) = -1. 5 x 10 /C 5
(8ke)0 = . 0045 Cp= 2.185 x 10 watt [gm/ C B = .0084 eff J = ,1068 sec. and employing the basic equations: _1_ dP , S ko P dT J b = ($k)o- e lcllT
~
P=P C \dl T g +y ( f kg ), T 2 J. , L. - when P=P max T = ( [gl ) P =P+Ck g 2
}
Tids yields a value of P max f 147 kw. From these same basic equations time plots of ( 5 k) , P and T were made which appear on a separate graph. In order to make $hese graphs it was assumed that Po= 10 kw since ( S k)e and hence P was a slowly varying function of time. Corrected times were then calculated. The following data was used in making the graphs: / (' u
{ , October 6,1966 MANHATTAN
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PilY.%I0.- IW.P.G rM EN r 212 548 1400 II. Reevaluation of MCA based upon M ZPR data (cont'd).
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't(sec) 5 ke (x 10 ) T( C) P(kw)
-4 0 4. 5 43.3 10 116.8 4.334 44.4 10 126.8 4.254 44.9 14.84 136.8 4.144 45.7 21.4 156.8 3.714 47.4 44.8 176.8 2.894 53.9 83.9 196.8 1.434 63.6 121 216.8 -0.433 76.0 147 236.8 -2.186 87.6 118
(. 256.8 -3.386 94.9 72 276.8 -4.216 101.1 31 316.8 -4.716 105 0 From these graphs it is seen that the reactor peak power of 147 kw would be reached in 3.6 min. after the beginning of the excursion and the power would be' essentially zero again after approximately 5.3 min. The core temperature will rise to 105 C indicating there might be some boiling of the water moderator in the center of the core. i I'
1< 0 October 6,1966 MANilATTAN C0LLEGE _ BRONX. NEW YORK _10471 PinSlO DEPANTMEST 212.M3.liOO E. A correlative study of the MZPR and the pool reactor at IRL was made. The nuclear parameters of the MZPR and IRL are not too differ-ent as can be seen from the following table. Similarities of volume fractions of fuel, water and aluminum and equivalent core size should be noted. The primary difference between the two cores is the clu,ter-ing of fuel in.the MZPR which results in a somewhat lower thermal utilization. MZPR IRL 0 U Volume of Unit Cell. 156 in 216 in Volume. Composition of Unit Cell HO .6393 .623 2 Al .3584 .375 U-235 .002084 .002394 6'f U-238 .000156 The clustering of the fuel was considered in the MZPR core cal-culations by the original designers using computer code methods provea to be reliable. The MZPR core can, we feel, be fairly well represented by a measured IRL core, after proper normalization. Prompt Temperature Coefficient The prompt temperature coefficient of the MZPR core was original-ly calculated by repeating the reactivity caledation. using P3and DMM codes, at two different temperatures 70 F and 270 F. The difference in reactivity at these two temperatures was then divided by 200 F to obtain the temperature coefficient. This resulted in a value of -9x10-5 Ak/ F. It has been argued that. this method was invalid for a zero power reactor since two such widely separated temperatures were assumed and con-ceivably a positive temperature coefficient could exist in the normal temperature range of 60 F to 780F. Though limited by lack of proper computer codes we made a two-group calculation of the reactivity at threc different temperatures 600F, 780F and 90 F. The method of calculation assumed that the predominant
- effect upon the reactor due to an excursior, would be the loss in modera-tion. An increase in temperature will cau e a decrease in the density of w rw , -,-- --.m-.. -,.c-------w-,---..w.,,,,-,-,.,,,,-v,- ,-,, , y,-r-,- -,,...y --- .
l k 0 October 6,1966 m ." "#, _MANHAT,T.AN COLLEG.,E BRONX, NEW YORK 10471 - - -
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PilYSICS DEPARTMENT 212 548 1400 Prompt Temperature Coefficient (cont'd) the moderator which results in a loss of slowing down power. More neutrons will tend to leak out of the system with a corresponding re-duction in the thermal fission rate. The temperature coefficient was defined as 1 d k,fg ,, 3 d[f 3 d[g . dT dT dT T
- k ,ff f * [ th Two group theory was used considering the change in the effective multi-p11 cation factor at various temperatures. According to two group theory the effective multiplication factor is equal to n
1 .A x /t v "I 2 (1+L p )Ax+ (1-L ,2)] 2 1t 2 ,2 + 1 32 " 2 - ( } where d 3 = - ~ J 2 - I h ~fi l II d- R) Ay = 2/ 2(,S Y
* }#I,'(5k f , _ ki Ki(k Dib Kg (lf1 R 1 Dy The primary and secondary bucklings are defined as c
2 1 1 1 4 (k - 1), ,' g =y - (p + g ) + - (1g + p 1-)2 + ta1 322 1 - 1 2 1 2 , I. r
,2 = y1 1 1 1 1
+ 4(k - 1) '
._ s ' - (q . + q ) - (q + g)2 tg tg .
