View source for NUREG-1138, Notice of Renewal of License R-28.Environ Assessment & SER (NUREG-1138) Encl

{{Adams
| number = ML20133C197
| issue date = 07/27/1985
| title = Notice of Renewal of License R-28.Environ Assessment & SER (NUREG-1138) Encl
| author name = Thomas C
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name = 
| addressee affiliation = 
| docket = 05000002
| license number = 
| contact person = 
| case reference number = RTR-NUREG-1138
| document report number = NUDOCS 8508060388
| package number = ML20133C176
| document type = FEDERAL REGISTER NOTICES, TEXT-CODE OF FEDERAL REGULATIONS
| page count = 52
}}

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7590-01 UNITED STATES NUCLEAR RECULATORY COMMISSION ~-'
NOTICE OF RENEWAL 0F FACILITY OPERATING LICENSE UNIVERSITY OF MICHIGAN DOCKET NO. 50-2 The U.- S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 29 to Facility Operating License No. R-28 for the University of Michigan (the licensee) which renews the license for operation of the training and research reactor located in Ann Arbor, Michigan. The facility is a non-power reactor that has been operating at power levels not in excess of two megawatts (thermal). The renewed Operating License No. R-28 will expire twenty years from the date of issuance.
The amended license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I. Those findings are set forth in the license amendment. Oppor-tunity for hearing was afforded in the notice of the proposed issuance of this renewal in the Federal Register on January 15, 1985 at 50 FR 2115.
No request for a hearing or petition for leave to intervene was filed fol-lowing notice of the proposed action.
The Commission has prepared a Safety Evaluation Report (NUREG-1138) for the renewal of Facility Operating Lice,se No. R-28 and has, based on that report, concluded that the facility can continue to be operated by the licensee without endangering the health and safety of the public.
SBRS IBan BITgg2 F

7590-01 The Commission also has prepared an Environmental Assessment, dated May 15, 1985, for the renewal of Facility Operating License No. R-28 and has concluded that this action will not have a significant effect on the quality of the human environment. The Notice of Finding of No Significant Environmental Impact was published in the Federal Registe_r on July 26, 1985 at 50 FR 3'0547.
For further details with respect to this action, see (1) the at, plication for amendment dated November 30, 1984, as supplemented, (2) the Finding of Ho    -
Significant Environmental Impact, (3) Arendment No. 29 to Operating License
     ~
R-28, (4) the Conmission's related Safety Eveluation Report (NUREG-1138),
and (5) the Environmental Assessment. These items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W.,
Washington, D.C. 20555.
Copies of NUREG-1138 may be purchased by calling (202) 275-2060 or (202)275-2171 or write the Superintendent of Documents, U.S. Government Printing Office, Post Office Box 37082, Washington, D.C. 20013-7982.
Dated at Bethesda, Maryland, this      day of           .
FOR THE NUCLEAR REGULATOPY COMMISSION Q, Yr;: =
Cecil 0. Thomas, Chief Standardization & Special
-                                            Projects Branch Division of Licensing o
9

faa%ge UNITED STAIES E         7,              NUCL5AR REGULATORY COMMISSION
$                                  WASHINGTON, D. C. 20555
%...../                                                              _ _ .
ENVIFONFENTAL ASSESSMENT FOR THE TRAINING AND RESEARCH REACTOR OF THE UNIVERSITY OF MICHIGAN LICENSE N0. R-28 DOCKET N0. 50-2 Description of Proposed Action This Environmental Assessment is written in connection with the proposed renewal for 20 years of the operating license of the research reactor at the University of Michigan (UM) facility located on the North Campus of the University in Ann Arhor, Michigan, in response to a timely application from the licensee dated November 30, 1984, as supplemented. The proposed action would authorire continued operation of the reactor in the nanner that it has been operated since facility license No. R-28 was issued in 1957. Currently, there are no plans to change any of the structures or operating characteristics associated with the reactor during the renewal period requested by the licensee.
Need for the Proposed Action The operating license for the facility was due to expire in January 1985.
The proposed action is required to authorize continued operation so that the facility can continue to be used in the licensee's mission of education and research.
Alternatives to the Proposed Action As required by Section 102(2)(E) of NEPA (42 U.S.C.A. Q4332(2)(E)), the staff h3s considered possible alternatives to the proposed action. The only reasonable alternative to the proposed action that was considered was not renewing the operating license. This alternative would have led to cessation of operations, with a resulting change in status and a likely small impact en the environment. From the standpoint of environmental impact, there are no appropriate alternatives to the proposed action.
Environmental Inpact of Continued Operation The UM reactor operates in an existing shielded water tank inside an existing single purpose building attached to a multi-purpose building.
No new construction is associated with continued operation of the reactor and there is no change in reactor operating conditions or practices.
Therefore, this licensing action would lead to no change in the physical environment.

Based on the review of the specific facility operating characteristics that are considered for potential impact on the environment, as set _ forth.in the staff's Safety Evaluation Report (SER)y for this action, it is concluded that reneral of this operating license will have an insignificant environ-mental impact.
Argon-41, a product from neutron irradiation of air during operation, is
                   - the principal airborne radioactive effluent from the UM reactor during routine operations. Conservative calculations by tha staff, based on the total amount of Ar-41 released from the reactor during a year, predict a maximum potential annual whole body dose of less than 1 millirem in unrestricted areas. Radiation exposure rates measured outside of the i                   reactor facility building are consistent with this computation.
l The staff has considered hypothetical credible accidents at the UM reactor and has concluded that there is reasonable assurance that such accidents will not release a significant quantity of fission products from the fuel cladding and, therefore, will not cause significant radiological hazard to the environment or the public.
This conclusion is based on the following:
a) the excess reactivity available under the technical specifications is insufficient to support a reactor transient generating enough energy to cause overheating of the fuel or loss of integrity of the cladding, 1
l                   b) at a thermal power level of 2 Mw, the inventory of fission products in the fuel cannot generate sufficient radioactive decay heat to cause
,                               fuel damage even in the hypothetical event of rapid total loss of coolant, and
                                                ~
c) the hypothetical loss of integrity of the cladding of the maxinun irradiated encapsulated fueled experiment will not lead to radiation exposures in the unrestricted environrent that exceed guideline values of 10 CFR Part 20.
In addition to the analyses in the SER summarized above, the environmental impact associated with operation of research reactors has been generically                                          ,
evaluated by the staff and is discussed in the attached generic evaluation.
This evaluation concludes that there will be no significant environnental impact associated with the operation of research reactors licensed to operate at power levels up to and including 2 ffWt and that an Environmentel Impact Statement is not required for the issuance of construction pernits or operating licenses for such facilities. We have determined that this generic evaluation is applicable to the continued operation of the UP reactor and that there are no special or unique features that would preclude reliance on the generic evaluation.
I NUREG-1138, " Safety Evaluation Report Related to the Renewal of the Operating License for the Training and Research Reactor at the University of Michigan.
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Agencies and Persons Consulted The staff has obtained technical assistance from the Los Alamos National Laboratory in performing the safety evaluation of continued operation of the VM facility.
Conclusion and Basis for No Significant Impact Finding Based on the foregoing considerations, the staff has concluded that there will be no significant environmental impact attributable to this proposed license renewal. Having reached this conclusion, the staff has further concluded that no Environmental Impact Statement for the proposed action need be prepared and that a No Significant Environmental Impact Finding is appropriate.
Dated: May 15, 1985 i
l

ENVIRONMENTAL CONSIDERATIONS REGARDING THE LICENSING-0F RESEARCH REACTORS AND CRITICAL FACILITIES Introduction This discussion deals with research reactors and critical facilities which
      - are designed to operate at low power levels, 2 MWt and lower, and are used primarily for basic research in neutron physics, neutron radiography, isotope production,. experiments associated with nuclear engineering, training and as a part of a nuclear physics curriculum. Operation of such facilities will generally not exceed a 5-day we'ek, 8-hour day, or about 2000 hours per year.
Such reactors are located adjacent to technical service support facilities with convenient access for students and faculty.
Sited most frequently on the campuses of large universities, the reactors are usually housed in already existing structures, appropriately modified, or placed in new buildings that are designed and constructed to blend in with existing facilities.      However, the environmental considerations discussed herein are not limited to those which are part of un'iversities.          -
                  '       ~
                                                                   ],
Facility                                                                       ,
There are no exterior conduits, pipelines, electrical or mechanical structures or transmission lines attached to or adjacent to the facility other than,for.
utility services, which are similar to those required in other similar facilities, specifically laboratories. Heat dissipation is generally accom-plished by use of a cooling tower located on the roof of the buildhg. These cooling towers typically are on the order of 10' x 10' x 10' and are comparaule to cooling towers associated with the air-conditioning systems of large office buildings.
Make-up for the cooling system is readily available and usually obtained from the local water supply. Radioactive gaseous effluents are limited to Ar-41 and the release of radioactive liqu.id effluents can be carefully monitored and controlled. Liquid wastes are collected in storage tanks           ,
to allow for decay and monitoring prior to dilution and release to the sani-     l tary sewer system. Solid radioactive wastes are packaged and shipped off-site for storage at NRC-approved sites. The transportation of such waste is done in accordance with existing NRC-D0T regulations in approved shipping containers.                                                                 "
Chemical and sanitary waste systems are similar to those existir.o at other similar laboratories and buildings.

