ML060820102

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Letter to Mr. Steve Ceccio from Patrick Isaac with Enclosure, Subj: Issuance of Amendment No. 48 to Facility Operating License No. R-28 University of Michigan Ford Nuclear Reactor
ML060820102
Person / Time
Site: University of Michigan
Issue date: 05/08/2006
From: Isaac P
NRC/NRR/ADRA/DPR/PRTB
To: Ceccio S
University of Michigan
Isaac P, NRR/ADRA/DPR/PRT, 301-415-1019
References
TAC MC3707
Download: ML060820102 (42)
v • d • e


Text

May 8, 2006 Mr. Steven L. Ceccio, Director Phoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109

SUBJECT:

ISSUANCE OF AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. R-28 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR (TAC NO. MC3707)

Dear Mr. Ceccio:

In response to your submittal of September 08, 2005, February 28, 2006, and April 6, 2006, the Commission has issued the enclosed Amendment No. 48 to Facility Operating License No. R-28 for the University of Michigan Ford Nuclear Reactor. The enclosed amendment consists of changes to the facility Technical Specifications to eliminate those specifications which are not applicable to and relax those specifications no longer appropriate for the facility not licensed to possess reactor fuel. These changes were developed in preparation for decommissioning your reactor.

A copy of the related safety evaluation supporting Amendment No. 48 is enclosed.

Sincerely,

/RA/

Patrick Isaac, Project Manager Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-02

Enclosures:

1. Amendment No. 48
2. Safety Evaluation cc w/enclosures: See next page

University of Michigan Docket No. 50-02 cc:

Special Assistant to the Governor Office of the Governor Room 1 - State Capitol Lansing, MI 48909 Mr. C.W. Becker Phoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit, 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

May 8, 2006 Mr. Steven L. Ceccio, Director Phoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109

SUBJECT:

ISSUANCE OF AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. R-28 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR (TAC NO. MC3707)

Dear Mr. Ceccio:

In response to your submittal of September 08, 2005, February 28, 2006, and April 6, 2006, the Commission has issued the enclosed Amendment No. 48 to Facility Operating License No. R-28 for the University of Michigan Ford Nuclear Reactor. The enclosed amendment consists of changes to the facility Technical Specifications to eliminate those specifications which are not applicable to and relax those specifications no longer appropriate for the facility not licensed to possess reactor fuel. These changes were developed in preparation for decommissioning your reactor.

A copy of the related safety evaluation supporting Amendment No. 48 is enclosed.

Sincerely,

/RA/

Patrick Isaac, Project Manager Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-02

Enclosures:

1. Amendment No. 48
2. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION:

PUBLIC PRT r/f JQuichocho PIsaac EHylton OGC ACCESSION NO: ML060820102 OFFICE PRT:PM PRT:PM PRT:LA OGC PRT:BC NAME JQuichocho:tls* PIsaac EHylton SUttal* BThomas:tls*

DATE 4/14/06 4/14/06 4/12/06 4/25/06 5/8/06 OFFICIAL RECORD COPY

UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR DOCKET NO. 50-02 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. R-28

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

A. The application for an amendment to Facility Operating License filed by the University of Michigan (the licensee), dated September 8, 2005, as supplemented on February 28, 2006 and April 6, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of notice for this amendment is not required by 10 CFR 2.106.

2. Accordingly, the license is amended by changes to paragraph 2.C(2) to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Brian Thomas, Branch Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance: May 8, 2006

ENCLOSURE TO LICENSE AMENDMENT NO. 48 FACILITY LICENSE NO. R-28 DOCKET NO. 50-02 Replace Appendix A Technical Specifications in its entirety with the enclosed pages. The pages are identified by amendment number and contain vertical lines indicating the areas of changes.

APPENDIX A TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR FACILITY LICENSE NO. R-28 DOCKET NO. 50-02 As Revised to Facilitate Permanent Reactor Shutdown, Decontamination and Decommissioning Amendment No. 48

FNR Tech. Specs.

TABLE OF CONTENTS PAGE 1.0 DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS . . . . . . . . . . . . . . . . . 7 2.1 Safety Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 2.2 Limiting Safety System Settings (LSSS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.0 LIMITING CONDITIONS FOR OPERATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.1 Reactivity Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.2 Reactor Safety Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.3 FNR Confinement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.4 Pool Water Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 3.5 Radiation Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 3.6 Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.7 Limitations of Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.0 SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.1 Reactivity Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.2 Reactor Safety System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.3 FNR Confinement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.4 Pool Water Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 4.5 Radiation Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 4.6 Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 4.7 Fission Density Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 5.0 DESIGN FEATURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5.1 Site Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5.2 Reactor Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5.3 Reactor Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5.4 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 6.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 6.1 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 6.2 Review and Audit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 6.3 Action to Be Taken in the Event of a Reportable Occurrence . . . . . . . . . . . . . . . . 24 6.4 Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 6.5 Operating Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 6.6 Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Amendment No. 48 FNR Tech. Specs.

1.0 DEFINITIONS Channel Calibration - A channel calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel 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 performance 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 channel to verify that it is operating.

Experiment - An 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 operation, surveillance, or maintenance technique;
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 or 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 categorized 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 for Operation (LCO) - Lowest functional capability or performance levels of equipment required for safe operation of the reactor (10CFR50.36).

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 before a safety limit is exceeded (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.

Amendment No. 48 FNR Tech. Specs.

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 Worth 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 oF) with the effect of xenon poisoning on core reactivity accounted for if greater than or equal to 0.05% )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 standard fuel elements in addition to the four control elements that house the control rods 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.

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 as 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 that an individual can be contacted and is within a reasonable driving time (1/2 hour) from the reactor building.

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; Amendment No. 48 FNR Tech. Specs.
2. Operation in violation of a limiting condition for operation established in the Technical Specifications;
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 intended safety functions;
4. Release of fission products from a failed fuel element;
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 which results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Appendix B, Table 1, Column 3, Derived Air Concentration (DAC) of 10CFR20;
7. An uncontrolled or unanticipated change in reactivity in excess of 0.005 )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 facility.

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 component 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-safety rod is a control rod fabricated from either borated stainless steel or a boron-aluminum alloy 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.

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 experiment. For moveable experiments, the terminal positions are fully removed from the reactor and fully inserted or installed in the normal functioning or intended position.