c, - T
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l October 6,1966 p a MANHA1 TAN COLLEGE bit 0NX, NEW YORK IM71 "hI3ia?No
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EdnudiI[N11Nd5I Prompt Temperature Coefficient (cont'd) The change in the effective multiplication was obtained 0 ly consider - ing the change in,the parameters in the equation at 78 and 90 F and then calculating the values of the effective multiplication factor at these tem-peiatures. For the variation of the thermal diffusich length we used the ex-Pression .612 2, f The fast diffusion length was approximated by the fermi age. The temperature variation of this parameter was obtained by the expression T = to (1 + 2 c/y AT) where o(y is the volume expansion coefficient. The variation in the radius and the height of the core and reflector was unsignificant in the temperature range we were considering. P1 was held constant since D ib and D1 were both dependent on the macrcscopic cross sections and the variations in these quantities cancelled each other, Values for various parameters and k,g at varopis T 600F 78 F 90 F M 22 = .0201 .0206 .0204 v = .5224 .5259 .5396 p2 = .01746 .01796 .01776 gr 2 = .52504 .52854 .54224 L2 = 2.127 2.107 2.055 72 = 30.94 31. U 31.02
= 03232 .03227 .03222 1
= .7780 .7780 .7780 kge
= 1.012 .9820 1.000 The results indicate a temperature coefficient neptive in the range 60 F to 780F and positive in the range from 78 F to 90 F. These results are reported here to demonstrate the sensitivity of the parameters in-(,,' volved in the calculation. Though the calculated temperature coefficient V for the bulk water is higher in this temperature range than the measure <t value there is an indication that by using computer methods it may be possible to show a positive temperature coefficient in the entire range from 600 F to 900F. This study will be continued.
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- 5. TEMPERATURE COEFFICIENT OF REACTIVITY (IRL)
- a. Purpose.
This experiment was performed to determine the reactivity effect of uniform temperature changes in the reactor core and surrounding wa'ter while the reactor operated at a low power 1cvel.
, b. . De s cription.
An externa 132Aat source was ne'eded to obtain temperature , changes ' with the reactor operatihg at essentially zero power, that is, a few tenths of a watt. This was done by passing pool water 'hrough t the primary side of the exchanger where it received heat from saturated steam fed to the secondary side from the plant boilers. To minimize system heat losses, the holdup tank was' bypassed by connecting a' hose to the tank inlet and outlet flanges. Temperatures were monitored by inserting'a thermocouple near the center of the core lattice. Three - Alnor resistance thermometers were located at various points around the core. See Figure 24. Core Loading No. 5 wa. po.iiioned in the stall section of the pool. The gate was placed between the two pool . se ctions. .
- c. Test and Results. ,
The temperature ranged from ShF to 112*F during the three main temperature runs. In the first test the pool water was heated to (' 23
.~ 5 ,
, a maximum temperature of 112*F and allowed to cool. The pool water circulated through the heat exchanger at a flow rate of 1000 r, Inn. During the cooling process, critical settings of the regulating rod t.nd temperature readings, at about one degree intervals, were recorded. In the second test, the pool water temperature was increased r over the 76. 5 to 100*F range. During the run the pool water tem-c perature increased at a rate varying from 12*F per hour at 80*F to approximately,3*F per hour near 100*F. The third test was performed over the temperature range from 59'F to 75*F. In this run, the holdup tr.nk was not bypassed and the two pool sections were not isolated from each other with :he pool gate as they were in the two previoas runs. Under these conditions, the pool water temperature increased at a constant rate of approximately
- 2. 4 *F per hour.
Figure 25 is a plot of the reactivity change due to pool water tempera,ture v$riations over the range 59*F to ll2*F. This curve has been normalized to a nominal room temperature of 70*F. The corresponding temperature coefficients as a function .of the pool water ternperature are shown in Figure 26.' The temperature coefficient - for these test conditions varied from a maximum positive value of
-6 .
+30 x 10 4K/*F to a maximum negative value of-14 x 10 64 K/*F.