Environmental Effects of Site Preparation and Facility Construction Construction of such facilities invariably occurs in areas that have already been disturbed by other building construction and, in some cases, solely within an already existing building. Therefore, construction would not be expected to have any significant effect on the terrain, vegetation, wildlife or nearby waters or aquatic life. The societal,' economic and esthetic impacts of construction would be no greater than those associated with the construction
        ~
of a large office building or similar research facility.
Environmental Effects of Facility Operation Release of thermal effluents Trom a reactor of less that 2 MWt will not have a significant effect on the environment. This small amount of waste heat is generally rejected to the atmosphere by means of small cooling towers. Ex-tensive drift and/or fog will not occur at this low power level.
Release of routine gaseous effluents can be limited to Ar-41, which is generated by neutron activation of air. Even this will be kept as low as practicable by using gases other than air for supporting experiments. Yearly doses to unre-stricted.. areas will be at or below established guidelines in 10 CFR 20,_ limits.
  .       Routin.e-releases of radioactive _ liquid. effluents can be carefully monitored and controlled in a manner that will ensure compliance witW current standards. Solid radioactive wastes will be shipped to an authorized disposal site.in approved '
cont'ainers. These wastes should not require more than a few shipping cordainers a year.                                                                                          _ . . . .
Based on experience with other research reactors, specifically TRIGA reactors operating in the I to 2 MWt range, the annual release of gaseous and liquid effluents to unrestricted areas should be less than 30 curies and 0.01 curies, respectively.
No release of potentially. harmful . chemical. substances will occur during normal cperation. Small amounts of chemicals and/or high-solid content water may be released from the facility through the sanitary sewer during periodic blowdown of the cooling tower or from laboratory experiments.
Other potential effects of the facility, such as esthetics, noise, societal or impact on local flora and fauna are expected to be too small to measure.
Environmental Effects of Accidents Accidents ranging from the failure of experiments up to the largest core damage and fission product release considered possible result in doses that are less then 10 CFR Part 20 guidelines and are considered negligible with respect to the environment.

Unavoidable Effects of Facility Construction and Operation The unavoidable effects of construction and operation involve.the materials used in construction that cannot be recovered and the fissionable material used in the reactor. No adverse impact on the environment is expected from either of these unavoidable effects.
          ~
Alternatives to Construction and Operation of the Facility To accomplish the objectives associated with research reactors, there are no suitable alternatives. Some of these objectives are training of students in the operation of reactors, production of radioisotopes, and use of neutron and gamma ray beams to conduct experiments.
                                                                                                  ~
Long-Term Effects of Facility Construction and Operation The long-term effects of research facilities are considered to be beneficial as"a result of the contribution to scientific knowledge and training. Because . u of the relatively small amount of capital resources . involved and the small impact on the . environment, very little irreversible and irretrievable commit-ment is~ associated with such facilities. -c              --
                                                                           ~ ~                  '
Costs ind Benefits of Facility Alternatives The costs are on the order 'of several millions of dollars with very little   -
environmental impact. The benefits include, but are not limited to, some combination of the following: conduct of activation analyses, conduct of neutron radiography, training of operating personnel and education of students.
Some of these activities could be conducted using particle accelerators or radioactive sources which would be more costly and less efficient. There is no reasonable alternative to a nuclear research reactor for conducting this spectrum of activites.~~
Conclusion                                                                        ,
The staff concludes that there will be no sig..!ficant environmental impact associated with the licensing of research reactors or critical facilities designed to operate at power levels.of 2 MWt or lower and that no environmental impact statements are required to be written for the issuance of construction permits or operating licenses for such facilities, i
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f i#PENDIX A TO FACILITY LICENSE R-2G TECHNICAL SPECIFICATIONS DOCKET 50-2 MICHIGAN MEMORIAL PHOENIX PROJECT THE UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN JULY 1985 I
4

O    d TECHNICAL SPECIFICATIONS
;                                                              Ford Nuclear Reactor Docket 50-2, License R-28
         ,                                                                   November, 1984 Contents 1.0   DEFINITIONS                                                                    1 2.0   SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS                              6 2.1   Safety Limits                                                                  6 2.1.1    Safety Limits in the. Forced Convection Mode                                                       6 2.1.2    Safety Limits in the Natural Convection Mode                                                       6 2.2   Limiting Safety System Settings (LSSS)                                         7 2.2.1    Limiting Safety System Settings in the Forced Convection Mode                                                7 2.2.2    Limiting Safety System Settings in the Natural Convection Flow Mode                                          8 3.0   LIMITING CONDITIONS FOR OPERATION                                              9 3.1   Reactivity Limits                                                              9 3.2   Reactor Safety System                                                         10 3.3   FNR Confinement Building                                                      15 3.4   Primary Coolant Conditions                                                    16 3.5   Heavy Water Reflector Tank                                                    17 3.6   Airborne Effluents                                                            18 3.7   Liquid Effluents                                                              19
* 3. 8  Limitations of Experiments                                                    20 3.9   Fission Density Limit                                                         22 4.0   SURVEILLANCE REQUIREMENTS                                                     23 4 .,1 Reactivity Limits                                                             23 4.2   Reactor Safety System                                                         24 4.3   FNR Confinement Building                                                      25 4.4   Primary Coolant System                                                        26 4.5   Heavy Water Reflector Tank                                                    27 4.6   Airborne Effluents                                                            28 4.' 7 Liquid Effluents                                                              28 4.8   Fission Density Limits                                                        29 5.0   DESIGN FEATURES                                                               30 5.1   Site Description                                                              30 5.2   Reactor Fuel                                                                  30 5.3   Reactor Building                                                              31 5.4   Fuel Storage                                                                  31 Contents-1

a o TECHNICAL SPECIFICATIONS                        1 Ford Nuclear Reactor                            i Docket 50-2, License R-28 November, 1984 6.0   ADMINISTRATIVE CONTROLS                33 6.1   Organi:ation                           33 6.2   Review and Audit                       34 6.3   Action to be Taken in the Event of a Reportable Occurrence                  37 6.4   Operating Procedures                   37 6.5   Operating Records                      38 6.6   Reporting Requirements                 39 1
1 Contents-2

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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 1.0   DEFINITIONS Channel Calibration - A channel calibration is an adjustment of the channel such that its output corresponds with acceptable occuracy to known values of the parameter which the channei measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, and trip, and shall be deemed to include the channel test.
Channel Check - A channel check is a qualitative verification of acceptable perf ormance by observation of channel behavior. This verification where possible shall include comparison of the channel with other independent channels or systems measuring the same variable.
Channel Test - A channel test is the introduction of a signal into the ch     1el to verify that it is operating.
Experimens       n experiment, as used herein, is any of the following:
(1) An activity utilizing the reactor system or its components or the neutrons or radiation generated therein; (2) An evaluation or test of a reactor system operational.
surveillance, or maintenance techni que; (3) An experimental or testing activity which is conducted within the confinement or containment system of the reactor; (4) The material content of any of the foregoing, including structural components, encapsulation er confining boundaries, and contained fluids or solids.
Experimental Facility - An experimental facility is any structure or device which is intended to guide, orient, position, manipulate, or otherwise facilitate a multiplicity of experiments of similar character.
Explosive Material - Explosive material is any solid or liquid which is categori:ed as a severe, dangerous, or very dangerous explosion hazard in DANGEROUS PROPERTIES OF INDUSTRIAL MATERIALS by N.I. Sax, Third Ed. (1968), or is given an Identification of Reactivity (Stability) Index of 2,3, or 4 by the National Fire Protection Association in its publication 704-M, 1966.
Limiting Conditions f or Operation (LCO) - Lowest functional capability or performance levels of equipment required for safe operation of the reactor (10CFR50.36).
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e e TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Limiting Safety System Setting (LSSS) - Settings for automatic protective devices related to those variables having significant safety functions, and chosen so that automatic protective action will correct an abnormal situation bef or e a 5afety 11aeit is eaceeded (10CFR50.36).
Measured Value - The measured value of a process variable is the value of the variable as indicated by a measuring channel.
Measuring Channel - A measuring channel is the combination of sensor, amplifiers, and output devices which are used for the purpose of measuring the value of a process variable.
Moveable Experiment - A moveable experiment is one which may be inserted, removed, or manipulated while the reactor is critical.                                                                  .
Operable - Operable means that a component or system is capable of performing its intended function in its normal manner.
Operating - Operating means that a component or system is performing its intended function in its normal manner.
Potential Reactivity Wo-th of an Experiment - The potential reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of intended or anticipated changes or credible malfunctions that alter equipment position or configuration.
Reactivity Limits - The reactivity limits are those limits
,     imposed on reactor core excess reactivity.       Quantities are referenced specifically to a cold core (nominally 90 F) with the effect of ':enon poisoning on core reactivity accounted for if greater than or equal to 0.05% Delta K/K. The reference core condition will be known as the cold, xenon free critical condition.
Reactor Operation - Reactor operation means that the control rods installed in the core are not fully inserted or that the control console key is in the keyswitch.       Reactor operation is not considered possible when there are less than six fuel elements loaded on the grid plate.
Reactor Safety System - The reactor safety system is that combination of safety channels and associated circuitry which forms the automatic protective system for the reactor or provides information which requires manual protective action to be initiated.
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TECHNICAL SPECIFICATIONL Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Reactor Scram - Shutoff of electrical current to the rod holding magnets and subsequent insertion of the rods into the core by gravity.
Reactor Secured - Reactor Secured is defined ao follows:
(1) The full insertion of all control rods has been verified; (2) The control console key is removed; and (3) No operation is in progress which involves moving fuel elements to or from the core, moving reflector elements to or from the core, the insertion or removal of secured experiments from the core, or control rod maintenance.
Readily Available on Call - Readily available on call shall mean a licensed senior operator shall insure that he can be contacted and is within a reasonable driving time (1/2 hour) from the reactor building when the reactor is being operated by a licensed operator.
Regulating Rod - The regulating rod is a control rod of low reactivity worth fabricated from stainless steel and used to control reactor power. The rod may be controlled by the operator with a manual switch or by an automatic controller.
Removable Experiment - A removable experiment is any experiment, experimental facility, or component of an experiment, other than a permanently attached appurtenance to the reactor system, which can reasonably be anticipated to be moved one or more times during the life of the reactor.
Reportable Occurrence - A reportable occurrence is any of the following:
(1) A safety system setting less conservative than the limiting setting established in the Technical Specifications; (2) Operation in violation of a limiting condition for
!                   operation established in the Technical Specifications; l
!              (3) A safety system component malfunction or other component or system malfunction which could, or threatens to, render the safety system incapable of performing its j                   intended safety functions; (4) Release of fission products from a failed fuel element; Page 3