Amendment No. 48 FNR Tech. Specs.

Time Intervals - The average over any extended period for each surveillance time interval shall be closer to the normal surveillance time than the extended time. Any extension of these intervals shall be occasional and for a valid reason, and shall not affect the average as defined.

Annually - 12 to 15 months.

Biannually - 24 to 30 months.

Biweekly - 14 to 20 days.

Daily - 24 to 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

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.

Amendment No. 48 FNR Tech. Specs.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits Applicability

  • As the Safety Limits were for the protection of the cladding integrity of the reactor fuel during
  • reactor operation, all safety limits have been removed from the Technical Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • 2.2 Limiting Safety System Settings (LSSS)

Applicability

  • As the Limiting Safety System Settings were for the protection of the cladding integrity of the
  • reactor fuel during reactor operation, all limiting safety system settings have been removed from
  • the Technical Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • Amendment No. 48 FNR Tech. Specs.

3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits Applicability:

  • The reactivity limits applied to the reactivity of the reactor core, the reactivity worths of the
  • control rods, and the reactivity of experiments to ensure that the reactor could be controlled and
  • shutdown at all times and to ensure that the safety limits contained in the Technical
  • Specification could not be exceeded. Reactivity limits have been removed from the Technical
  • Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • 3.2 Reactor Safety System Applicability:
  • These specifications applied to the reactor safety system and other safety related
  • instrumentation. The Reactor Safety System requirements have been removed from the
  • Technical Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • The area radiation monitor system has been moved to Limiting Condition for Operation 3.5,
  • Radiation Monitoring.
  • The facility radiation exhaust monitor has been moved to Limiting Condition for Operation 3.3,
  • FNR Confinement.
  • 3.3 FNR Confinement Applicability:
  • This specification applies whenever the quantity of radioactive materials in unsealed form, on
  • foils or plated sources, or sealed in glass contained in the reactor building exceeds 1.5 x 10-2
  • times the quantities in 10CFR30.72, Schedule C - Quantities of Radioactive Materials Requiring
  • Consideration of the Need for an Emergency Plan for Responding to a Release
  • Amendment No. 48 FNR Tech. Specs.

Objective: *

1. To assure that automatic protective action is initiated to limit the release of radioactive
  • effluents from the reactor building when required. *
2. To provide an audible within the reactor building to initiate evacuation when required. *
3. To assure that the FNR reactor building confinement integrity is maintained when required.
  • Specification: *
1. While the quantity of radioactive materials in unsealed form, on foils or plated sources, or
  • sealed in glass contained in the reactor building exceeds 1.5 x 10-2 times the quantities in
  • 10CFR30.72, Schedule C, AND whenever one or more of the following is open: 1) the
  • reactor building supply damper, 2) the reactor building exhaust damper, 3) the beam port
  • exhaust damper to Stack 2, or 4) the room 3103 hood exhaust dampers to Stack 2 THEN:
  • Gamma Radiation Detector *
a. A gamma radiation detector which utilizes a Geiger Mueller tube to measure the
  • radiation level in the building air exhaust plenum shall be operating, *
b. When the radiation detector which utilizes a Geiger Mueller tube to measure the
  • radiation level in the building air exhaust plenum indicates a dose rate equal to or
  • greater than 1 mrem/hr, THEN *
i. The reactor building ventilation supply and exhaust fans shall automatically turn off;
  • close;
  • iii. IF open, THEN the beam port exhaust damper to Stack 2 shall automatically close
  • OR IF the penetration through the reactor building wall is mechanically sealed,
  • THEN no action is required,
  • iv. IF open, THEN the room 3103 hood exhaust damper to Stack 2 shall automatically
  • close OR IF the penetration through the reactor building wall is mechanically sealed,
  • THEN no action is required,
  • AND *
v. An audible alarm is sounded in the reactor building to initiate evacuation.
  • The gamma radiation detector which utilizes a Geiger Mueller tube to measure the radiation
  • level in the building air exhaust plenum may be out of service for one week, BUT during that
  • period, no activities which could lead to the release of radioactivity from the facility may
  • conducted within the reactor building. This restriction does not apply to activities required to
  • restore the monitoring system to service. *
2. While the quantity of radioactive materials in unsealed form, on foils or plated sources, or
  • sealed in glass contained in the reactor building exceeds 1.5 x 10-2 times the quantities in
  • 10CFR30.72, Schedule C, THEN the following conditions shall be administratively
  • controlled:
  • Amendment No. 48 FNR Tech. Specs.
a. Personnel access doors will be closed except as necessary for the passage of personnel and/or equipment;
b. The main equipment access door onto the beam port floor will be opened only long enough to permit the passage of equipment;
c. The personnel door to the cooling tower area will remain closed except to permit the passage of personnel and/or equipment to the cooling tower area;
d. The door located on the beam port floor which connects to the Phoenix Memorial
  • Laboratory hot cave operating area will remain closed except to permit the passage of
  • personnel and/or equipment,
  • AND
e. The access hatch from grade level to the beam port floor AND the personnel exit door located in the north wall of the building will be sealed closed.

Bases:

The potential 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. Conformance to Specifications 3.3.1 and 3.3.2 will assure that the building leak rate will not exceed the leak rate used in the evaluation.

The 1.0 mrem/hr setpoint for the facility exhaust radiation monitor provides a mechanism for isolating the building ventilation system in the event of a significant release of radioactive material into the reactor building. This setpoint, for the detector location involved, represents a gamma emitting nuclide concentration of 10-3 to 10-4 microcuries/cc of building air.

By requiring that the access doors and equipment hatch remain closed, except for brief, attended periods to permit personnel or equipment passage, the integrity of the confinement will be maintained at or above the level assumed in the Hazards Summary Report, and the release of radioactive material will be minimized.

3.4 Pool Water Conditions

  • Applicability:
  • This specification applies to the makeup water added to the reactor pool while the quantity of
  • water in the pool is greater than 900 gallons.
  • Objective:
  • Record of the makeup water needs over a period of time allows for the detection of significant
  • pool water leaks.
  • Specification: *
1. IF the quantity of water contained in the reactor pool is greater than 900 gallons, THEN a
  • record of the makeup water added to the reactor pools shall be maintained.
  • Amendment No. 48 FNR Tech. Specs.