24 l +
,.=
/
Tho zero temperature coefficient occurred at approximately 94*F. O
\.'-
The net reactivity g.iln between rooin tempe ratu r.' .tud ') !"F w.ir. O. 02*/. 4 K. , It should be noted that the uniform temperature effect measured and reported here is dce to changes in the der.sity of de water ar.d the core materials. It is not the temperature effect which would occur during normal high power operation or during a transier.t. During power operation temperature drops exist across the film boundary and over thle core length. In addition, the effect of the reflector on the temperature co-efficient during power operation is not included here since the , 1 rcilector is then at a much lower temperature than the core. ' 1-Jacobs, A. , Two Group Albedo Theory c.nd Application to .TemperMure Coefficient Calculations, Research Reactor Facility, The 1:ennsylvania State University, University Park, Pennsylvania. (Unpublished)
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MANHATTAN COLLEGE. m vr.sm A t.2 Gl'ONX, NrW VO!4> t<M s
- cr8 n F OF TitW. PDE&tDENT I Octot:er 10, 1966 Mr. Eber R. Price, Director Division of State & Licensee Relations Atomic Energy Commission Washington, D. C. 20545 ,
Dear Mr. Price s In answer to your letter of September 20,1966, listing four items of apparent noncompliance noted during the compliance inspection conducted on July 28,1966, I am forwarding berewith a letter prepared by Brother Gabriel Kane, Chairman of the . , Ca==inee for Nuclear Studies. (. Brother Gabriel's letter indicates the corrective steps we have taken or that will be taken with respect to the items listed in your letter. I trust that his explanation regarding the circum-
' stances of the violations and regarding our corrective measures will meet with your uppsoval. The actual date when full compliance will be achieved is contingent upon the Licensing Division of AEC to which we have made application as indicated by Brother Gabriel.
I rmgret very much that any of our activities may have been in noncompliance with AEC requirements. I trust that this letter, as well as my oral comments to your representatives, will serve to assure you of our utmost cooperation in seeing that all requirements are fulfilled in pecper fashion.
- Yours sincerely,
!)fl l . / * '.. . .
Brother Gregory Nugent, F.S.C. l , BG:mkd President cc: Brothei Gabriel Kane Brother Stephen Sullivan Brother C. Leonard O'Connor
APPENDIX H NOVEMBER 15, 1966 CORRESPONDENCE i H-1 I
i , . l MANIIA'ITAN C01.1 EGE HRONX, NEW YORK 10471
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PllYSICS UF,PART%IENT 212.MA ll00 November 15, 1966 1 Mr. Roger S. Boyd, Chief Research & Power Reactor Safety Branch
- Division of Reactor Licenshg U.S. Atomic Energy Commission Washington, D.C. 20545
Dear Mr. Boyd:
Brother Gregory Nugent, President, has referred to me your letter of November 2 relative to the determination of the temperature coefficient of reactivity. In the second paragraph of your letter you request further information on the following points: (1) The basis used for predicting the temperature at which the moderator temperature coefficient of reactivity becomes negative. The graphical estimate of the temperature coefficient of reactivity is chown in the first enclosed graph (Fig.1). The first point on the line to the 0 left regresents the average temperature coefficient of reactivity between 60 F and 75 F. The points off the line represent the values for the tgmperature coefficient of reactivity taken at intervals between 60 F and 75 F. The second point to the right on the line of this graph represents the turn-around tempera-ture for the temperature coefficient of reactivity. This point was obtained by following the curvature of the graph for the IRL reactor as shown in Fig. 2.
~
This estimate is subject to the errors inherent in taking measurements over a wide period of time, as has been already indicated in the material sub-mitted with our letter of October 6,1966. It is also subject to limitations because of the comparatively small number of measurements involved and the - fact that these measurements were taken with an ordinary thermometer with-in the tankbut outside of the core of the reactor. Finally, there seems to be g- very little point in pursuing this topic further since we shall repeat all of iv these measurements with a high degree of accuracy and make a direct experi-mental determination of the turn-around temperature.