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor
      ' Docket 50-2, License R-28 November, 1984 (5) An uncontrolled or unplanned release of radioactive material from the restricted area of the facility; (6) An uncontrolled or unplanned release of radioactive material wnich results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Appendix B, Table 1 of 10CFR20; (7) An uncontrolled or unanticipated change in reactivity in excess of 0.005 delta K/K; (8) Conditions arising from natural or man made events that affect or threaten to affect the safe operation of the facility; (9) An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the faciltiy.
Rundown - A rundown is the automatic insertion of the shim safety rods.
Safety Channel - A safety channel is a measuring channel in the reactor safety system.
Safety Limit (SL) - Limits upon important process variables which are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity (10CFR50.36).
Secured Experiment - Any experiment, experimental facility, or cotaponent of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor by mechanical means. The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or of forces which might arise as a result of credible malfunctions.
Shim Safety Rod - A shim saf ety rod is a control rod fabricated from borated stainless steel which is used to compensate for fuel burnup, temperature, and poison effects. A shim safety rod is magnetically coupled to its drive unit allowing it to perform the function of a safety. rod when the magnet is deenergized.
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l TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Static Reactivity Worth - The static reactivity worth of an experiment is the absolute value of the reactivity change which is measurable by calibrated control rod comparison methods between two defined terminal positions or configurations of the
: e. . p u t.ner L . For moveable experidients, the terminal pos1 Lions are fully removed from the reactor and fully inserted or installed in the normal functioning or intended position.
Time Intervals Annually - 12 to 15 months.
Biannually - 24 to 00 months.
Daily - 24 to 32 hours.
Monthly - 30 to 40 days.
Quarterly - 3 to 4 months.
Semiannually - 6 to 8 months.
Weekly - 7 to 10 days.
True Value - The true value of a process variable is its actual value at any instant.
Unscheduled Shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not to include shutdowns which occur during testing or checkout operations.
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. i TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 2.O    SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1    Safety Limits 2.1.1 Safety Limits in the Forced Convection Mode Applicability:
This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the steady state with forced convection flow.         These variables are:
Reactor Thermal  Power, P Reactor Coolant  Flow Through the Core, m Reactor Coolant  Inlet Temperature, Ti Height of Water  Above the Top of the Core, H Objective:
To assure that the integrity of the fuel clad is maintained.
Specifications (1) The true value of reactor power (P) shall not exceed 4.68 Mw and the true value of flow (m) shall not be less than 900 gpm.
(2) The true value of reactor coolant inlet temperature (Ts) at 2 Mw shall not exceed 116 F.
(C) The true value of water height above the core (H) shall not be less than 18 feet while the reactor is operating.
Bases:
The basis for forced convection safety limits is that the calculated maximum cladding temperature in the bottom of the htt channel of the most compact FNR core (25 elements) will not reach the boiling point of the water coolant.
2.1.2 Safety Limits in the Natural Convection Mode Applicability:
This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the natural convection mode of operation. These variables are Reactor Thermal Power, P Reactor Coolant Inlet Temperature, Ti Height of Water Above the Top of the Core, H Page 6

s s TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Objective:
To assure that the integrity of the fuel clad is maintained.
SPECificatiCn:
(1) The true value of the reactor thermal power (P) shall not exceed 380 kw.
(2) The true value of the reactor coolant inlet temperature (Tt ) shall not exceed 131 F.
(3) The height of pool water above the core (H) shall not be less than 18 feet.
Bases:
The basis f or natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact FNR core (25 elements) will not reach the boiling point of the water coolant at a depth of 18 feet.
2.2   Limiting Safety System Settings (LSSS) i 2.2.1 Limiting Saf ety System Setting in the Forced Convection Mode Applicability:
This specification applies to the set points for the safety channels monitoring reactor thermal power (P), primary coolant flow (m), height of water above the top of the core (H), and core enit temperature    (T.).
Objective:
To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
Specifications (1) The limiting safety system settings for reactor thermal power (P), primary coolant flow through the core (m),
height of water above the top of the core (H), and reactor coolant exit temperature (T.) shall be as follows:
Variable           (SSS P (Max)           2.4 Mw m (Min)          700 gpm H (Min)           19 ft T.(Max)           129 F Page 7

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Bases:
The limiting safety system settings for forced convection assure that automatic protective action will correct the most t reere atncrmal rituaticn anticipated bercre a safety lim:t ic exceeded.
2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability:
These specifications apply to the setpoint for the safety channels monitoring reactor thermal power (P), pool water level 04 ) , and pool water temperature (T).
Objective:
To assure that automatic protective action is initiated to prevent a safety limit from bei*ng exceeded.
Specifications:
(1) The limiting safety system setting for reactor thermal power (P), height of water above the top of the core 04 ) , and pool water temperature (T) shall be as follows:
Variables        LSSS P   (Max)       100 kw H  -(Min)       19 ft T   (Ma:: )     129 F Bases:
The limiting safety system settings for natural convection assure that automatic protective action will correct the most severe abnormal situation anticipated before a safety limit is exceeded.
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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 3.0   LIMITING CONDITIONS FOR OPERATION 3.1   Reactivity Limits Applicability:
This specification applies to the reactivity of the reactor core and to the reactivity worths of control rods and experiments.
When the reactor is operated with the heavy water reflector tank in place, the limits will not include the static reactivity worth of the tank.
Objective:
To assure that the reactor can be controlled and shutdown at all times and that the safety limits will not be exceeded.
Specification:
(1) The shutdown margin relative to the cold. xenon free critical condition shall be at least .025  delta K/K with all three shim safety rods fully inserted  and the regulating rod fully withdrawn and 0.0045  delta K/K with the most reactive shim safety rod and the  regulating rod fully withdrawn.
(2) The overall core excess reactivity including moveable experiments shall not exceed 0.038 delta K/K.
(3) The total reactivity worth of all enperiments shal'. not exceed 0.012 delta K/K.
(4) The reactivity worth of each enperiment shall be limited as follows:
Maximum Exoeriment          EJacti tity Worth Moveable            0.0012 delta K/K Secured             0.012 delta K/K (5) The reactor shall be subtritical by at least 0.03 delta K/K during fuel loading changes.
(6) Shim safety rods shall not be removed from the core for inspection if the shutdown margin is less than 0.01 delta K/K with the most reactive remaining shim safety rod fully withdrawn.
(7) The reactivity worth of the regulating rod shall not exceed 0.006 delta K/K.
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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 (8) Experiments which could increase reactivity by flooding, shall not remain in or adjacent to the core unless the shutdown margin required in Specification 3.1.(1) would be satisfied after flooding.
Bases:
f                                                            The shutdown margin required by Specification 3.1.(1)
{                                                     assures that the reactor can be shutdown from any operating condition and will remain subcritical after cooldown and xenon decay even if the rod of the highest reactivity worth should be in the fully withdrawn position.
i Specification 3.1.(2) limits the allowable encess reactivity to the value necessary to overcome the combined negative reactivity effects of: (1) an increase in primary coolant temperature from 90 F to 116 F; (2) fission product xenon and samarium buildup in a clean core; (3) power defect due to increasing from a :ero power, cold core to a 2 Mw, hot core; (4) fuel burnup during sustained operation for 30 days; and (5) moveable experiments.                                               l Specification 3.1.(3) limits the reactivity worth of experiments to values of reactivity which, if introduced as positive step changes, will not cause fuel melting.
Specification 3.1.(4) limits the individual reactivity worth of experiments to values that will not produce a stable period of
!                                                     less than 30 seconds and which can be compensated for by the action of the control and safety systems without exceeding any safety limits.
Specifications 3.1.(5) and 3.1.(6) provide assurance that the core will remain subcritical during fuel loading changes and shim safety rod maintenance or inspection.
Specification 3.1.(7) assures that failure of the automatic control system will not introduce sufficient excess I                                                     reactivity to produce a prompt critical condition.
Specification 3.1.(8) assures that the shutdown margin required by Specification 3.1.(1) will be met in the event of a positive reactivi ty insertion caused by the flooding of an experiment.
3.2    Reactor Safety System Applicability:
These specifications apply to the reactor safety system and other safety related instrumentation.
Page 10