Bases:

Record of the makeup water needs over a period of time allows for the detection of significant

  • pool water leaks.
  • 3.5 Radiation Monitoring
  • Applicability:

This specification applies to the monitoring of effluent releases from the Ford Nuclear Reactor,

  • area radiation levels within the reactor building, and particulate airborne activity within the
  • reactor building.
  • Objective:

To assure that the release of airborne radioactive material from the Ford Nuclear Reactor is maintained below the limits established in 10CFR20 and to ensure that occupational exposures

  • are controlled as established in 10CFR20.
  • Specification:
1. The concentration of radioactive materials in the effluent released from the facility exhaust stacks shall not exceed 400 times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 1, Air Effluent Concentration (EAC), averaged over time periods permitted by 10CFR20.
2. During license activities which could lead to the generation of airborne radioactivity
  • Column 3, Derived Air Concentration (DAC), the following conditions shall be met: *
a. An air particulate monitor shall be operating on or near the pool floor. *
b. An air particulate monitor shall be operating on the first floor.
  • IF an air particulate monitor required by above is found to be not operable or is taken out of
  • service, THEN licensed activities which could lead to the generation of airborne radioactivity
  • Column 3, Derived Air Concentration (DAC), shall be stopped in a safe condition AND shall
  • not resume until the air particulate monitor is restored to operating. *
3. Area Radiation Monitors: *
a. Licensed activity involving radioactive materials that could produce radiation levels in
  • areas accessible to individuals in excess of 100 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters *

(measured from an accessible surface that emits radiation) shall not be performed on

  • the pool floor unless an operating area radiation monitor which measures the general
  • gamma radiation level and provides a local alarm at or below 50 mrem/hr is located on
  • the third floor near the reactor pool.
  • Amendment No. 48 FNR Tech. Specs.

IF a local area radiation monitor required above is found to be not operable or is taken out of

  • service, THEN licensed activity involving radioactive materials that could produce radiation
  • levels in areas accessible to individuals in excess of 100 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters *

(measured from an accessible surface that emits radiation) shall be stopped in a safe

  • condition AND shall not resume until the affected local area radiation monitor is restored to
  • an operating condition.
  • Bases:

The limits established in this specification incorporate a dilution factor of 400 for effluents released through the exhaust stacks. This dilution factor was calculated from actual FNR site meteorological data and represents the lowest dispersion factor determined and the highest frequency of wind in any sector. Because of the use of the most conservative measured values of wind directional frequency and dispersion factors, this dilution factor will assure that concentrations of radioactive material in unrestricted areas around the FNR site will be far below the limits of 10CFR20.

The pool floor area radiation monitor provides local indication of elevated levels of radiation

  • from the irradiated materials in the reactor pool.
  • The requirements of this specification are considered adequate to assure proper monitoring of
  • area radiation and airborne radioactivity levels within the reactor building.
  • 3.6 Liquid Effluents Applicability:

This specification applies to the monitoring of radioactive liquid effluents from the FNR.

Objectives:

The objective is to assure that exposure to the public resulting from the release of liquid effluents will be minimized.

Specification:

1. The concentration of radioactive materials in the effluent released from the facility liquid waste system to the city of Ann Arbor sanitary sewer system shall be readily soluble (or readily dispersible biological material) in water and shall not exceed 315 times the concentrations specified in 10CFR20, Appendix B, Table 3, Releases to Sewers.
2. The amount of liquid discharged shall be limited to the equivalent of 3,000 gallons of liquid at the concentration limit specified in 3.6.1 each day.
3. Liquids from the facility's radioactive liquid waste system shall not be discharged into the storm drain system.

Amendment No. 48 FNR Tech. Specs.

Bases:

All radioactive liquid effluents are collected in a series of three, 3,000 gallon, coated, steel retention tanks, and they are normally recycled to the reactor pool to make up for surface evaporation. However, after sampling, analysis, and dilution, if the concentration of radioactivity is less than the limit of 10CFR20, liquid effluents can be discharged to the sanitary sewer system.

In the past, less than 50 retention tank discharges per year have been required. During 1970, the North Campus water released into the sanitary sewer system averaged 946,000 gallons per day. This provides a daily dilution factor of 315 for a 3,000 gallon waste tank, which assures that there will be no significant exposure to the public from radioactive waste discharged to the sanitary sewer system.

3.7 Limitations of Experiments Applicability:

  • These limits established the administrative constraints for the lowest functional capability or
  • performance level for equipment associated with and operational characteristics of experiments
  • conducted in the Ford Nuclear Reactor. These limits have been removed from the Technical
  • Specifications.
  • Bases:
  • On January 29, 2004 the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • 3.8 Fission Density Limit Applicability:
  • The fission density limit specified the maximum burnup allowed for a fuel element to ensure fuel
  • failures were not experience during the operation of the reactor. This limit has been removed
  • from the Technical Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • Amendment No. 48 FNR Tech. Specs.

4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits Applicability:

  • All surveillance requirements for reactivity limits have been removed from the Technical
  • Specifications
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • 4.2 Reactor Safety System Applicability:
  • This specification applied to the surveillance of the reactor safety system. These surveillance
  • requirements have been removed from the Technical Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • 4.3 FNR Confinement
  • Applicability:
  • These surveillance requirements apply whenever the quantity of radioactive materials in
  • unsealed form, on foils or plated sources, or sealed in glass contained in the reactor building
  • exceeds 1.5 x 10-2 times the quantities in 10CFR30.72, Schedule C - Quantities of Radioactive
  • Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a
  • Release.
  • Objective: *
1. To assure that automatic protective action is initiated to limit the release of radioactive
  • effluents from the reactor building when required. *
2. To assure that the audible alarm within the reactor building is available to initiate evacuation
  • when required. *
3. To assure that the FNR reactor building confinement integrity is maintained when required.
  • Amendment No. 48 FNR Tech. Specs.

Specification: *

1. Gamma Radiation Detector *
a. The gamma radiation detector which utilizes a Geiger Mueller tube to measure the
  • radiation level in the building air exhaust plenum shall be calibrated annually, AND *
b. The ability of the radiation detector which utilizes a Geiger Mueller tube to measure the
  • radiation level in the building air exhaust plenum to initiate the automatic protective
  • action required by 3.3.1.a.ii shall be tested quarterly. *
2. The condition of the following gaskets shall be inspected semiannually, and the gaskets shall be replaced whenever any evidence of deterioration is found:
a. Building ventilation system intake and exhaust dampers;
b. Personnel access doors;
c. Equipment access doors;
d. Cooling tower access door.