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a.: i O . November 15, 1966 - Mr. Roger S. Boyd (2) The integrated dose to the operator during the accident. The graph and data submitted with our letter of October 6,1966 repre-sents an excursion with a peak power rise of 147 Idlowatts with a release of 13.2 megawatt-seconds of energy. The integrated dose at 150 cm. above the core center line (water surface) will be
- Roen n ,
13.2 x 10 = 18.5 Roentgens 5 x 10 _ s 3800 g
;
This calculation is based on "Research Reactors" U.S. AEC,1955, p.111 Fig. 2-31. (Cf. Supplementary Hazards Summary Report, p.5). In comparing {- this excursion with the one described in Table I and the following graph of the Hazards Summney Report and page 5 of the Supplementary Hazards Summary Report, it should be kept in mind that the earlier calculation of radiation dose is based on an absorption through 129 cm. of water (distance from top of core to water surface), while this more recent calculation for a larger excursion la based upon an absorption through 150 cm. of water (dis-tance from approximate center of core to water surface). (3) The effect of cold water in the pool reacMe the core by natural convection. - The grid plate is a solid aluminum block with aluminum cylinders mounted upon it for receiving the fuel elements and hold-down rods as shown in Figure A-16 of the Runeds Summary Report. Consequently, there will be no free circulation of cold water thmugh the fuel elements by natural con-vection, even though they are open at the top. The heating due to the excursion should, therefore, remain trapped in these fuel elements for a long period of time. As a nresult, if a second excursion did occur, it would be after a con-siderable length of time following the first. It should also be noted that since - the excursion was pr4sumed to be initiated at the turn-around temperature, there abould be no reason to anticipate a second excursion.
- b The third paragraph of your letter requests us to: (1) mess e the excess reactivity as a function of the temperature up to at least 10 F beyond
- - - , . ..--.,,,.-,---,,--_.---,.-..---,,,.n-,,-,_,.---c,,,.
l l l l C . Mr. Roger S. Boyd November 15, 1966 , _3 the turnover temperature with the partial element removed, (2) re-evaluate i ths MCA (assuming convection through the core) based on the measured data, and (3) calculate the doses which would be received by the operator during an accidental excursion. We have taken all the preparatory steps necessary to make a direct determinatfon of the excess reactivity as a function of the. temperature up to at least 10 F beyond the turnover temperature: (a) A heat. exchanger will be installed on the Cellar Floor in the area below the Advanced Physics Laboratory. This region is shown in Suppl. Fig.6 of the Supplementary Hazards Summary Report. A purchase order for $950.00 to make this installation has been sent to g[ Alex C. Patterson & Sons, Inc., 503 West 57th St., New York, N.Y.10019. This unit will be a steam to hot water converter with future capped pro- ~ visions for chilldd water connections. These latter will enable students to perform the experiment on the temperature coefficient of reactivity during " the summer months. A steam capcity of 40 #/hr. is required to heat the 5000 galloss in the tank up to 140 F in ten (10) bours. However, the equipment l 1s capable of handling the load in five (5) hours when' a steam capacity of 804f/hr. i l is maintained. Circulation from the Reactor Pool through the heat exchanger will be maintained by a Bell & Gassett high velocity circulator. . When in operation, the water will be withdrawn from the bottom of the tank through the presently existing opening. After passing through the heat cw h-str it will be returned to the tank by means of pipes passing over the i top rim of the tank. These pipes will enter the water at four points on the circumference and will extend down into the tank and release the water at
~
about one foot above the bottom of the tank. (b) A portable mixer or agitator will be clamped onto the rim of the , tank in order to insure as far as possible a uniform distribution of tempera-ture throughout the tank. A purchase order for $609.00 for an ND-4B Portable Mixer has been , b placed with Mixing Equipment Co. , Inc., 51 Lincoln St., P.O. Box 3068, i
l l f I l Mr. Roger S. Boyd November 15, 1966 t l 4_ 1 East Orange, New Jersey 07018. This unit has the following specifications according to the vendor:
"1 - Model ND-4B "LIGHTNIN" Gear Driven Portable Propeller Type Agitator powered by a 3 hp totally enclosed chemical plant type motor wound for operation on a 220/440 volt, 60 cycle, 3 phase current. This 1750 rpm motor will be mounted on a quiet set of MIXCO internal helical reduction gears to provide a pro-peller output speed of 350 rpm. A shaft 7/8" in diameter x 66" in overall iength will be fitted with a single 15.1" diameter SuperPitch adjustable propeller. The shaft and the propeller will be supplied in type 304 SS. The agitator will be furnished'hoddlete with an aluminum swivel ball and socket mounting clamp which
(~ will attach to either the rim af your tank or a suitable support bracket spanning the top of your tank.? (c) Thperature measurements will be made by thermistors placed at about ten or twelve places within the fuel tubes, in the core.between the fuel tubes, and outside the core. The vendor of the heat exchanger has stated that it can be installed in "two or three days". The delivery time for the portable mixer is about two teoks. We shall try to perform the experiment ~on the temperature coefficient : of reactivity as soon as possible after all these installations have been com-pisted. In your letter you have requested us to state a specific date by which - we expect to complete this reactivity measurement. If a specific date is insisted upca, I believe we must be realistic and take into account both the normal and the unexpected delays for such an operation. I would, therefore, specify January 1,1967 as the ultimate target date for the completion of this > measurement. , It is not completely clav to me whether _a change in Technten1 Specifi-cations is necessary la order to introduce the heat exchanger and portable minor into the reactor system. However, if such a change is necessary, please consider this letter as a formal request for such a change. C =
I t C
~..,
a Mr. Roger S. Boyd November 15, 1966
~
g. I I trust that I have treated satisfactorily all of the points which you rain;d in your letter of November 2,1966. , ._
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i Sincerely yours, '
, J .