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Objective:
To specify the lowest acceptable level of performance or the minimum number of acceptable components for the reactor safety tf ttom And cther safety .clated i n s t r u.nen t a t i on .
Specification:
The reactor shall not be made critical unless:
(1) The reactor safety systems and safety related instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minimum number of channels and the indicated maximum or minimum setpoints; (2) All shim safety rods are operable; (3) The time from the initiation of a scram condition in the scram circuit until the shim safety rods are fully inserted (release-drop time) shall not exceed 500 milliseconds; (4) Mechanical devices are installed which prevent the lifting of fuel elements through the movement of control rods.
Bases:
Neutron flux level scrams pros)de redundant automatic protective action to prevent enceedirg the safety limit on reactor poier. The period scram limits the rate of rise of the reactor                           ]
i power to periods which are manually controllable without reaching                           I excessive power levels or fuel temperatures.
* Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram will occur in the event of a loss of flow when the reactor is operating at power levels above 100 kw.
The rod withdrawal interlock on the Log Count Rate channel assures that the operator has a measuring channel operating and indicating neutron flux levels during the approach to criticality.
The core e: tit temperature auto rundown function and response of the operator to the pool level alarm assure that the reactor will not be operated above the safety limit for core inlet temperature and below the safety limit for pool level.
l Page 11

P TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 November, 1994 Table 3.1 REQUIRED SAFETY CHANNELS M ; n . .r.un.
Number Channel                      Setooint         Recuired       Function Log Count Rate               2 cps                   1       Rod Withdrawal Interlock Log N Period                                         i       Wide range power level and input for period scram        ;
Period Safety                5 sec                   1       Scram Level Safety                 120%(2.4 Mw)           2        Scram High Power /No               (a) 900 gpm             i       Scram 1100 kw Water Flow             (b) holdup tank isolation valve not fully open (c) holdup tank static pressure 1 psig below full power value High Power /
Header Down                                   i       Scram 1100 kw Header Up/                   900 gpm                 1       Scram No Water Flow Building Exhaust             1 mr/hr                 1       Scram Radiation Level Building Alarm                                       1       Scram Manual Switch Manual Scram Switch                                   1      Scram Magnet Power Keyswitch                                1      Scram Reactor Coolant Exit Temp.             129 F                   1      Auto Rundown Pool Level                   1 foot below pool 1            Auto Pundown overflow Bridge Not                  When clamps              1       Scram Clamped                  released Page 12

TECHNICALSPEChFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Table 3.2 Required Safety Related Instrumentation Minimum Number Instrumentation                            Setooint                  Pecaired            Function Linear Level Channel                       As Required                  1                Linear power level measurement and input for the automatic control mode Power Level Deviation                      95% cf control                1               Return reactor to Interlock                            point setting                                 manual control mode if setpoint is reached Reactor Coolant Inlet                      Not Applicable                1(a)            Provide Temperature                                                                         information for the heat balance
:                                                                                                       determination l
i Facility Radiation
* l                   Monitor System (b) l              1. Building Air Eahaust                     1(1)            mr/hr        i               Alarm, scram, initiate l
confinement evacuation
;              2. Reactor Bridge                           00(50) mr/hr                 1               Alarm l
0 .~ NW Column. Beamport                    10(50) mr/hr                 1(c)            Alarm Floor
: 4. N Wall, Beamport                          5(50) mr/hr                 1(c)            Alarm                          7
;                       Floor                                                                                                          i l
t 5..NE Column, Beamport                       2(50) mr/hr                 1(c)            Alarm Floor                                                                                                          ,
: 6.       Primary Deminer-                   20(50) mr/hr                 1(c)            Alarm                          I ali:er (Hot D1) r               (a) Not required for natural convection operation.
I                                                                                                                                      ,
(b) The f acility radiation monitoring system consists of 6 radiation detectors which alarm and read out locally, and are recorded in the control room.                        The normal setpoints for this system are shown.           The value in parentheses is the manimum Page 13             ,

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 Table 3.2 Required Saf ety Rel ated Instrumentation (continued) s a t o o i n '- which will be used dnoendian en l oc H condittmos.
Use of higher then normal setpoints will require approval of the Reactor Manager or the Assistant Reactor Manager. Any reactor staff member may adjust a setpoint lower than the normal value.
(c) Of the detectors labelled 3-6,      any one unit may be out of service for a period not to exceed 7 days without requiring reactor shutdown or replacement by a locally alarming monitor with similar range. Should a second of these units require repair, such repair must be completed within 24 hours or the reactor must be shutdown or replacement of the second unit with a locally alarming monitor of similar range is required.
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I Page 14 l

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 The manual scram button and the magnet power keyswitch provide two methods for the reactor operator to manually shutdown the reactor if an unsafe or abnormal condition should occur and the automatic reactor protection does not function.
The use of the area radiation monitor system assures that areas of the facility in which a high radiation area could exist are monitored.
Specifications 3.2.(2) and 0.2.(0) assure that the safety system response will be appropriate.
0.0     FNR Confinement Building Applicability:
This specification applies to the FNR confinement building                                                  ,
requirements.
Objective To minimi:e the release of airborne radioactive materials from the FNR.
Specifications (1) The ventilation intake and enhaust dampers, the intake and exhaust ventilating fans. and the dampers in the beamport enhaust system and the room 0100 exhaust hood duct shall automatically close when the radiation level                                                I in the building ventilation eahaust duct is 1 millirem / hour or more.
(2) During reactor operation. the following conditions will be administrattvely controlled
: a. Personnel access doors will be closed except as necessary for the passage of personnel and/or equipment;
: b. The main equspment access door onto the beaanport floor will be opened only long enough to permit the passage of equipments
: c. The personnel door to the cooling tower area will remain clamped except to permit the passage of personnel and/or equipment to the cooling tower area.             The door will remain closed but not clamped until all personnel have left the                                                   ,
l cooling tower areal Page 15

v 0 TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28                                                     i November. 1994
: d. The access hatch from grade level to the beamport floor will be sealed closed;
: e. The personnel exit door located in the north ali c* thu W114ing A id LM : ;c.' I c c. . t e d a t h ee beamport floor which connects to the PML hot cave operating area will be clamped closed.
Bases:
The potenti al radiation exposure to persons at the operations boundary following an accident releasing fission products within the confinement building has been evaluated. The evaluation used a leakage rate from the confinement building of 10% of the building volume per day, and concluded that the accident doses would be acceptable. Confccmance to Specifications
: 3. 3. (1 ) and 2.0.(2) will assure that the building leak rate will not e.:ceed the leak rate used in the evaluation.
;             The 1.0 mr/hr setpoint for the facility exhaust radiation monitor provides a mechanism for isolating the bu11 ding ventilation system in the event of a sign 1+1 cant release of radioactive mater.a1 Into the reactor butiding. This setpoint, for the detector location involved. represents a gamma emitting nuclide concentration of 10-2 to 10-* microcuries/cc of building air.
By requiring that the access doors and equipment hatch romain closed, except for brief, attended pericds to permit personnel or equipment passage, the integrity of the confinement will be maintained at or below the value assumed in the Ha:ards Summa y Repcet, end the release of radioactive material will be minimi:ed.
0.4   Primary Coolant Conditions App 1tcability:
This specification applies to the limiting conditions for available pool water volume, primary coolant pH. resistivity, radioactivity, and flow distribution.
Objective To maintain the primary coolant in a condition to minims:e the corrosion of the primary ccolant system. fuel clad. and other reactor components, and to assure proper conditions of coolant for normal and emergency requirements.
Page 16

{
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l                                                                                                                       TECHNICAL SPECIFICATIONS
!                                                                                                                           Ford Nuclear Peactor
}                                                                                                                      Docket 50-2. License R-28 November, 1984
(
Specification:
1
;                                                                                  (1) The primary coolant pH shall be maintained between 4.5 l                                                                                      and 7.5.
(2) The primary coolant resistivity shall be maintained at a value greater than 200,000 ohm-cm e:: cept for periods of time not to e.Nceed 7 days when the resistivity may not be less than 50.000 chm-cm.
(3) For cperation at power levels in excess of 100 kw in the fceced convection mode. all grid positions shall contain fuel elements. reflector elements, grid plugs or e>: p er i men t al facilities.
(4) For operation at powers in e;: cess of 1 Mw. the pool gate must be in its storage location.
Bases:
Experience at this and other facilities has shown that the maintenance of priinary coolant system water quality in the rangen specified in Specification 3.4.(1) and 0.4.(2) will control the corrosion of the aluminum components of the primary coolant system and the fuel element cladding.
The requirement that all grid positions be occupied will prevent the degradation of flow rates due to flow bypassing the Acttve fueled region through an unoccupied grid pl. ate position.
The requirement that the gate be stored assures that the full vol.ime of the pool water is available to provide cooling of the core during normal operation and in the event of a losn of coolant ac:1 dent.
: 3. 5   Heavy Water Reflector Tank Applicability:
This specification applies to the heavy water reflector tant used in the reactor core.
Objective:
To assure that heavy water handling in the heavy water reflector tant does not jeopardt:e facility and personnel safety.
Page 17