Bases:

The gamma radiation detector which utilizes a Geiger Mueller tube to measure the radiation

  • level in the building air exhaust plenum has been calibrated annually for most of the operating
  • history of the FNR. This instrument has displayed excellent reliability over many years of
  • operation. The semiannual inspection of the gasket materials has been occurring for most of
  • the operating history of the FNR. These materials are not in a damaging environment and
  • semiannual inspection has been found sufficient to assure that the gasket will perform their
  • function of limiting leakage through these openings in the event of a release of airborne
  • radioactivity within the reactor building.
  • 4.4 Pool Water Conditions
  • Applicability:
  • This specification applies to the makeup water added to the reactor pool while the quantity of
  • water in the reactor pool is greater than 900 gallons
  • Objective:
  • Review of the makeup water needs over a period of time allows for the detection of significant
  • pool water leaks.
  • Specification: *
1. IF the quantity of water contained in the reactor pool is greater than 900 gallons, THEN the
  • quantity of makeup water added to the reactor pool shall be reviewed quarterly.
  • Bases:
  • A small portion of the pool structure is in direct contact with the soil under the reactor building.
  • Routine inspection of the makeup water records over a period of time provides early warning of
  • significant pool leaks.
  • Amendment No. 48 FNR Tech. Specs.

4.5 Radiation Monitoring

  • Applicability:
  • This specification applies to the surveillance of the monitoring equipment used to measure area
  • gamma levels and airborne radioactivity.
  • Objective:
  • The objective is to assure that accurate assessment of area gamma levels and airborne
  • radioactivity is available during the conduct of licensed activities.
  • Specification: *
1. Air Particulate Monitors *
a. The air particulate monitors shall be calibrated semiannually. *
b. The operation of the air particulate monitors shall be checked daily when the reactor
  • staff is present in the facility. *
c. An air particulate monitor shall be calibrated upon replacement or following maintenance
  • which could affect calibration. *
2. Area Radiation Monitors: *
a. The area radiation monitors shall be calibrated semiannually. *
b. The area radiation monitors shall be channel checked monthly. *
c. An area radiation monitor shall be calibrated and a channel check shall be performed
  • upon replacement or following maintenance which could affect the calibration.
  • These surveillance requirements shall be met during the conditions specified in the Limiting
  • Condition for Operation. Surveillances do not have to be performed on inoperable equipment
  • Bases:
  • The Ford Nuclear has upgraded to the Eberline AMS-4 for the air particulate monitors. The
  • AMS-4 continuously monitors all critical operating parameters of the unit, such as air flow,
  • detector response, etc., and generates a local alarm whenever one of the monitored parameter
  • falls outside the operator established range. The AMS-4 has several years of demonstrated
  • reliable performance in the power reactor community. The surveillance intervals provided for
  • the air particulate monitors are sufficient to ensure the operability of the air particulate monitors
  • between surveillance intervals.
  • Semiannual calibration of radiation monitors, which have displayed excellent stability over many
  • years of operation, is adequate to verify the set point unless instrument repairs have been
  • made.
  • Amendment No. 48 FNR Tech. Specs.

4.6 Liquid Effluents Applicability:

This specification applies to the surveillance of the monitoring equipment used to measure the activity in liquid effluents.

Objective:

The objective is to assure that accurate assessment of liquid effluents can be made.

Specification:

1. The monitoring equipment used to measure the radioactive concentrations in the waste retention tank contents shall be calibrated semiannually when releases are made to the sanitary sewer.
2. The contents of each tank released shall be sampled and evaluated prior to its release.

Bases:

Experience with the counting equipment used in measuring the radioactivity in the waste retention tanks suggests that the above period is a suitable calibration frequency. Waste water is normally recycled to the reactor pool. Consequently, discharges are not normally made to the sewer and calibrations are not normally needed.

4.7 Fission Density Limits Applicability:

  • The surveillance requirement for the fission density limit has been removed from the Technical
  • Specifications.
  • Bases:
  • On January 29, 2004, the license for the Ford Nuclear Reactor was modified with the following
  • condition: Maximum Power Level: The licensee shall not operate the reactor nor place fuel
  • elements in the reactor grid. and the condition allowing for the possession of reactor fuel under
  • Amendment No. 48 FNR Tech. Specs.

5.0 DESIGN FEATURES 5.1 Site Description The Ford Nuclear Reactor (FNR) is located on the North Campus of the University 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 nearly 900 acres, about 1-1/2 miles northeast of the center of Ann Arbor. It is bounded on the north by Plymouth Road and on the south by Glazier Way. A VA hospital and some apartments are south of Glazier Way. Apartments are located north of Plymouth Road. Open land and the Arborcrest Cemetery lie to the east. To the west are University athletic fields, municipal parks and a wooded ridge. The Huron River flows through land bordering the area on the west and south and some marsh land lies adjacent to the river on the south.

The reactor building is located near the center of the North Campus area. No housing or buildings containing housing facilities are erected within 1500 feet of the reactor.

The University of Michigan controls all the land within 1500 feet of the reactor site, with the exception of a small portion of the highway right of way along Glazier Way on the southeast and the Arborcrest Cemetery located 800 feet to the east of the site.

The reactor site consists of all the land 500 feet to the east, 1000 feet to the west and north and 1200 feet to the south. The boundary of this area consists of roadways around the site whose traffic flow can be controlled should such control be desirable.

The reactor restricted area consists of the reactor building and the contiguous Phoenix Memorial Laboratory (PML). The reactor building is the operations boundary and the emergency planning zone.

5.2 Reactor Fuel The license for the Ford Nuclear Reactor does not allow for the possession of reactor fuel.

  • 5.3 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 building is approximately 69 feet wide x 68 feet long x 70 feet high with approximately 44 feet exposed above grade. The building has the following general features:
1. The reactor is housed in a closed room designed to restrict leakage.
2. The reactor room is equipped with a ventilation system designed to exhaust air or other gases present in the building atmosphere into an exhaust stack which exhausts a minimum of 54 feet above ground level.
3. The ventilation system provides ventilation for certain storage and experimental facilities and exhausts these a minimum of 54 feet above ground level.