</
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, 'h,e c -[/h f s -
u l \ jt b-h<!(.. $ Brother Gabriel Kane, Chairman Committee for Nuclear Studies .; {'. l 1 l I 1 I I i I 6 m P i l
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APPENDIX I JANUARY 24, 1967 CORRESPONDENCE -
" EXPERIMENTAL DETERMINATION OF THE TEMPERATURE COEFFICIENT OF REACTIVITY OF THE MANHATTAN COLLEGE ZERO POWER REACTOR" t
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k MANilATTAN COI,1,EGE liltONX, NEW YtiltK 10m
~,a itn I It) Sit .% id.I'.ttiT\tt N r ;f January 24, 1967 Mr. Roger S. Boyd, Chief Research & Power Reactor Safety Branch Division of Reactor Licensing U.S. Atomic Energy Commission Washington, D.C. 20545
Dear Mr. Boyd:
I am enclosing a report on the determination of the temperature coefficient of reactivity of the MZPR, which you requested in your g', j'- letter of November 2,1966 to Brother Gregory Nugent, President. The
\. . - turnaround temperature is 110.6U F and the excess reactivity at this temperature including the worth of the partial element is 0.440% ak/k.
In your letter of November 2,1966 you also requested a re-evaluation of the MCA based on the measured data and the calculated doses which would be received by the operator during the accident. The evaluation of the MCA assuming an excess reactivity of 0.450% o k/k has already been presented in our letter of October 6,1966 to Mr. Marvin K. Woodard. The integrated dose to the operator during the accident was stated in our letter to you dated November 15, 1966. The information here presented should serve as a basis for the discussion of a change in Technical Specifications which will be accept-able both t'o the AEC and to Manhattan College. Sincerely yours,
.i. :,'- >'
y wdN' Y/.? f ~/
- f f h ;/ C < E.
Brother Gabriel Kane, Chairman BGK:mk Committee for Nuclear Studies ~(,
r i m S EXPERIMENTAL DETERMINATION OF THE TEMPERATURE COEFFICIENT OF REACTIVITY OF THE MANHATTAN COLLEGE ZERO POWER REACTOR L ,
. l Experimental Determination of the Temperature Coefficient of Reactivity of the Manhattan College Zero Power Reactor 4
This experiment was undertaken to comply with the following directive given by Mr. Roger S. Boyd, Chief of Research and Power Reactor Safety l Branch, Division of Reactoi Licensing, USAEC in a letter to Brother Gregory Nugent dated November 2,1966: That "the reactor should not be operated with an excess reactivity exceeding that which exists with the partial fuel element removed (approximately 0.17% delta k/k) until such time that you have: (1) " mea-sured the excess reactivity as a function of the buperature up to at 1 cast 10 F beyond the turnover temperature". The turnover tempeature is defined as that temperature at which the temperature coefficient of reactivity changes from positive to negative. In preparation for this experiment the following three items were purchaseri and installed: I. A Heat Exchanger A heat exchanger was installed in the enclosed Cellar Floor area below the Advanced Physics Laboratory. Tids region is shown in
? Suppl. Fig. 6 of the Supplementary Hazards Summary Report. This -( item was purchased for $950.00 from Alex C. Patterson & Sons, Inc. ,
503 West 57th St., New York, N. Y.10019. This unit is a steam-to-hot water converter with capped provisions for chilled water connect-ions. These latter have already been used with temporary fixtures. Permanent connections will be attached later. A steam capacity of 332 lbs. per hour is required to heat the 5000 gallons in the tank up to 1400 F in ten (10) hours. (It should be noted that the figure of 40 lbs. l of steam per hour stated in our letter of November 15,1966 was the ! figure originally given to us by the vendor.) The steam was sent into the heat exchanger at 5 lbs. gauge pressure. Circulation from the Reactor Pool through the heat exchanger is maintained by a Bell & Gasset high velocity circulator at a rate of 25 gallons per minute. When in operation, the water is withdrawn from the bottom of the l- tank through the 3/4" aluminum pipe coupling and gate valve shown in Suppl. Fig. 2 of the Supplementary Hazards Summary Report. The valve leading to the de-ionizer was turned off during this experiment. The water is therefore led through a pipe branching in the opposite direction to the circulation pump and heat exchanger. Af ter passing through the heat exchanger it is returned to the tank by means of pipes passing over the rim at the top of tank. Aluminum pipes enter the water at four points (90 degrees apart) on the circumference and ex-s( , tend down into the tank and release the water about one foot above the bottom of the tank. I
