ML061450128

From kanterella
Jump to navigation Jump to search
Ford Nuclear Reactor - Technical Specification Amendment Request, Amendment 50
ML061450128
Person / Time
Site: University of Michigan
Issue date: 05/17/2006
From: Becker C
University of Michigan
To:
Document Control Desk, NRC/FSME
References
Download: ML061450128 (30)
v • d • e


Text

PHOENIX MEMORIAL LABORATORY FORD NUCLEAR REACTOR goA. ANN ARBOR, Ml 48109-2100 MICHIGAN MEMORIAL PHOENIX PROJECT 17 May 2006 S'p D 40l0.?

Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Docket 50-2, License R-28

Subject:

Ford Nuclear Reactor - Technical Specification Amendment Request, Amendment 50

Dear Sir:

The University of Michigan's, Ford Nuclear Reactor is providing a revised, full Technical Specifications which fully incorporates the Technical Specification changes requested in the Decommissioning Plan, Revision 1 dated 05 January 2006 as submitted to the Commission via latter dated 10 January 2006. This revised, full Technical Specifications is based upon the Technical Specification Amendment 48 approved by the Commission on 8 May 2006.

In the preparation of this revised, full Technical Specifications, Sections 6.5, OperatingRecords and 6.6, Reporting Requirements were renumbered (i.e. 6.5 became 6.6 and 6.6 became 6.7) as the change requested in the Decommissioning Plan, Revision I split Section 6.2, Review and Audit into two sections 6.2, Review and Section 6.3, Audit. No other changes were made to the Operating Records, or Reporting Requirements sections of the Technical Specifications.

Additionally, in reviewing the Decommissioning Plan, Revision I a typo was identified on page 3-25. In the end of the last paragraph a reference is made to license amendment No. 35 and No. 46. The correct license amendments are No. 36 and No. 46.

If there are any questions regarding this information, please feel free to contact Christopher W. Becker at (734) 764-6224.

I declare under penalty of perjury that the foregoing is, to the best of my knowledge, true and correct.

Signature: O .Bc er Executed on: /7 4fa-Z A Christophtor LW.Becker Mng Nuclear Reactor Laboratory Manager Cc: Patrick Isaac File: Correspondence 06-008 License Amendment - Decommissioning Plan Aoo-O, Phone: (734) 764-6224 Fax: (734) 936-1571

( RDocurnents cand SothirqA s\s.vbeckcr\My Documrc;ils\UofM'\Genral\Lciler File\CYO6\06-8i.cdoc 1 of 1

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 PermanentReactor Shutdown, Decontamination and Decommissioning Amendment No. 50

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 .. ........ I................. 24 6.5 Operating Records .............. ...... 25 6.6 Reporting Requirements ............................................ 25 Amendment No. 50 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.l. 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. 50 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 orzconfiguration.

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 xenon poisoning on core reactivity accounted for if greater than or equal to 0.05% AK/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. 50 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 AK/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 Ournup, 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. 50 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. 50 FNR Tech. Specs.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits Anplicability 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 I OCFR70 was removed.

2.2 Limiting Safety System Settings (LSSS)

A&plicability 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 IOCFR70 was removed.

Amendment No. 50 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 IOCFR70 was removed.

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 10CFR70 was removed.

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 I OCFR30.72, Schedule C - Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release Amendment No. 50 FNR Tech. Specs.

Obiective:

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 I mrem/hr, THEN i The reactor building ventilation supply and exhaust fans shall automatically turn off; ii. The reactor building ventilation supply and exhaust dampers shall automatically 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 rooTp 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. 50 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 104 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. 50 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.

Obiective:

To assure that the release of airborne radioactive material from the Ford Nuclear Reactor is maintained below the limits established in IOCFR20 and to ensure that occupational exposures are controlled as established in I 0CFR20.

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 IOCFR20, 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 exceeding 1% of the applicable concentrations specified in I OCFR20, Appendix B, Table 1, 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 exceeding 1% of the applicable concentrations specified in 10CFR20, Appendix B, Table 1, 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. 50 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 I OCFR20.

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.

Obiectives:

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. 50 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 10CFR70 was removed.

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. i l 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 10CFR70 was removed.

Amendment No. 50 FNR Tech. Specs.

4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits ADplicability:

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 IOCFR70 was removed.

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 10CFR70 was removed.

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 I OCFR30.72, Schedule C - Quantities of Radioactive Materials Requiring Consideration of the Need for an Emergency Plan for Responding to a Release.

Obiective:

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. 50 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 Obiective:

Review of the makeup water needs over a perisd 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. 50 l 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. 50 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 10CFR70 was removed. ,

Amendment No. 50 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. 50 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.