Amendment No. 48 FNR Tech. Specs.

4. The openings into the reactor building are an equipment access door, three personnel doors, an equipment access hatch, air intake and exhaust ducts, room 3103 fume hood exhaust duct, beam port ventilation duct, a sealed north wall door, a door between the hot cave operating face and the beam port floor, a sealed foundation tile drain to the cold sump, and a pneumatic tube system for sample transfer between the FNR and several laboratories in the Phoenix Memorial Laboratory.

These design features apply until the quantity of radioactive materials in unsealed form, on foils

  • or plated sources, or sealed in glass contained in the reactor building is less than 1.5 x 10-2
  • times the quantities in 10CFR30.72, Schedule C - Quantities of Radioactive Materials Requiring
  • Consideration of the Need for an Emergency Plan for Responding to a Release.
  • 5.4 Fuel Storage The license for the Ford Nuclear Reactor does not allow for the possession of reactor fuel.

Amendment No. 48 FNR Tech. Specs.

6.0 ADMINISTRATIVE CONTROLS 6.1 Organization

1. The organizational structure of the University of Michigan relating to the Ford Nuclear Reactor (FNR) shall be as shown in Figure 6.1.
2. The Nuclear Reactor Laboratory Manager shall be responsible for the safe operation of the Ford Nuclear Reactor. 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 operating procedures. During periods of his absence, his responsibilities are delegated to the Assistant Manager for Operations or to the Assistant Manager for Research Support Activities.
3. In all matters pertaining to the operation of the plant and these technical specifications, the Nuclear Reactor Laboratory Manager shall report to and be directly responsible to the Director, Michigan Memorial-Phoenix Project.
4. Qualifications, Nuclear Reactor Laboratory Manager and Assistant Managers: Minimum qualifications for the Nuclear Reactor Laboratory Manager and Assistant Managers shall be bachelor's degrees and at least four years of reactor operating experience in increasingly responsible positions. Years spent in graduate study may be substituted for operating experience on a one for one basis up to a maximum of two years. Within six months after being assigned these positions, the Nuclear Reactor Laboratory Manager and the Assistant Managers shall apply for NRC senior operator licenses if they do not already hold licenses.
5. A health physicist who is organizationally independent of the Ford Nuclear Reactor operations group shall be responsible for radiological safety at the facility.
6. A licensed operator or licensed senior operator pursuant to 10CFR55 shall be present in the control room whenever the reactor is in operation as defined in these specifications.

The minimum operating crew shall be composed of two individuals, at least one of whom shall be a licensed senior reactor operator.

7. The Nuclear Reactor Laboratory Manager, one of the Assistant Managers, or a licensed senior reactor operator shall be readily available on-call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, seven days per week. The identity of and method for rapidly contacting the on-call supervisor shall be known to the reactor operator or shutdown watchman on duty.
8. Licensed operators are not required to be present in the facility when the reactor is secured.
9. All licensed operators at the facility shall participate in an approved operator requalification program as a condition of their continued assignment to operator duties.

Amendment No. 48 FNR Tech. Specs.

Figure 6.1 Organization Chart for the Ford Nuclear Reactor Amendment No. 48 FNR Tech. Specs.

6.2 Review and Audit

1. A Safety Review Committee (SRC) shall review reactor operations and advise the Director, Michigan Memorial-Phoenix Project, in matters relating to the health and safety of hte public and the safety of facility operations.
2. The Safety Review Committee shall have at least eight members of whom no more than the minority shall be from the line organization shown in Figure 6.1 or shall administratively report to anyone in that line organization below the Vice President for Research. The Committee shall be made up of University faculty and staff and an individual from outside the University appointed by the Vice President for Research who shall collectively provide experience in reactor engineering, instrumentation and control systems, radiological safety, and mechanical and electrical systems.
3. The Committee shall meet at least semiannually.
4. A quorum shall consist of not less than a majority of the full committee and shall include the chairman or his designated alternate.
5. Those changes, experiments, and tests that require specific SRC review must be approved by a majority of the full Committee Membership. Votes may be cast at SRC meetings or via individual polling of members.
6. Minutes of each Committee meeting shall be distributed to the Director, Michigan Memorial-Phoenix Project, all Safety Review Committee members, and such others as the chairman may designate.
7. The Safety Review Committee shall:
a. Review and approve proposed experiments and tests utilizing the reactor facility which are significantly different from tests and experiments previously performed at the Ford Nuclear Reactor. In the event of a disagreement over approval of an experiment between the Committee and the Nuclear Reactor Laboratory Manager, the matter shall be referred to the Director, Michigan Memorial-Phoenix Project for resolution.
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 prepared 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 pursuant to 10CFR50.59(c).
e. Review the audit report provided by the consultant for reactor operations.
8. 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 Amendment No. 48 FNR Tech. Specs.

Director, Michigan Memorial-Phoenix Project. The Director shall provide the members of the Safety Review Committee with copies of this report.

9. The audit shall be conducted with the following guidelines:
a. At least once every five years, a broad review will be made of the following areas: (1)

Administration; (2) Safety Review Committee; (3) Reactor operators (4) Procedures; (5)

Surveillance; (6) Quality Assurance Program; (7) Logs and Records; (8) Experiments; (9) Emergency Plan; (10) Security Plan; and (11) Health physics support. The purposes of the review are: (1) Evaluate the adequacy of the organization, training, plans, procedures, surveillance, and records for safe operation of the facility; (2) Verify that the requirements of Technical are being met; (3) Establish whether plans and procedures are being implemented; and (4) Determine wheter responsibilities within the organization are appropriate.

b. Routine audits will review a limited number of systems in depth each year and iwll include as applicable to each system: (1) Operating procedures and records; (2)

Calibration procedures and records; (3) Equipment operation, condition, and failures; (4) Modifications; and (5) Reportable occurrences.

6.3 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 Nuclear Reactor Laboratory Manager shall be notified of the occurrence. 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 Committee; the Director, Michigan Memorial-Phoenix Projet; 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 measures to prevent or reduce the probability or consequences of recurrence.

6.4 Operating Procedures Written procedures including applicable checklists, 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 reactor
2. Installation and removal of fuel elements, control rods, experiments and experimental facilities;
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 releas of radioactivity, including provisions for evacuation, reentry, recovery, and medical support;
5. Maintenance procedures which could have an effect on reactor safety; Amendment No. 48 FNR Tech. Specs.
6. Periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors;
7. Facility security plan;
8. Radiation protection procedures.