II. A Portable Mixer or Agitator A heavy steelI-beam was hung from the bridge acrcss the opening above the tank which is in the corner of the reactor laboratory nearest to the switch boxes. A portable mixer or agitator was then clamped onto this steel beam in. order to insure as far as possible a uniform distribution of temperature throughout the tank. This piece of appara-tta is an ND-4B Portable Mixer and was purchased for $609.00 from Mixing Equipment Co., Inc., 51 Lincoln St. , P.O. Box 3068 East Orange, New Jersey 07018. The unit has the following specifications according to the vendor: 1 - Model ND-4B "LIGHTNIN" Gear Driven Portable Propeller Type Agitator powered by a 3 hp totally enclosed chemical plant type motor wound for operation on a 220/440 volt, 60 cycle, 3 phase current. This 1750 rpm motor will be mounted on a quiet set of MIXCO internal helical reduction gears to provide a propeller output speed of 350 rpm. A shaft 7/8" in diameter x 66" in overall length will be fitted with a single 15.1" diameter Super Pitch adjustable propeller. The shaft and the propeller will be supplied in type 304 SS. The agitator will be furnished complete with an aluminum swivel ball and socket mounting clamp which will attach to either the rim of your tank or a suitable
- support bracket spanning the top of your tank".
C. This mixer was tested before the experiment. The agitation was so violent that it became obvious that this particular model could not be used unless some modification were made. The lights in the tank oscillated back and forth and a vortex was created which was so strong that the core could be seen directly from the bridge with no water s intervening. The experiments proceeded satisfactorily without the agitator. The rapid circulation of the pump and the convection currents , at high temperature were sufficient to ensure a fairly uniform tempera-ture throughout the core. For the experiment on temperature coefficient of reactivity which will be performed by the students in the future, only-a short temperature range of about 600 F to 75 F will be investigated. For this, some stirring action will be necessary. Consequently, we have obtained a smaller impeller from the same vendor. This docs not cause any vortex nor serious oscillations of the tank lights. However, the BF3 counter is moved somewhat by it. Consequently, reactor mea- . surements will be made only wh11e the agitator is turned off. III. Thermistors for Temperature Measurement In order to measure the temperature at various positions in the
. reactor during the experiment, twelve thermistors were purchased
- { from Fenwal Electronics, Inc., 63 Fountain Street, Framingham, Mass.
01702. These thermistors (model #GB35P2) are the glass probe type 1/2 inch long and 0.1 inch in diameter. The nominal resistance at 25 C is 4 , - - . . - ~c., - , -.
- a ._ -_ - .: - --- -- - -- - - - - - - - - - - - - - - -
l 5,000 ohms. Each thermistor was attached to a pair of #22 lead in l copper wires. These wires are color coded and tags numbering from O 1 tnrough 12 have been fastened to them. The wires were brought to terminal blocks in one of the junction boxes above the reactor. One wire for each thermistor and one common wire were thenled through one of the existing conduits under the reactor floor and brought up in-side the console. A twelve-pole switch was mounted in back of the console inside the doors. The twelve wires for the thermistors were then attached to the poles. A wire from the wiper of the twelve-pole switch was attached to one of a pair of Jacks. The common thermistor . lead-in wire was connected to the other jack. This makes it possible to use any one of a number of measuring instruments available such as a Wheatstone bridge or impedance bridge to mesure the resistance of the thermistors. The instrument actually used was a Model 355 Ballant.ine Digital DC-AC Voltmeter. Each thermistor in turn was placed in series with (1) a voltage source provided by a regulated power supply, (2) a 5000 ohm precision resistance and (3) a variable resistance. By means of a double-pole double-throw switch, the digital voltmeter was placed first across the 5000 ohm precision resistance and the variable resistance was adjusted until the digital voltmeter read exactly 5.00 volts. This guaranteed that exactly 1.00 mil 11 amperes was flowing through the thermistor. The digital voltmeter was then switched across the thermistor and its resistance read directly. rn ( All of the thermistors were calibrated using a constant teinperature bath and a precision centigrade thermometer which read t.o 0.2 degrees C. The resistances for each thermistor were determined at twelve different temperatures between 12 degrees centigrade and 65 degrees centigrade. The relationship between resistance and temperature for thermistors is given by the equation
~