I I , ,\ , I Amendment No. 50 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 Reactor Manager shall be responsible for the safe decommissioning of the Ford Nuclear Reactor. He shall be responsible for assuring that all activities are conducted in a safe manner within the limits prescribed by the facility license, including the technical specifications and facility procedures. During periods of his absence, the responsibilities of the Reactor Manger may be delegated to an individual who satisfies the qualification requirements for the Reactor Manager.
3. In all matters pertaining to the decommissioning of the Ford Nuclear Reactor and these technical specifications, the Reactor Manager shall report to and be directly responsible to the Director of Occupational Safety and Environmental Health.
4. A Radiation Safety Officer or health physicist, who is organizationally independent of the Ford Nuclear Reactor staff and contractors performing decommissioning activities, shall be responsible for radiation and industrial safety at the facility. During periods of his absence, the responsibilities of the Radiation Safety Officer may be delegated to an individual who satisfies the qualification requirements for the Radiation Safety Officer.
5. Qualifications:
1. At the time of appointment to the position, the Reactor Manager shall have a minimum of six years of nuclear experience. The individual shall have a recognized baccalaureate or higher degree in an engineering or scientific field. Education or experience that is job related may be substituted for a degree on a case-by-case basis. The degree may fulfill four years of the six years of nuclear experience required on a one-for-one time basis.

The individual shall receive appropriate facility specific training based upon a comparison of the individual's background and abilities with the responsibilities and duties of the position. Because of the educational and experience requirements of the position, continued formal training may not be required.

2. At the time of appointment, the Radiation Safety Officer shall have a minimum of six years of radiation safety experience. The individual shall have a recognized baccalaureate or higher degree in health physics, nuclear engineering, or scientific field.

Education or experience that is job related may be substituted for a degree on a case-by-case basis. The degree may fulfill four years of the six years of nuclear experience required on a one-for-one time basis. The individual shall receive appropriate facility-specific training based upon a comparison of the individual's background and abilities with the responsibilities and duties of the position. Because of the educational and experience requirements of the position, continued formal training may not be required.

Amendment No. 50 FNR Tech. Specs.

Figure 6.1 Organization Chart for the Ford Nuclear Reactor Regents University of Michigan I

[;dInI lPresident I

, rI I

lVice President ResearchI I Executive Vice President and Chief Financial Officer I

Associate Vice President Facilities & Operations I

, ail, " F" ;v -

~.l':

...l....11tt I Director Occupational Safety and Environmental Health I Review Committee Safety and Licensing Function I Radiation Safety Officer Reactor Manager

~I, I Safety Reactor Staff Staff Safety e Tech tiiCal, Environmental

  • Operation a/, Quality Line Management & Liceonsing Function

- Managcement

.1.

1*I Amendment No. 50 FNR Tech. Specs.

6.2 Review

1. A Decommissioning Review Committee (DRC) shall review decommissioning activities and advise the Director of Occupational Safety and Environmental Health in matters relating to the health and safety of the UM community, the public, and the safety of decommissioning activities.

2 The Decommissioning Review Committee shall be composed of a minimum of three members and an unspecified number of alternates of which only a minority shall be from the line organization shown in Figure 6-1. The members and alternates shall be appointed by the Vice President for Research. The review committee chair shall be appointed from the UM tenured faculty with a degree in engineering or a scientific field. The review committee chair shall receive, at the time of appointment, briefings sufficient to provide an understanding of the decommissioning project. The remaining members of the review committee and alternates shall collectively represent a broad spectrum of expertise appropriate for the decommissioning of FNR and may be either from within or outside the UM. Alternates may attend and vote on matters, regardless of the absence of regular members.

3. The review committee shall meet at least semiannually through the completion of the final status survey. After the completion of the final status survey the review committee shall meet as necessary to review or approve such matters as desired by the committee chair, the Director, Reactor Manager or the Radiation Safety Officer.
4. A quorum shall consist of not less than one-half the regular review committee membership, not including alternates, where the FNR Decommissioning Project staff does not constitute a majority and a representative of UM management at the Associate'or Assistant Vice President level or higher.
5. Approval of items by the review committee must be by a majority of the full review committee membership. Approval of items by the review committee may be cast at meetings or via individual polling of the regular review committee members.
6. The review committee chair may appoint subcommittees to facilitate targeted reviews or audits. The subcommittee chair shall be a regular committee member or alternate and shall not be a member of the FNR Project Staff. Thb Subcommittee shall forward items to the review committee chairman with recommendations. The full review committee shall approve all products of the subcommittee.
7. The minutes of the review committee shall be distributed to the Director, Reactor Manager, Radiation Safety Officer, Project Manager, Health Physics Supervisor, the regular members of the review committee, and such others as the chairman may designate.
8. The Decommissioning Review Committee shall approve:
a. Proposed changes in the license or technical specifications.
b. Proposed changes to the facility that can be implemented without the prior approval of the NRC as authorized by the license conditions implementing 10 CFR 50.59.
c. Proposed changes in the Decommissioning Plan that can be implemented without the prior approval of the NRC as described in the Decommissioning Plan, Section 9.0, Changes to the Decommissioning Plan and authorized by license condition.