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 the approval of the Nuclear Reactor Laboratory Manager or one of the Assistant Managers. All temporary changes to 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. Records of experiments performed;
d. Records of radioactive shipments;
e. Records of radioactive experiments;
f. Operator requalification program records (the five year period will commence after termination of the assignment of the operator to operative duties);
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:
a. Gaseous and liquid waste released to the environs;
b. Off site 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.

6.6 Reporting Requirements In addition to reports required by Title 10, Code of Federal Regulations, the following reports shall be submitted to the United States Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D.C. 20555 and to the Administrator, Region III.

Amendment No. 48 FNR Tech. Specs.

The report shall include the following:

1. Annual Operating Report
a. Operations Summary
1. Changes in facility design.
2. Performance characteristics (e.g., equipment and fuel performance).
3. Changes in operating procedrues 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 experiments which required authorization from the commission pursuant to 10CFR50.59(a).
6. Changes in the plant operating staff serving in the following positions:
a. Nuclear Reactor Laboratory Manager;
b. Health physicist;
c. Safety Review Committee members.
b. Power Generation A monthly tabulation of the thermal output of the facility during the reporting period
c. Shutdowns A listing of unscheduled shutdowns which have occurred during the reporting period, tabulated according to cause, and a brief discussion of hte actions taken to prevent recurrence.
d. Maintenance A discussion of corrective maintenance, excluding preventative maintenance, performed during the reporting period on safety related systems and components.
e. Changes, Tests and Experiments A brief discussion and a summary of the safety evaluation for those changes, tests, and 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 Amendment No. 48 FNR Tech. Specs.
a. Gross Radioactivity Releases
1. Total gaseous radioactivity in curies.
2. Average concentration of gaseous effluents released during normal steady state operation averaged over one year.
3. Maximum instantaneous concentration of noble gas radionuclides released during special operations, tests or experiments.
4. Percent of diluted, 10CFR20, Appendix B, Table 2, Column 1, air effluent concentration limit.
b. Iodine Releases (Required if iodine-131 is identified in primary coolant samples, or if fueled experiments are conducted at the facility.)
1. Total particulate gross beta and gamma radioactivity released in curies excluding background radioactivity.
2. Percent of diluted, 10CFR20, Appendix B, Table 2, Column 1, air effluent concentration limit.
c. Particulate Releases
1. Total particulate gross beta and gamma radioactivity released in curies excluding background radioactivity.
2. Gross alpha radioactivity released in curies excluding background radioactivity. (Required if the operational or 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 diluted, 10CFR20, Appendix B, Table 2, Column 1, air effluent concentration limit, 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 unrestricted areas or sanitary sewer averaged over period of release.
b. The maximum concentration of beta and gamma radioactivity released to unrestricted areas.
c. Total alpha radioactivity in curies released and average concentration released to unrestricted areas averaged over the period of release. (Required if the operational or experimental program could result in the release of alpha emitters.)

Amendment No. 48 FNR Tech. Specs.

d. Total volume in ml of liquid waste water 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.
g. Percent of diluted, 10CFR20, Appendix B, Table 3, Releases to sewers.
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. Average annual concentrations or levels of radiation for the sampling point with the highest average concentration or level and the location of that point with respect to the site.
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 10% of those that could result from continuous exposure ot the concentration values listed in 10CFR20, Appendix B, Table 2, Columns 1 and 2, estimates of the likely resultant exposure to individuals and to population groups and assumptions upon which estimates are based.
7. If significant variations of off site 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 whole body 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.

Amendment No. 48 FNR Tech. Specs.

2. Non-Routine Reports
a. Reportable Occurrence Reports In the event of a reportable occurrence as defined in section 1.0, notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and FAX to the Reactor Project Manager, Headquarters, U.S. Nuclear Regulatory Commission and to the Administrator, Region III, followed by a written report within 14 days to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D. C. 20555, and to the Administrator, Region III. FAX 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 FAX notification shall:
1. Describe, analyze, 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 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.
b. Technical Specification, Safety Analysis, and System Deficiencies A written report shall be forwarded within 30 days to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington D. C. 20555, and to the Administrator, Region III, in the event of:
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;
2. Discovery of any substantial variance from performance specifications contained in the technical specifications and safety analysis.
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.

Amendment No. 48 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. R-28 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR DOCKET NO. 50-02

1.0 INTRODUCTION

By letters dated September 08, 2005, February 28, 2006, and April 6, 2006, the University of Michigan (the licensee) submitted a request to change the Technical Specifications (TSs) for the Ford Nuclear Reactor (FNR). The requested change would eliminate those specifications which are no longer applicable for the facility not licensed to possess reactor fuel. Each change is discussed below.

2.0 EVALUATION 2.1 Technical Specification 2.1, Safety Limits As of December 16, 2003, the FNR no longer has reactor fuel on site and on January 29, 2004, the license for the FNR was modified to no longer permit operation of the reactor and to not allow fuel elements to be placed in the reactor grid. As the Safety Limits in the TS were for the protection of the cladding integrity of the fuel during reactor operation, the licensee is requesting that TS 2.1, Safety Limits, and its subsets TS 2.1.1, Safety Limits in the Forced Convection Mode, and TS 2.1.2, Safety Limits in the Natural Convection Mode be removed from the TS.

The objectives of TS 2.1.1 and 2.1.2 are to assure the integrity of the fuel cladding during reactor operation. The licensee is requesting to delete TS 2.1.1 and 2.1.2 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel this change is acceptable.

2.2 Technical Specification 2.2, Limiting Safety System Settings

The objective of TS 2.2 and its subsets TS 2.2.1, Limiting Safety System Setting in the Forced Convection Mode, and TS 2.2.2, Limiting Safety System Setting in the Natural Convection Flow Mode, is to prevent exceeding a safety limit and assure the cladding integrity of the reactor fuel during reactor operation. The licensee is requesting to delete TS 2.2, TS 2.2.1, and TS 2.2.2 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part

70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel this change is acceptable.