R=R o e#(T (1) where T is the absolute temperature, To is the reference temperature and R is the resistance at the reference temperature. In the logarithmic form o this equation becomes R p p (2)
/n Ro To T
Our CDC 8090 Digital Computer was used to make a least-square fit for the linear relationship between A n (R/R o) and 1/T shown in equation (2). l ! The computer then printed out tables for each thermistor of resistances vs. degrees Fahrenheit in steps of one degree F from 50 F to 150 F. The common logarithms of these resistances were also printed out to facilitate interpolation. A copy of these tables is appended to this report. Thermistor #8 was damaged before the experiment started. Of the remaining eleven thermistors, one was placed near the edge of the tank i a
- , - - - . . - . . - , , , . . - - . , . - , , ~ . . . , , , - - - - , -
__ _ .; =_ =_. _ - _ - . . . - _ _ _ _ _ -. and the other ten were placed at various positions in the core either attached to the fuel elements or to lucite rods. The experiment.was O' started with the partial fuel element out. It was then discovered that 1 the copper of the lead-in wires depressed the reactivity so much that <
. the reactor remained sub-critical with both control rods 100% out. .
Consequently, the control rods were driven in and four thermistors were removed from the core. It was then possible to make the reactor critical. During the experiment there was good agreement among five of the six thermistors in the core. There was an appreciable difference between the temperatures recorded by these five thermistors and that , recorded by the sixth. Therefore, only the temperatures recorded by these five thermistors were used in the final calculations. The numbers and locations of these thermistors are indicated below. Thermistor Number Location 1 Attached to outside of fuel element #34 6 inches below center. 4 Attached to outside of fuel element #22 at center. 5 Attached to outside of fuel element #54 at center. s 6 Attached to outside of fuel element #35 at center. 10 Attached to end of lucite rod which rested on top of fuel plates inside fuel element
#34.
Experimental Procedure and Results On Tuesday, December 13, 1966 thi/ty-six readings were taken of the excess reactivity of the Manhattan College Zero Power Reactor between 3:00 P.M. and 10:00 P.M. The partial element was out and six thermistors were in the core (readings of five were recorded). The temperature was varied from 65 F to 124 F. Separate records were made of the time of each reactor reading and the reading of each thermistor. Then a quadratic l relationship was established and a least square fit made for the temperature (T)-time (t) relationship for each thermistor using the CDC 8090 Digital Computer. This fit had to be made in two steps since dT gradually in- ' dt creased up,to about 92.5 F and then gradually decreased. The computer then interpolated so as to obtain the exact value of the temperature of each [. thermistor when the thirty-six readings of excess reactivity were made by b . _ . . _ _ . _ . _ _ _ . _ _ _ . _ _ _ _ _ ,
the reactor operator. The temperatures recorded by thermistors 1,4,5 and 10 were in very close agreement throughout the entire experiment. C Thermistor #6 recorded about 5 F above the others at the lowest tempera-tures. This difference was gradually diminished as the temperature rose until all five were in very close agreement at about 102U F. Then thermis-tor #6 began to record slightly lower temperatures until it was recording about 20 F lower at the end of the experiment. It is believed that these readings represent actual diffeiences of temperature at different places in the core and are not due to any defect in thermistor #6. This thermis-tor was attached to the outside of fuel element #35, which is at the outer edge of the core. A hot stream of water coming from the return pipes from the heat exchanger would c.ause the region around this thermistor to be heated more rapidly than the region toward the center of the core. This would account for the fact that thermistor #6 read higher than the others at low temperatures. To account for the fact that it read lower at the high-er temperatures, it should be recalled that dT gradually decreases for dt the entire core above 92.5 F. This can be accounted for by increased radiation losses at these higher. temperatures. It is natural to expect, therefore, that the outside of the core should radiate more rapidly than the inside of the core giving a lower temperature reading for this region. The computer took an average of the readings of the five thermistors and
. determined the deviations from the average for each thermistor. Thermis-tor #10 was not inserted until after the sixth reading on the otit er four thermistors.