Amendment No. 50 FNR Tech. Specs.

d. New procedures and changes to the procedures involving licensed activities and required by Section 6.5 of these specifications.

9 The Decommissioning Review Committee, as a review function, shall review:

a. Violations of technical specifications and reportable occurrences made pursuant to the requirements of the technical specifications.
b. Audit reports issued by a member or subcommittee as required by Section 6.3 of these specifications.
c. Plans for the following decommissioning activities prior to their implementation:

i Any activity which could compromise the structure and integrity of the reactor pool or the primary coolant system while pool water is relied upon for shielding of irradiated reactor components; ii The dismantlement of the irradiated reactor components in preparation for disposal; iii The movement of any heavy objects, greater than 5 tons in weight; iv Any activity which could compromise the structural integrity of the post and beam structure which supports the reactor building; v Any activity that will result in the direct release of radioactivity from the facility to the sanitary sewer or a navigable waterway; vi The draining of the reactor pool; vi The decontamination or dismantlement of the reactor pool structure; vii Any activity for which it is estimated that the cumulative radiation exposure for the activity will exceed 1 person-rem, or an individual radiation exposure to either an occupationally exposed person or a member of the public will exceed 20% of any applicable exposure limits of 10 CFR 20; and ix Any activity, known or anticipated by the review committee, which the review committee requests to review, subject to the approval of the Director.

6.3 Audit I The Decommissioning Review Committee as an audit function, shall ensure that the following are independently monitored or-audited:

a. Decommissioning operations to ensure they are being performed safely and in accordance with all applicable licenses and registrations held by the University and in compliance with applicable federal and state regulatory requirements (Radiological Protection Plan, Environmental Safety and Health Plan, etc.).
b. The quality assurance to verify that performance criteria are met as well as to determine the effectiveness of the program in satisfying the quality assurance requirements.

2 Each monitoring or audit report shall describe each reported adverse finding and shall be distributed to the Director, Reactor Manager, all review committee members, and others at the direction of the Director.

3 Monitoring or audits shall be performed annually, at a minimum, and should be scheduled by the Chair of the Decommissioning Review Committee, in a manner to provide coverage and coordination with ongoing activities, based on the status and importance of activities.

Amendment No. 50 FNR Tech. Specs.

4 The lead auditor and the audit team (if utilized) shall be selected by the Chair of the Decommissioning Review Committee, shall not be directly associated with decommissioning activities, shall not be a member of the FNR Decommissioning Project Team, and shall be familiar with quality assurance requirements applicable to the decommissioning of nuclear facilities.

6.4 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 Reactor Manager shall be notified of the occurrence. Corrective action shall be taken to correct the abnormal conditions and to prevent its recurrence. All other ongoing licensed activities shall be ceased until the occurrence has been resolved.

- 2 A report of such occurrence shall be made to the Decommissioning Review Committee the Director and the Nuclear Regulatory Commission in accordance with Section 6.7.2. 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.

6.5 Procedures I Written procedures, including applicable check lists, reviewed and approved by the Decommissioning Review Committee shall be in' effect and followed 'for the following licensed activities:

a. Normal operation of all systems structures or components described in these technical specifications or which are important to safety.
b. Actions for responding to emergency conditions involving the potential or actual release of radioactivity, including provisions for evacuation, reentry, recovery, and medical support.
c. Actions to be taken to correct specific and foreseen malfunctions of systems, structures or components described in these technical specifications or which are important to safety.
d. Activities performed to satisfy a surveillance requirement contained in these technical specifications.
e. Radiation and radioactive contamination control.
f. Physical security of the facility.
g. Implementation of the quality assurance program for the calibration and response testing of radiation instrumentation utilized for direct measurement in support of characterization, release, final status survey, or other quality assurance activities.

2 Substantive changes to these procedures shall be made only with the approval of the Decommissioning Review Committee. Non-substantive changes to these procedures may be made with the approval of the Reactor Manager. All non-substantive changes made to procedures shall be documented and subsequently reviewed by the Decommissioning Review Committee.

Amendment No. 50 FNR Tech. Specs.

6.6 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.

6.7 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 IlIl.

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.

Amendment No. 50 4 I-FNR Tech. Specs.

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
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 I, air effluent concentration limit.

Amendment No. 50 FNR Tech. Specs.

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'a'verage 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.)
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 Amendment No. 50 4

FNR Tech. Specs.

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 I OCFR20, Appendix B, Table 2, Columns I 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.
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 lil, 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 Ill. 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; Amendment No. 50 FNR Tech. Specs.
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 IIl, 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. 50

Retrieved from "https://kanterella.com/w/index.php?title=ML061450128&oldid=2584840"