2.3 Technical Specifications 3.1, Reactivity Limits, and 4.1, Reactivity Limits The objective of TS 3.1 is to assure that the reactor can be controlled and shutdown at all times and that the safety limits will not be exceeded. The licensee is requesting to delete TS 3.1 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part

70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel or operate the reactor, this change is acceptable.

The objective of TS 4.1 is to assure reactivity limits of TS 3.1 are not exceeded. The licensee is requesting to delete TS 4.1 based on the FNR operating license modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70 be removed. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel, and TS 3.1 has been deleted this change is acceptable.

2.4 Technical Specifications 3.2, Reactor Safety System, and 4.2, Reactor Safety System The objective of TS 3.2 is to specify the lowest acceptable level of performance or the minimum number of acceptable components for the reactor safety system and other safety related instrumentation. The request to delete TS 3.2 is based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70.

In addition, the licensee is requesting that the requirements for area radiation monitoring identified in TS 3.2 be moved to the revised Limited Condition of Operation (LCO) Section 3.5, Radiation Monitoring, and the requirements of the facility radiation exhaust monitor identified in TS 3.2 be moved to the revised LCO Section 3.3, Confinement.

Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel or operate the reactor, and the requirements for radiation monitoring and the requirements for facility radiation exhaust monitor identified in TS 3.2 are moved to TS 3.5 and TS 3.3 respectively, this change is acceptable.

The objective of TS 4.2 is to assure that the reactor safety system is operable as required by TS 3.2. The licensee is requesting to delete TS 4.2 based on the FNR operating license modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70 be removed. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel or operate the reactor, and TS 3.2 has been deleted this change is acceptable 2.5 Technical Specifications 3.3, FNR Confinement, and 4.3, FNR Confinement The objective of TS 3.3 is to assure that the FNR building confinement integrity is maintained during reactor operation and to minimize the release of airborne radioactive materials from the reactor building. With the permanent cessation of operations and to facilitate equipment access for decommissioning, the licensee is requesting to revise the objective of TS 3.3, FNR Confinement to:

1. To assure that automatic protective action is initiated to limit the release of radioactive effluents from the reactor building when required.
2. To provide an audible alarm within the reactor building to initiate evacuation when required.
3. To assure that the FNR reactor building confinement integrity is maintained when required.

The licensee is also requesting that the applicability of TS 3.3, FNR Confinement, and its surveillance be revised to remain in effect until that point during decommissioning where the removal of radioactive materials from the facility reduces the quantity of radioactive materials in unsealed form, on foils or plated sources, or sealed in glass contained in the reactor building exceeds 1.5 x 10-2 times the quantities in 10 CFR 30.72, Schedule C - Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release. The 1.5 x 10-2 times is to account for the difference between the 1 rem limit in 10 CFR 30.(i)(1)(i) and the lower 15 mrem limit for an Unusual Event (the lowest level of emergency for a non-power reactor). Once the quantity of radioactive materials in unsealed form, on foils or plated sources, or sealed in glass contained in the reactor building has been reduced to less than 1.5 x 10-2 times the quantity of materials listed in 10 CFR 30.72, Schedule C, then the need for the automatic protective actions associated with the reactor building exhaust radiation monitor or the continuous air monitor may be removed. The licensee recognizes that the requirements of 10 CFR 20.1301, Dose Limits for Individual Members of the Public would continue to apply, subject to the allowances of 10 CFR 20.1302, Compliance with Dose Limits for Individual Members of the Public.

The new TS 3.3, FNR Confinement, will continue to specify that when the radiation level in the FNR ventilation exhaust duct is equal to or greater than 1mR/hr, automatic protective actions occur to isolate the building ventilation system. The new TS 3.3, FNR Confinement, will: 1) provide a mechanism to isolate the FNR building ventilation system in the event of a significant release of radioactive material into the reactor building; 2) maintain the integrity of confinement at or above the level assumed in the Hazardous Summary Report and minimize the release of radioactive material by requiring that access doors and equipment access hatch remain closed except for brief attended periods to permit personnel or equipment passage; 3) assure that the building leakage rate will not exceed the leakage rate used in the evaluation of potential

radiation exposure to persons at the operations boundary following an accident releasing fission products within the confinement building; 4) add the requirement of a radiation instrument in the building air exhaust plenum to assure that automatic protective actions for confinement occur should there be a release of radioactive material equal to or greater that 1 mR/hr from the FNR building and that an audible alarm is sounded in the reactor building to initiate evacuation (the audible alarm requirement was moved to this section from TS 3.2, Reactor Safety System).

The replacement of the applicability and objectivity for TS 3.3 is based on: 1) the FNR operating license modified on January 29, 2004 which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, 2) the condition in the operating license which no longer allows for the possession of reactor fuel under 10 CFR Part 70; 3) the requirements of effluent monitoring which has been moved to TS 3.5; 4) the addition of a radiation instrument to monitor the building air exhaust plenum for effluent monitoring and an audible alarm should protective actions occur; and 5) FNR has no reactor fuel.

The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel, the radiation instrument identified in TS 3.2 is moved to TS 3.3, and that there is a gamma radiation detector to monitor radioactive effluents and cause automatic protective actions to limit the release of radioactive effluents from the reactor building, this change is acceptable.

The licensee is requesting to revise the applicability and objective of TS 4.3, FNR Confinement, to reflect the applicability and objective of revised TS 3.3, FNR Confinement. The new TS 4.3, FNR Confinement will assure that the closure devices for the building openings are in satisfactory condition to provide adequate confinement of any airborne radioactivity released into the building. In addition, the licensee is requesting to add surveillance requirements to assure that the radiation detector used to initiate the automatic protective action is operable.

The NRC staff concludes that this change is acceptable.

2.6 Technical Specifications 3.4, Primary Coolant Conditions, and 4.4, Primary Coolant System The objective of TS 3.4 is to maintain the primary coolant in a condition to minimize the corrosion of the primary coolant system, fuel clad, and other reactor components, and to assure proper conditions of coolant for normal and emergency requirements. Currently, FNR has no reactor fuel. Based on the FNR operating license, modified on January 29, 2004, which states:

The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR 70, the specifications of TS 3.4 are no longer necessary. The licensee is requesting to revise TS 3.4 to change its title, objective, and specification. The proposed title for TS 3.4 is Pool Water Conditions. The proposed objective and applicability of TS 3.4 will facilitate the detection of significant pool water leaks whenever the quantity of water in the pool is greater than 900 gallons. The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel, and the new TS will provide for continuous monitoring for pool water leakage, this change is acceptable.