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 November, 1984 Specifications (1) The shutdown margin for the core shall not be less than 0.10 delta N/N whenever heavy water movements which can "m  ' t te postta m -23ct: :t   intcet.cr2 3r   'md art; t tr .
(2) The tritium content of the heavy water reflector tank shall be no greater than 50 curies.
bases:
The largest positive reactivity increase that can be produced by replacing light water with heavy water in the heavy water reflector tank is 0.04 delta K/K.      Maintaining the reactor shutdown margin at no less than 0.10 delta N/K during heavy water transfers provides adequate margin to assure that the reactor will remain subcritical during heavy water transfers that could add positive reactivity.
The 50 curie limit imposed on the tritium content of the heavy water reflector tant in Specification 0.5.(2) assures that offsite concentrations of tritium in the event of a tank rupture will not onceed the limit established in 10CFR20 for tritium releases to uncontrolled areas.
0.6    Airborne Effluents Applicability:
This specification applies to the monitoring of airborne effluents from the FNR.
Objuctive:
To assure that containment integrity is maintained during reactor operation and that the release of airborne radioactive material from the FNR is maintained below the limits established in 10CFR20.
Specificattens (1) The concentration of radteactive materials in the effluent released from the facility exhaust stac6s shall not onceed 400 times the concentrations specified in 10CFR20, Appendia D, Teblo !!. when averaged over timo periods ourma tted by 10CFR20.
(0) During operation of the reactor. the follcwing conditions shall be mott Page 10

o .
TECHNICAL SFECIFICATION3 Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984
: 4. The particulate activity monitor and the gaseous activity monitor fcr the facility exhaust stacks shall be operating. If either unit is to be out of service for more than 24 hours. either the rt. :tur tha'1
                                      . to . hut h n s.- tai v..i t ch ll to replaced by one of comparable monitoring capability;
: b. The particulate acti vity monitor and the gaseous activity monitor for the reactor building shall be operating. Temporary shutdown of these units shall be limited as in specification 3.6.(2).a above;
: c. The building enhaust air radiation moniter shall be operating whenever the reactor is in operation as required by Table'3.2 of specification 0.2.
Bases:
1 The limits established in specification 3.6 (1) incorporate i     a dilution factor of 400 for effluents released through the i     eahaust stacL1. This dilution factor was calculated from actual l     FNR site meteorological data and represents the Icwent dispersion factor determined and the ble) hest frequency of wind in any sector.
l     Decause of the une of the most conservative measured values of l     wind directional froquency and dispersion factcra, this dilutton f actor will assure that concentrations of radioactive material in i
unrestrictod areas around the FNR site will be far belcw the l     limits of 10CFR20.
The requirements of specification 3.6.(2) are constdered adequate tc assure proper airborne effluent monitoring.
l     0.7   Liquid Effluents Applicability:
This specification appites to the monitoring of radioactive l
liquid effluents from the FNR.                                           !
I                                                                              r Objectives:                                                        l The objective 10 to assure that esposure to the public i
resulting from the release of liquid effluents wt11 be minimi:ed.
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l Page 19

TECHNICAL SPECIFICATIONS l                                             Ford Nuclear Reactor Docket 50-2, License R-28 November. 1984 Specification:
I (1) The concentration of radioactiva materials in the effluent released from the facility 11guld waste system tw Llie ...y  vi A a. Ar Lcr t, ,ri a t a r ,wwur 3. v u . on s n .e i l n o t.
l enceed the concentrations specified in 10CFF20 for releases to sanitary sewer s y st eins .
l (2) The amount of 11guld discharged shall be limited to the                         '
equivalent of 0.000 gallons of liquid at the concentration limit speci fied in 0. 7(1) each day.
(3) Liquids from the facility's radioactive liquid waste l
system shall not be discharged into the storm drain system.
Dases:
1 All radioactive 11guld effluents are collected in a series of three. 0,000 gallon. coated. steel retention tanks.                  The liquid
(                                             waste in the tants is sampled and analy:ed bef ore di'scharge. When the concentration is less than the limit of 10CFROC. it is discharged to the sanitary sewer system.
Current esperience requires dischargos of less than 50 tanks por vedr. During 1970. the North Campus water released into ths' l                                             nani t ar y sewer systurn averaged 946.000 gallons per day.               Th19 provides a daily dilution factor of 015 for a 0.000 gallon waste tJnk, which assures that there will be no signi ficant e:'posure to the public f rom radioactive waste ditscharged to the sanitar y sewer systum.
0.0    Limitations of Experiments Applicability:
This specification applies to esperiment's installed in the FNR.
Objectivos To prevent damage to the reactor or excessive release of radioactive materials in the avont of an enpuriment fattore.
Specifications (1) Each unperiment shall be designed so that the surface temperature shell be below the temperature calculated for the inception of nucleate boiling. Prior to                                 -
insertion in the reactor, any capsule which is onpocted to operatsi with an internal pressure in eaceus of one atmosphere shall be tested at a pressure twice the calculated manimum pressure.
Page OC

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 November. 1904 (2) All experiments which Are in contact with reactor coolant shall be either corroston resistant or encapsulated within corrosion resistant containers.
            ''' ? . f.1 ; ; '. ( 1 , ', s . i21s :h al l s;t t ; p '. 2 : c d i r. the raae t :r
!               pool.
(4) Neutron radiography of explosives shall be conducted l               with the eaplosives contained in a blast proof irradiation container, a prototype of which has been successfully tested and demonstrated not to fail by detonation of at least twice the amount of enplosive to be irradiated.
(5) The radioactive material content. Including fission products. of any singly encapsulated experiment should be limited so that the complete release of all gaseous, particulate. and volettle compenents from the encapsulation could not result in doses in excess of 10%
of the equivalent annual doses stated in 10CFR20. This dose limit applies to persons occupying unrestricted areas continuously for two hours starting at time of release and restricted areas during the length of tia a required to evacuate the restricted area.
(6) The radioactive metectal content, including fisstor4 products. of any doubly encapsulated capartment uhot1d be 11ritted so that the complete r elease of all gaseous.
particulate. or volettle components from the encapsulation could not result in doses in eacess of the equivalent annual doses stated in 10CFR 20.                           This dose limit applies to persons occupying unrestricted areas continuously for two hours starting at the time of relemvo and restrteted areas during the length of time required to evacuate the restricted area.
Basesi 3peci f ications 0.0. (1) through 3.8.(4) are intended to reduce the 116 elihood of damage to reactor components and radioactivity releases resulting from esportment failure and serve as a guide for the review and approval of new and untried caper!monts by factltty personnel and the Safety Review Committee.
Neutron radiography is conducted in a vertical beam tube and at hori:cntal beamports that terminato at the heavy water reflector tank adjacent to the reactor core. In the radiography of a:tplosives, the eaplostve devices will be contained. during Page 21

  . .                                                                                    b  ,
j                                                                                         .      .
1 TECHNICAL SPECIFICATIONS Ford Nuclear Reactor i
Docket 50-2. License R-28 November. 1984 enposure. Inside a blast proof enclosure. The enclosure will not be coupled to the beamtube or beamport and will be constructed to fully contain any blast effects or missiles which might be generated by an accidental detonation.
Specifications 0.8.(5) and 0.8.(6) conform to the regulatory position put forth in Regulatory Guide 2.2 issued November. 1970.
The calculations for experiment radioactivity Itmits are provided in section 14.0 of the SAFETY ANALYSIS.
0.9   Fission Density Limit Applicability:
This specification applies to fission density limits in FNR fuel.
Objective To prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products.
Specifications (1) The FNR fission density limit shall be 1.5x1085 fisticn/CC.
Dates The fission density limit is below operational fission densi ti es reach.ed in other operating reactoru using the same Lind of fuel without failures attenbuted to the fuel.
An enportmental data base which supports the uafe use of UA1. and Uv0m fuel in the FNR up to the fission donsity was dortvod from arradiation tests performed in the Materials Test Reactor (MTR). the Engineering Test Reactor (ETR). and the Advance Test Reactor (ATR) at the Idaho National Engineering Laboratory, thc. High Flua Isotope Reactor (HFIR) at the 046. Ridge National Laboratory, and the German Farlsruho FR2 reactor.
Page 20

    . _ - _ . _ _ _ ___._.__-_                                          _- -      _ . _ . __..      _        __   . ~ - _
o     o f
TECHNICAL SPECIFICATIONS          *            ,
Ford Nuclear Reactor Docket 50-2, License R-28 November, 1994 4.0                 SURVEILLANCE REQUIREMENTS 4.1                 Reactivity Limits                                                                            j 4sitwebi;6cf:
{
i Thi's speci fication applies to the survet11ance requirements                                i for reactivity limits.
[
Objective:
To assure that the reactivity limits of Specification 0.1                                    j are not exceeded.
Specifications (1) Shim safety rod reactivity worths shall be measured
: a. Not less than once each calendar years                                          i
: b. Whenever the fuel olements in more than three                                   ,
interior core locations are replaced:                                           l
: c. Whenever the replacement of a fuel element in an                                1 interior core location results in an element                                    ,
fuel mass change of more than 10% in that                                       !
locations                                                                       i i
: d. Whenever the addition of more than three                                        f standard fuel elements to an outer face of the                                  '
core is made to achieve the desired excess                                      .
reactivity f or- the operation of the reactor.                                  I (0) Shim safety rods shall be visually inspected and put through a jig to check for swelling at least annually.
(7) The reactivity worth of those experiments whose safety                                  i l                                   review indicates a need f or such a deterinination shall                                !
be measured prior to the enperiment*s initial use. That                                 !
worth shall be verified if core configuration changes                                   !
l                                   occur which could reasonably be enpocted to cause                                       [
l                                   increases in expertinent reactivity worth whereby thw                                   l experiment worth could onceed the values specified in                                   l Specification 3.1.                                                                      i Dases i
(                              Specification 4.1.(1) will assure that shim-safety rod                                       ;
I           reactivity worths are not degraded or changed by core                                                           !
l           arrangements.                                                                                                   1
                                                                                                                          *I i
i Page 20                 l