A quadratic relationship was established and a least square fit was made for the relationship of the excess reactivity to the temperature from 650F to 1200F. In order to complete the experiment it was necessary to determine the positive reactivity worth of the partial element and the negative reactivity worth of the six nairs of lead in wires to the thermistors. To accomplish this the water was cooled down to 60 F. All the thermistors except #10 were removed. This latter rested on top of the fuel plates of fuel element #34 and it was verified that its effect on the reactivity was negligible. The cooling process was very slow. After six days the tempera-ture of the reactor was down to only 780F. Every heat source in the labo-ra'ory was turned off and the window was left open for 24 hours. This brought the temperature down to slightly above 70 F. Preparations had been made to perform the remainder of the experiment on Tuesday, Decem-ber 20,1966. In order to bring the temperature down to 60 F, it was neces-I sary to add three thousand pounds of ice directly to the reactor and run cold water through the heat exchanger. Approval of the use of the partial element at 60 F was sent by telegram from the AEC in Washington. Confirmation of this fact was received verbally from Mr. Roger Boyd of the AEC before the partial element was inserted. The average value of the reactivity before and (. after the insertion of the partial element was inserted was 0.0707% 4 k/k. The reactivity while the partial element was present was 0.3124% ak/k.
l
. l
;
This indicates that the worth of the partial element is 0.2417% 4 k/k. This measurement with the partial element in was made at 59. 80F. i (, After the partial element had been removed, the steam was turned on and 13 readings were taken of the excess reactivity of the MZPR between 5:00 P.M. and 7:00 P.M. The temperature varied from 600F to 75 F. The temperature recorded by the thermistor was checked regularly against the reading on the thermometer suspended in the reactor. Both were found to agree to within 10F. The computer was again used to make a least square fit for the quadratic relationship between excess reactivity and temperature for the 13 experimental points indicated. For the remainder of this report, the portion of the experiment performed on December 13,1966 will be called Run #1 and the portion of the experiment performed on December 20,1966 will be called Run #2. Run #1 went from 670 F to 1240F with 34 experimental points recorded. Run #2 went from 600 F to 75.5 F with 13 experimental points recorded. In Run #1 there were 6 pairs of copper lead in wires in the core. In Run
#2 there was only one pair of copper lead in wires and its contribution to the reactivity was negligible. .Between 670 F and 75.5 F there were 8 experimental points in Run #1 and 10 experimental points in Run #2. The following are the values obtained from the computer outputs for the two runs taken separately after the least square fit had been made. .. Temperature 4 k/k ok/k $'x 104 k/k,2) .- (Degrees F) $x10-2) goxio-2) ,
Run #1 Run #2 Difference Run #2
- Run #1 67 0.643 11.069 10.426 68 1.039 11.453 10.414 69 1.426 11.840 10.114 70 1.804 12.232 10.428 71 2.172 -
12.628 10.456 72 2.531 13.029 10.498 73 2.881 13.434 10.553 74 3.221 13.844 10.623 75 3.553 14.258 10.705 Average - 10.502 The worth of the copper in the thermistor lead in wires is, therefore, 0.10502% 4 k/k. 9 C
- -. . . . , - , - - , , , , . - , - , - + , - , , , , - ,e ..- --,-.-,,._..,,,w,- -- ,
1 This value was added to each of the 34 excess reactivity values determined experimentally during Run #1. The computer then used these
,, corrected values together with the 13 experimental values from Run #2 L to make a least square fit for the quadratic relationship between excess reactivity and temperature for the entire 47 experimental values obtained {
from both Run #1 and Run M. The relationship established by the com-puter was ;
-2 -4 2 (ok/k)% = - 35.83 x 10 + 100.67 x 10 T - 45. 53 x 10-6 T The calculated values agreed with the experimental values with a probable error of 2.1 x 10-4 % 4 k/k. The turnaround temperature was 110.6 F.
The excess reactivity at this temperature in including the worth of the partial element is 0.4400 6 4 k/k. N. . I
GRAPHS AND TABLES h Graph Number Fig. 1 Original experimental results for Run #1 and Run #2. Fig. 2 Same as Graph #1 with experimental results of Run #1 corrected to account for copper of thermistor lead in wires. Fig. 3 Calculated values of excess reactivity (including effect of partial element) and temperaturo coefficient of re-activity vs. temperature. Table Number 1 Reg. Rod Calibration 1 2 Reactivity readings during Run #1 0 3 Reactivity readings during Run #2. 4 Thermistor temperatures for each reactivity reading of Run #1. 5 Calculated values of excess reactivity both with and without the partial element inserted and calculated talues of temperature coefficient of reactivity from 60 F to 1250F in steps of 1 F. 6 Calibration tables for thermistors. W e
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