The objective of TS 4.4, Primary Coolant System, is to assure high quality pool water and to detect the release of fission products from fuel elements. Based on the FNR operating license modified on January 29, 2004 which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and the condition in the operating license allowing for

the possession of reactor fuel under 10 CFR Part 70 be removed, the licensee is requesting to revise TS 4.4 to change its title, objective, and specification. The proposed title for TS 3.4 is Pool Water Conditions. The proposed objective and applicability of TS 4.4 will facilitate the detection of significant pool water leaks whenever the quantity of water in the pool is greater than 900 gallons. The revision to TS 4.4 is based on routine inspection of the makeup water records to provide early warning of significant pool leaks.

The NRC staff concludes that since the FNR does not have any fuel, the operating license does not allow for the FNR to possess any fuel, and that the FNR makeup water needs will be monitored over a period of time when the reactor pool is greater than 900 gallons, which will allow for detection of significant water leaks, this change is acceptable.

2.7 Technical Specification 3.5, Radiation Airborne Effluents Currently the LCO requirements for area monitoring are contained in TS 3.2, Reactor Safety System, which is being deleted from the TS. The licensee has proposed that the requirements for the area monitors be combined with the requirement in Section 3.5, Airborne Effluents, and that this section be renamed Radiation Monitoring. The applicability of the new TS 3.5 is based on monitoring of effluent releases from the FNR, area radiation levels within the reactor building, and particulate airborne activity within the reactor building to assure that the release of airborne radioactive material from the FNR is maintained below the limits established in 10 CFR Part 20 and to ensure that occupational exposures are controlled as established in 10 CFR Part 20. The licensee has proposed:

1. that the new title of TS 3.5 be Radiation Monitoring. Since this is administrative, this change is acceptable.
2. that the LCO and surveillance requirements associated with the mobile particulate monitor for the Stack 2 exhaust be removed from TS 3.5. The LCO and surveillance requirements of the Stack 2 monitors are based on monitoring radioactive effluent from a possible failure of an experiment in the pneumatic tube system. The FNR operating license, modified on January 29, 2004, states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and removes the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70. The permanent cessation of operation of the reactor has eliminated the pneumatic tube system as a source of high level of radioactive effluent, and the airborne radioactivity of grid, the reactor building is monitored by the reactor building exhaust radiation monitoring system. The NRC staff concludes that this change is acceptable.
3. that an airborne particulate monitor on the first floor be added to TS 3.5 as a requirement during licensed activities which could lead to the generation of airborne radioactivity exceeding 1% of the applicable concentrations specified in 10 CFR 20, Appendix B, Table 1, Column 3, Derived Air Concentration (DAC). The addition of this requirement facilitates the removal of the Stack 2 mobile particulate air monitor. The NRC staff finds that this addition to TS 3.5 is acceptable.
4. that the LCO and the surveillance requirements for gaseous activity detectors be deleted. With the removal of all irradiated fuel from the facility and the current license modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the

operating license allowing for the possession of reactor fuel under 10 CFR Part 70, radioactive gases such as argon-41 are no longer present and can no longer be generated as fission products or neutron activation products at the facility. The NRC staff concludes that the requirement for the gaseous activity detector systems can be removed without decreasing the safety of the facility. This change is acceptable.

2.8 Technical Specification 3.7, Limitations of Experiments The objective of TS 3.7 is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure. The licensee is requesting to delete TS 3.7 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part

70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel, this change is acceptable.

2.9 Technical Specifications 3.8, Fission Density Limit, and 4.7, Fission Density Limits The objective of TS 3.8 is to prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products. The objective of TS 4.7 is to assure that the fission density limits of TS 3.8 are not exceeded. The licensee is requesting to delete TS 3.8 and 4.7 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part

70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel, this change is acceptable.

2.10 Technical Specifications 5.2, Reactor Fuel, and 5.4, Fuel Storage The objective of TS 5.2 is to assure that proper fuel design is used in the FNR core. The objective of TS 5.4 is to assure that adequate cooling is provided for irradiated fuel elements and fueled devices in storage. The licensee is requesting to delete TS 5.2 and 5.4 based on the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor nor place fuel elements in the reactor grid, and which removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part

70. Currently, FNR has no reactor fuel. The NRC staff concludes that since the FNR does not have any fuel and that the operating license does not allow for the FNR to possess any fuel, this change is acceptable.

2.11 Technical Specification 5.3, Reactor Building TS 5.0, Design Features, identifies those design features of the facility, such as materials of construction and geometric arrangements that, if altered or modified, would significantly affect safety and are not included in Sections 2, 3, or 4 of the TS. In section 5.3, Reactor Building, the licensee describes the general features of the reactor building, the reactor building ventilation system, the ventilation air intake and exhaust ducts, and various openings of the reactor building including the personnel and equipment access doors. Currently, the FNR operating license, modified on January 29, 2004, which states: The licensee shall not operate the reactor

nor place fuel elements in the reactor grid, removed the condition in the operating license allowing for the possession of reactor fuel under 10 CFR Part 70. The licensee is requesting that the design features described in TS 5.3 no longer apply when the quantity of radioactive materials in unsealed form, on foils or plated sources, or sealed in glass contained in the reactor building exceeds 1.5 x 10-2 times the quantities in 10 CFR 30.72, Schedule C - Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release. This request to revise TS 5.3 is to support the decommissioning and dismantling of the FNR as described in the licensee's decommissioning plan submitted on June 23, 2004, and currently under review by the NRC staff.

The dismantling of safety related equipment or components during decommissioning are described in the decommissioning plan, submitted to the NRC for approval. The licensee is committed to the protection of the public and personnel from potentially hazardous exposures and situations resulting from the decommissioning. The NRC staff concludes that this change is acceptable.

2.12 Editorial changes The licensee made various grammatical and format changes, which resulted in the need to reissue the TS in its entirety. The licensee indicated these changes did not affect the meaning of the requirement, and therefore, the changes are acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves changes in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes in inspection and surveillance requirements. The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

This amendment also involves changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities, and (3) such activities will be conducted in compliance with the Commissions regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.

Principal Contributors: Jessie F. Quichocho Patrick J. Isaac Date: May 8, 2006

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