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-20 November. 1984 Shim safety rod inspections ar e the single, largest source of radiation e>:posure to f acility personnel .                   Futhermore. frequent inspections of sham safety rods fer swelling over the last ten years have produced no evidence of swelling or cracking.                         In order n <. m t . : : 7 p;r;cr. ci . ;;i ;.* ; ;,:, ; y: : .. e : r.1 p;..d ;,n t,.g:.t;:n frequency that will detect early evidence of swelling and cracking. an annual inspection interval was selected for specification 4.1.(2).
The spect fled surveillance relating to the reactivi ty worth of eaperiments will assure that the reactor is not operated for e,ttended periods before determining the reactivity worth of e:t p er i men t s . This specification also provides assurance that e::periment reactivi ty worths do not increase beyond the established limits due to core configuration changes.
4.2        Reactor Safety System Applicability:
This specification applies to the survetllance of the reacter safety system.
Objective To assure that the reactor safety system is operable su required by Specification 7.2.
Specifications (1) A channel test of the neutron flua level safety channels, perted safety channel. log count rate channels. and power-flcw coincidence scrams shall be performed
: a. Prior to each re&ctor startup following a period when the reactor was secured
: b. After a channel has been repaired or deenergi:od.
(2) A channel calibration of the safety channels 16stod in Table 7.1, which can be calibrated, shall be performed at least once each calendar year.
(0) A channot check of the neutron f l uit level safety channeta during reactor operation comparing the channel
;                      outputs with a heat balance, shall be performed short1s after reaching operating power level anJ wee 6 Iv
!                      thereaftne tf the reactor is to be operated at a thermal i                      power lovel above 500 6w.
l l
Page 24

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 (4) The operation of the radiation monitoring system reqiired in Specification 2.0 shall be verified prior to every reactor startup for which safety system channel tests are required as in 4.2.(1).                                    If the system has t r:n e .:;; ;.: i r s d , er : r. : I t i :. - s r. d r. ; '. ; ;,1, *      .  ' .:ct;cn will be performed prior to use.
(5) The radiation monitor system required in Specification
                 ".2 shall          be calibrated not less than once evurf si:t months.
(6) Sham safety rod release-drop time shall be moesured not lens than once each calendar year.
(7) Shim safety rod release-drop time sha*1 be measured whenever the shim safety rod's core location is changed or whenover maintenance is performed which could effect the rod's drop time.
Bases:
Frostartup tests of the safety system channels .nssure their operability.      Annual calibration detects any long term drift that 1+a not detected by normal intercompartson of channels.                                     The channel check of the neutron flun level channels assures that the detectors are properly adjusted to accurately monitor the parameter they are sneasuring.
Radiation monitcrs are checled for proper operation in Spocification 4.0.(4). Calibration and notpoint verification invol.e use of a calibration source and significant personnel radiation caposure.              It tu felt that overall calibration of radiation moni tore, which have displ ayed ettcollent stability over inan y years of operation, every s t .: months is adequate to veri f y the setpoint unless instrument repairs have been made.
The measured releaue-drop timos of the shtm safety rods have bwen consistent sinco the installation of the boron / stainless                                        i steel shim safety rods in 1760.                         Annual check of these parameters is considered adequate to detect any detortoratton which could change the release-drop time.                       01nding or rubbing caused by rod misalignment could result from maintenanece therefore, release drop timun will be chect ud af ter such maintenance.
4.0    FNR Confinement Building Applicability l
This specificatten applies to the surveillance of the facility openings and damporn.
aN

TECHNICAL 3PECIFICATIONS Ford Nuclear Reettor Docket 50-2. License R-28 November. 1984 Objective:
To assure that the condition of the closure devices for the building openings are in satisfactory condition to assure their W .1 t                          6-   p         M . d e w .s t e . r.4 : w w & ;4 f. n at er r w redtcacttvit,<ieleased into the bu11 dang.
Specifications (1) The operation of the dampers described in Spectftcation 0.3.(1) shall be tested for operability whenever ccmpleto chec6out of the reactor control system is required prior to startup.              This operability test will be a portion of the startup checkout list for the facility.
(0) The condition of the following gas 6ett shall be inspected at intervals not to exceed si n months, and the geS6 eta shall be replaced whenever anv evidence cf detertoretton is foundt
: 4. DutidirQ ventilation system inta6e end exheuut damperst
: b. Forsonnel access docrat
: c. Equipment actevs decent
: d. Celing tcwer ecceso dcor.
Dauoat The greestart chect wt the mu n damper f unction pr ovidos asturance that the eut amatic f unction provided b / these dampers w L il b's a c tua ted when conf a nwmont isolation is required.                                The somtennual inspection of gau6et materials, utnce these materials erw not in a damaging atmothphere, will provide assurance that the gaulots will perform thute function of Ilmating tealage through these openings in the event of a release of ateborne activity into the tau t iding.
4.4                         Primary Coolant Gystem Applicabilityt Ihte spoetfication ADDlten to the survenllancu of the primar / coolant systum.
Oti j wt t i v e To assure high quelltv pool water and to detect the releasa of finuton prot 1ucts frca fuel elements.
F4ge 26

TECHNICAL SPECIFICATIONS Ford Nuclear Peactor Dociet 50-2, License R-28 November, 1984 Specifications (1) The pH of the primary coolant shall be measured weekly.
::: '' e , : n i r t.
                     .          .   . . i t . Li L ?. ,,r..... .  ; % i .. . c 9r ,1 i h neesured weekly.
(0) The radioactivity of the primary coolant shall be analyzed b1 weekly.
(4) A record of pool makeup water shall be maintained to discover significant lealage of primary coolant from the facility.
Dates:
Regular surveillance of pool water quality and radioactivity providos assurance that pH and conductivity changes that could accelerate the corrosion cf the primary coolant system would be detected before significant corrosive damage would occur, and that the presence of leating fuel elements in the reactor is detected.
Routine inspection of makeup water needs over a period of timo providos early warning of small poc! water leaks.
4.5   Heavy Water Reflector Tank Applicability:
This specificaticn applies to surveillance requirements regarding the heavy water reflector t ani used in the reactor coro.
Objectives To assure that the t hint t a of Spucification 0.5 are not eaceeded.
9pecifications (1) The shutdown margin required by Specification 0.5.(1) will be vertited whenever heavy water transfers as described in that specification eru to be made.
(0) The trittum content of the heavy water reflector tan 6 shall be measured not less than orco ovary three months provided the reacter has oporated during that period.
Daneel Actual verificatten of the shutdewn mergin required in 7.5.(1) will assure the reactor stava suberttical under all                                 a possible circumstances during heavy water transfers.
PtQo    ?

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor l       Docket 50-2, License R-OS I
November, 1984 Reactor experience during the last twenty years with the tritium production rate in the tank supports the conclusion that l       quarterly tritium analyses are sufficient to prevent violation of l
Specification 0.5.(2).
l l       4.6    Airborne Effluents i
Applicability:
!              This specification applies to the surveillance of the I
monitoring equipment used to measure airborne radioactivity.
Objectives t
l              The objective is to assure that accurate assessment of airborne effluents can be made.
Specifications (1) The building exhaust air radiation monitor shall be calibrated not less than once every sin months.
(2) The particulate air monitors shall be calibrated not less than once every six months.
(~) The gaseous activity monitors shall be calibrated for A** not less than once every six months.
(4) The operation of all airborne activity monitors shall be checked daily encept when the reactor staff is not present in the facility.
Bases:
Enperience with the electronic reliability and calibration stability of the units used the FNR demonstrates that the above periods ar e reasonable surveillance f requenct es.
i 4.7   Li quid Ef fluents i
t              Applicability:
This specification applies to the surveillance of the monitoring equipment used to measure the activity in liquid effluents.
Objective The objectise is to assure that accurate assessment cf liquid effluents can be made.
Page 20

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l                                                             TECHNICAL SPECIFICATIONS l                                                                 Ford Nuclear Reactor I                                                            Docket 50-0. License R-OS November. 1984 l           Specifications (1) The monitoring equipment used to measure the radioactive l                concentrations in the waste retention tank contents l                : S s '. ! t c. : e '. 1 ., t : J .at 141. t%+i ..c  s .wr , u. . ..svr. U i m .
(2) The contents of every tank released shall be sampled and evaluated prior to its release.
Bases:
E,cperience with the counting equipment used in measuring the radioactivity in the waste retention tanks suggests that the above period is a suitable calibration frequency.
4.8   Fission Density Limits Applicability:
This specification applies to the surveillence requirements for fission density limits.
Objective:
To assure that the fission density limits of Specification 0.9 are nct evceeded.
Specifications (1) The fiasion density of all fuel elements which have uranium 005 burnup shall be calculated at least quarterly.
Bases:
09 termination of fission densities en a quarterly basis will ensure that the fission density limits of Specification 0.9 are not onceeded. Fuel element swelling will be kept well below levels which could result in clad rupture and release of radioactive fission products.
Fago 29

TECHNICAL SFECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-09 November. 1984 5.0    DESIGN FEATURES 5.1    Site Description
           % c e .- r : g :',2:. % .t;r ' :- * ~ ' ..
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Campus of the Universit/ of Michigan at Ann Arbor, Michigan.                  The North Campus area is under the administrative control of the Regents of the University of Michigan.
The North Campus is a tract of near1/ 900 acres, about l't miles northeast of the center of Ann Arber.            It is bounded on the north by Plymouth Road and on the south by Glacier Way. Open land and the Arborerest Cemetery lie to the east. To the west are University athletic fields, municipal parts and a wooded ridge.
The Huron Pi ver flows through land bordering the area on the west and south and some marshland lies adjacent to the river on the nouth.
The reactor building is located near the conter of the North Campus area.      Development of the North Campus area by the University has been done using the following guido11 nest (1) Only laboratory and research buildings will be constructed within 50 feet of the reactor.
           'O) No hcusing or other buildings containing housing factittlos will be erected withan 1500 feet of the reactor.
The Untversity of Mich1gan controls all the land within 1500 feet of the reactor site. with the escootten of a small portton of the htghway rtght of wav alor a Gl acier Way on tho southeast and the Arborcrest Cometery located GQQ feet to the east of the site.
The reactcr site consists of all the land 500 fcet to the east. 1000 feet to the west and ncrth and 1200 foot to the south.
The boundary of this area consists of roadways around the sito whose traffic flew can be controlled shculd such control be desirable.
The reacter restricted area consists of the reactor building and the contiguous Phoen t >t Memortal Laboratory (F ML) .          The coactor building is the operations bounderv and tho omorgenc / pl anning
:eno.
5.2    Reactor Fuel The fuel assemblies shall be of the MTR t<pe. conutsting of plates centoining uranium aluminide 'UA1.) or urantum calde (UyOn) fuel enriched to less than 00% in the isotope U205 clad with alumtnum.
Pago 00

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-0. License R-28 November, 1984 The authori:ed fuel assembly designs aret Man 1 mum               Max 1 num Number           Plate Loading          Assembly Loading cr    ~.etes            sa *?5-
_                  u u;J5 18               9.2810%                  16710%
9               9.2320%                   S412%
5.0   Reactor Building The reactor building is a windowless. four story, reinforced concrete building with 12 inch walls structurally integral with the footings and foundation mats. The butiding ts approntmately 69 feet wide .1 68 feet long n 70 feet high with approntmately 44 feet enposud above grade.      The building has the follcwing general features:
(1) The reactor is housed in a closed room destqned to restrict 1catage.
(2) The reacter room te equipped with a ventilation system designed to exhaust air or other gases present in the butiding atmosphere into an exhaust stact which euhausts a mintmum of 54 feet above ground level.                     '
(0) The ventilation svttem provides ventalation for certain storage and superimental fac111ttet and e< haunts these a minimum of 54 feet above ground level.
(4) The cpunings into the reactor building are an equipment        [
eccwes door, three personnel doors. an equipment access hatch, air intake and enhaust ducts. rocm 0100 fume hood enhaust duct, beamport ventilation duct. a sealed north well dcor. a door betwoon the hot cave operating face and the beampcet floor, and a pneumatic tube 1/ stem for sample transfer betwoon the FNR and coveral laboratornou 1n the Phoenta Memorial Laboratorv.
0.4   Fuel Otorage (1) Irradtated fuel elements and fuuled devices shall be stored in an arra/ which will permit sufflctent natural l                  ccnvuction cooling by water or air such that the fuel        L i                  element ce fuelod device tempurature will not eacoed 100 C.
l I

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(
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Doctet 50-2. License R-28 j     November. 1984
!           (2) All reactor fuel elements and f ueled devices shall be j                stored in a geometric array which assures l                subcriticality. The array spacancs will be based on the j                experimental results reported in CANL-CF-50-9-40 for i                t'--:qc r e .e t r n-i me t : ; rf: mcM i: 6. P CFF :s , d 2TF fuel elements.
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:                                                             TECHNICC*. SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 November, 1994 6.0 ADMINISTRATIVE CONTROLS 6.1 Drganization
               ~'s   ;   ;.c.;st.@,4       . t c M t .. . u ci Uw 'J h . . sn s . ; , ., e MachtQan relattnQ to the Ford Nuclear Reactor (FNR) shall be as shown in FtQure 6.1.
(0) The FNR Reacter Manager shall be responsible fcr the safe operation of the FNR. He shall be responsible for assuring that all operations are conducted in a safe manner and within the limits prescribed by the facility license, including the technical specifications and operattnQ proceduros.             During periods of his absence.
his responsibilities are delegated to the Assistant Reactor Manager.
( 7d In all matters pertatning to thw oporetten of the plant and those technical spectitcations. the FNP Geacter Manager shall report to and be directly responsible to the Director. Michi gan Morner t al-Fhoon t n Froject.
(4) Cua l t i t e.a t i on s . FNR Reactor ManaQurt            Mtntmum qualtftcettons for the FiP Reactor ManaQor shall be a b.nchelor's doQree and at lea st f our year s of reactor operating v1pertence in increast nQl / retoentt ble l              pntttons. Years spont tn Qraduate study m a < t, e substituted for operating eapertonce on a one for cne basis up to a matimum of two years. Within sit monthm after botnQ anstQned this position. the Rwactse Manager shall 4pply fer en NFC senter operator Incente if h4 dovu not already hold one.
(5) *. heal th physteint who is organt:stten411y t r.d ep ende n t cf the FhR operations group shall be responsible f or radiolcQtcal safety at the fact 16ty.
(6) A licensed operator or Incensed sentor operator pursuant to 10LPROC shall be preeent in thw control rcom whenever the reactor is in operatich as defined in these spec t f 6 c ations. The ent ntinum cpor et tnQ crew will t w composed Of two indtviduals. at 1444% Gnw of which will be go licensed.
(7) A licensed senior cocrator whall be present or readily
* available en call at an/ time the reectdr le in ebwration.
!         <di  The Idonttta of and mw*.hcd for captulv :ontac'.shQ the Itcensed tentor operator en dut< shall to 6nown to '.he reactor Gppertor at eny time that thw reacter is .n                                                                     .
OD#ratico.
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l

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-23 November. 1984 (9) Licensed senior operators or operators are not required to be present in the facility when the reactor is secured.
                  .   '; Etrd ac" tL 1 ;t t ,a '.m.1.t, sh;1' participate in an approved operator requalification program as a condition of their continued assignment of operator duties.
6.2   Review and Audit (1) A Gafety Review Committee (SRC) shall review re. actor operations and advise the Director. Michigan Memor t a l -F hoen i x Project. in matters relating to the health and safety of the public and the safety of factitty operations.
(2) The Gefety Restew Committee shall have at 1 cast eight members of whom no mcre than the mincrity shall be from the line organisation shown in Figure 6.1 or ediningstratively report to anyone in that line cegant:Atton below the Vice President for Research.
The Committen shall be made up of University staff and faculty whc shall collectively provide enpertence in reacter engineering, instruinentaticn and control eestem4 radtological safety. and mechantent and electricel uvstemu.
           '')   The Committee shall .tiset at least samtennus11f.
(4) The quorum shall centist of not less then a majortt's of the fv11 coinmi tte and shall include the chateman or his designated alternate.
(5) F1ve votes are required to approve these changes, o"p or t inen t s , and tests which require spectftc 3RC approval. Votes may be cast at SRC meetings or via individual polling of members.
(4) Minutes of each Committee meetlng shall be distributed to the Director. Michigan Memortal-Phoenta Project, all Defety Review Commi ttee meinbors. and such other s as the chairman may designate.
(7) The Gafety Peview Committee shalls
: a. Review and approve proposed e>tperiments and tests uti112 t ng thts r ##c ter factitty which are signtficant1< different from tests and etperiments previcuelv perfccmod at the FNR.              In Page *4

o .
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor
,                                                     Docket 50-2, License R-28 l
November, 1984 l
Figure 6.1       Organization Chart for the Ford Nuclear Reactor Regents University of Michigan President Vice President Research Director                                            Director Michigan Memorial-Phoenix Projeci                   Radiation Control Service I
I I
L__,        Safety Review Committee Reactor Manager     .---         -----.            Health Physicist Assistant                                                                  '
Reactor Manager
                               ~~
supervisse Reactor Operations safety and l                                                                      Licensing runction Licensed Operators                                                              !
O Page 35

. r TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 the event of a disagreement over approval of an experiment between the Committes and the Reactor Manager, the matter shall be referred to the Director. Michigan Memorial-Phoenix Project for s waciutivi.
: b. Review reportable occurrences.
: c. Review and approve proposed standard operating procedures and proposed changes to standard operating procedures. This requirement pertains to those procedures prepareo pursuant to Section 6.4 of these specifications.
: d. Review and approve proposed changes to the technical specifications and proposed amendments to the facility license and review proposed changes to the facility made pursuant to 10CFR50.59(c).
: e. Review the audit report provided by the consultant for reactor operations.
(S) A consultant will be retained by the University of Michigan to perform an annual audit of reactor operations and the safety of facility operations.                               The consultant shall be selected by the Director, Michigan Memorial-Phoenix Project and shall be an individual presently or recently engaged in the management of a research or test reactor of comparable power level and type.       He shall provide a report on the conclusions drawn from that audit to the Director, Michigan Memorial-Phoenin Project. The Director shall provide the members of the Safety Review Committee with copics of this report.
(9) The consultant for operations shalls
: a. Audit reactor operations and reactor operational records for compitance with internal rulen, procedures, and regulations and with license provisions including technical specificationst
: b. Audit existing standard operating procedures for adequacy and to assure that they achieve their intended purpose in light of any changes since their implementatient
: c. Audit plant equipment performance with particular attention to operating anomalies. reportable occurrences, and the steps taken to identify and correct their causes.
Page 06

I TECHNICAL SPECIFICATIONS Ford Nuclear Reactor
 ;                                                                                      Docket 50-2. License R-28 November. 1984 6.0   Action to Be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defined in these technical specifications, the following action shall be taken:
 ;                     (1) The FNR Reactor Manager shall be notified of the'
 ;                          occurance. Corrective action shall be taken to correct the abnormal conditions and to prevent its recurrence.
(2) A report of such occurrence shall be made to the Safety Review Committeeg the Director. Michigan                                                 I Memori al-Phoeni:: Project; and the Nuclear Regulatory Commission in accordance with Section 6.6.(2).a. The report shall include an analysis of the causes of the occurrence, the effectiveness of corrective actions taken, and recommended of measures to prevent or reduce the probability of consequences of recurrence.
6.4   Operating Procedures Written procedures. including applicable check lists, reviewed and approved by the Safety Review Committee shall be in effect and followed for the following operations:
(1) Startup, operation and shutdown of the reactors (2) Installation and remosal of fuel elements, control rods, experiments and experimental facilitiest (3) Actions to be taken to correct specific and foreseen potential malfunctions of systems or components.
including responses to alarms, suspected primary coolant system leaks, and abnormal reactivity changes (4) Emergency conditions involving potential or actual release of radioactivity. including provisions for evacuation, reentry. recovery, and medical support; (5) Maintenanco procedures which could have an effect on reactor safetyt (6) Periodic sur veillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors; (7) Facility security plang (8) Radiation protection procedures.
Page 37

l l               TECHNICAL SPECIFICATIONS j               Ford Nuclear Reactor l               Docket 50-2, License R-28 l               November, 1984 Substantive changes                              to the above procedures shall be made only with the approval of                              the Safety Review Committee.          Temporary changes to the procedures                               that do not change their original intent may be.made with approval                               of the FNR Reactor Manager or the A;I.starit Cemata                            M,no3es. All tea.p a, er f chen w ei La the procedures shall be documented and subsequently reviewed by the Safety Review Committee.
6.5    Operating Records (1) The following records and logs shall be prepared and retained by the licensee for at least five years:
: a. Normal facility operation and maintenance;
: b. Reportable Occurrences;
: c. Tests, checks, and measurements documenting compliance with surveillance requirements;
: d. Records of experiments performed; I
: e. Records of radioactive shipments; 1
: f. Operator requalification program records (the             !
five year period will commence after termination of the assignment of the operator to operative duti es) ;                                                :
: g. Facility radiation and contamination surveys.
(2) The following records and logs shall be prepared and retained by the licensee for the life of the facility:
L                                                       a. Gaseous and liquid waste released to the environs;
: b. Offsite environmental monitoring surveys;
: c. Radiation exposures for all FNR personnel;
: d. Fuel inventories and transfers;
: e. Updated, corrected, and as built facility drawings;
: f. Minutes of Safety Review Committee meetings.
Fage 38

TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 6.6   Reporting Requirements The following information shall be submitted to the USNRC in addition to the reports required by Title 10, Code of Federal nmgv!stione,   a'' "-itten r=;;rts s5311 bc add; c :ed t      th e U. 2.
Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D. C. 20555 with a copy to the Administrator, Region           j III.                                                                       l (1) Annual Operating Reports A report coverirg the previous year shall be submitted by March 31 of each year. It shall include the following information.
: a. Operations Summary A summary of operating experience having safety significance occurring during the reporting period.
: 1) Changes in facility design.
: 2) Perf ormance characteri stics   e.g., equipment and fuel performance).
: 3) Changes in operating procedures which relate to the safety of facility operations.
: 4) Results of surveillance tests and inspections required by these technical specifications.
: 5) A brief summary of those changes, tests, and enperiments which required authorization from the commission pursuant to 10CFR50.59(a).
: 6) Changes in the plant operating staff serving in the following positions:
(a) FNR Reactor Manager; (b) Health Physicist; (c) Safety Review Committee members.
I
: b. Power Generation A monthly tabulation of the thermal output of the facility during the reporting period.
Page 39

o r TECHNICAL SPECIFICATIONS' Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984
: c. Shutdowns A listing of unscheduled shutdowns which have occurred during the reporting period, t abul ated eccording to cause. and e urist oiscussion or the actions taken to prevent recurrence.
: d. Maintenance A discussion of corrective maintenance, excluding preventive maintenance, performed during the reporting period on safety related systems and components.
: e. Changes, Tests, and Experiments A brief description and a summary of the safety     l evaluation for those changes, tests, and            I experiments which were carried out without prior commission' approval, pursuant to the requirements of 10CFR50.59(a).
: f. Radioactive Effluent Releases A statement of the quantities of radioactive effluents released from the plant.
: 1) Gaseous Effluents                                3 (a)  Gross Radioactivity Releases (1) Tctal gross radioactivity in curies, primarily noble and activation gases.
(2) Average concentration of gasesous effluents released during normal steady state operation averaged over the period of reactor operation.
(3) Maximum instantaneous concentration of noble gas radionuclides released during special operations, tests, or experiments.
(4) Percent of technical specification limit.
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!                                                                                          TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-29 t
November, 1984 l
l                                      (b)        Iodine Releases (Required if iodine is identified in primary coolant samples, or if fueled
                                                  + p er . .r..: n + .3 u s cc..duc ted at tha facility.)
(1) Total iodine radioactivity in curies by nuclide released, based on representative isotopic analyses performed.
(2) Percent of MPC.
(c)        Particulate Releases (1) Total gross beta and gamma radioactivity released in curies excluding background radioactivity.
l (2) Gross alpha radioactivity released in curies excluding background radioactivity.                         (Required if the operational cr experimental program could result in the release of alpha emitters.)
(3) Total gross radioactivity in curies of nuclides with half lives greater than eight days.
(4) Percent of MPC for particulate radioactivity with half lives greater than eight days.
: 2) Liquid Effluents (a) Total gross beta and gamma radioactivity released in curies excluding tritium and average concentration released to the unrestricted area or sanitary sewer averaged over period of release.
(b) The maximum concentration of beta and gamma radioactivity released to the unrestricted area.
Page 41

o -
9 TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1084 (c) Total alpha radioactivity in curies released and average concentration released to the unrestricted area averaged over the period of release.
(Requirec if the operational or experimental program could result in the release of alpha emitters.)
(d) Total volume in ml of liquid waste released.
(e) Total volume in ml of water used to dilute the liquid waste during the period of release prior to release from the building to the sanitary sewer system.
(f) Total radioactivity in curies, and concentration averaged over the period of release by nuclide released, based on representative isotopic analyses performed for any release from a waste storage tank whose contents have a concentration in excess of 9x10-*
microcuries/cc.
(g) Percent of technical specification limit for total radioactivity from the site.
: g. Environmental Monitoring             .
For each medium sampled:
: 1) Number of sampling locations and a description of their location relative to the reactor.
: 2) Total number of samples.
: 3) Number of locations at which levels are found to be significantly higher than the remaining locations.
: 4) Highes*., lowest, and the annual average concen -ations or levels of radiation f or the sampling point with the highest average and the location of that point with respect to the site.
Page 42

. v TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Decket 50-2, License R-28 November, 1984
: 5) The maximum cumulative radiation dose which could have been received by an individual continuously present in an unrestricted area during reactor operation from:
(a) Direct radiation and gaseous effluent; (b) Liquid effluent.
: 6) If levels of radioactive materials in
* environmental media, as determined by an environmental monitoring program, indicate the likelihood of public intakes in excess of 1% of those that could result from continuous exposure to the concentration values listed in Appendix B, Table II, 10CFR20, estimates of the likely resultant exposure to individuals and to population groups and assumptionis upon which estimates are based.                    -
: 7) If significant variations o'f offsite environmental concentrations with time are observed, correlation of these results with effluent release shall be provided.
: h. Occupational Personnel Radiation Exposure A summary of annual radiation exposures greater than 500 mrem (50 mrem for persons under 18 years of age) received during the reporting period by facility personnel including faculty, students, or experimenters.
(2) Non-Rcutine Reports
: a. Reportable Occurrence Reports Notification shall be made within 24 hours by telephone and telegraph to the Director of the appropriate Regional Inspection and Enforcement Office followed by a written report within 14 days to the U. S. Nuclear Regulatory Commission.
Attn: Document Control Desk, Washington,    D. C.
20555, with a copy to the Director of the Regional Inspection and Enforcement Office in the event of a reportable occurrence, as defined in Section 1.0. Telegraph notification may be sent on the next working day in the event of a reportable occurrence during a weekend or holiday period. The written report of a reportable occurrence, and, to the extent possible, the preliminary telephone and Page 43

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TECHNICAL 5FECIFICATIONS 1               Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984 telegraph notification shall:
: 1) Describe, analy:e, and evaluate safety implications;
: 2) Outline the measures taken to assure that the cause of the condition is determined;
: 3) Indicate the corrective action including any changes made to the procedures and to the L
quality assurance program taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems;
 ;.                                                4) Evaluate the safety implications of the incident in light of the cumulative
 ,                                                      experience obtained from the record of
,                                                       previous failure and malfunctions of similar systems and components.
i
: b. Unusual Events
}                                                  A written report shall be forwarded within 30
 ;                                                 days to the U. 3. Nuclear Regulatory Commission, j '
Attn: Document Control Desk, Washington D. C.
20555, with a copy to the Director of the                                                                     ;
Pegional Inspection and Enforcement Office in the event of:
i                                                 1) Discovery of any substantial errors in the transient or accident analyses or in the methods used for such analyses, as described in the safety analysis or in the bases for the technical specifications;
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i
: 2) Discovery of any substanti al _ vari ance from performance specifications contained in the technical specifications and safety 2
anaylysis.
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: 3) Discovery of any condition involving a possible single failure which, for a system designed against assumed failures, could result in a loss of the capability of the system to perform its safety function.
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