ML20148M041

Amend 24 to License R-77,removing Authority from License to Operate Reactor,Authorizing possession-only of Reactor & Changing TSs to Remove Operational Requirements Not Needed for possession-only Status

ML20148M041
Person / Time
Site:	University of Buffalo
Issue date:	06/19/1997
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20148M035	List: ML20148M041 ML20148M044
References
R-077-A-24, R-77-A-24, NUDOCS 9706200252
Download: ML20148M041 (30)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001 l  % ***** $

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! STATE UNIVERSITY OF NEW YORK AT BUFFALO l DOCKET N0. 50-57 i AMENDMENT TO FACILITY OPERATING LICENSE I Amendment No. 24 License No. R-77

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

A. The application for amendment to Facility Operating License l No. R-77, filed by the State University of New York at Buffalo l (the licensee), dated July 23, 1996 and February 14, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter 1; B. The facility will be maintained in conformity with the  :

application, the provisic,ns of the Act, and the rules and j regulations of the Commission; C. There is reasonable assurance (1) that the activities I authorized by this amendment can be conducted without l endangering the health and safety of the public, and (ii) that  !

such activities will be conducted in compliance with the regulations of the Commisiion; D. The issuance of this amendment will not be inimical to the j common defense and security or to the healtii and safety of the  !

public; )

E. This amendment is issued in accordance with 10 CFR Part 51 of I the regulations of the Commission and all applicable l requirements have been satisfied; and i F. Prior notice of this amendment was not required by 10 CFR I 2.105 and publication of notice for this amendment is not required by 10 CFR 2.106.

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( l 9706200252 970619 PDR ADOCK 05000057 P PDR ,

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2. ' Accordingly, the license is amended by changes to the following

j paragraphs which are hereby amended to reads as follows: l 2.8. 1. Pursuant to Section 104c of the Act and Title 10 CFR Chapter 1, Part 50, " Domestic Licensing of Production and Utilization' >

Facilities", to possess, but not operate the reactor at the designated location in Buffalo, New York, in accordance with the

. procedures and limitations described in the application-and-this j license.

l 2. Pursuant to the Act and Title 10 CFR Chapter 1, Part 70,  ;

" Domestic Licensing of Special Nuclear Material", to possess up i to 55 kilograms of uranium-235 contained in enriched uranium and- .

1 other Special Nuclear Material produced by past operation of the '

reactor.

3. Pursuant to the Act and Title 10 CFR Chapter 1., Part 70,  ;

" Domestic Licensing of Special' Nuclear Material", to receive, possess, and use up to 80 grams of plutonium encapsulated in  ;

five 1-curie plutonium-Leryllium neutron sources in' connection I with the facility.

4. Pursuant to the Act and Title 10 CFR Chapter 1, Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material", to possess a 30-curie antimony-beryllium source and to possess, but not to separate, such byproduct material as may have been produced by operation of the facility.

2.C 1. The licensee shall not operate the reactor.

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2. Technical Soecifications i I

The Technical Specifications contained in Appendix A, as revised '

through-Amendment No. 24, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications as amended.

3. This license amendment is effective as' of its date of issuance except for Technical Specification Section 10.3.1.1 which shall become effective 30 i days from the date'of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h*%. h4 < -

Marvin M. Mendonca, Acting Director  !

Non-Power Reactors and Decommissioning Project Directorate' Division of Reactor Program Management Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance: June 19, 1997

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ENCLOSURE T0 tYCEN51_ AMEN 0 MENT 'ND. 21  ;

FACILITY OPERATING LICENSE WD. R-77 DOCKET NO. 50-57  ;

Revise Appendix A Technical Specifications by removing all pages and replace <

with the enclosed pages:

Remove Insert .

All Pages All Pages i

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Buffalo Materials Research Center State University of New York'at Buffalo ,

License R-77  :

Docket 5047 Technical Specifications .

(Possession On y) 2 AppencixA l

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Table of Contents 2.0 Possession Only Limits... . .. . . . . . . . . . .. . .. . .. 5 2.1 Authorized Activities.. . .. . .. . . . . . . . . . . . . . . . . .. 5 2.2 Fuel Quantity Limit.. .. . . . . . . . . .. . . . . .. . . . . . . . . . . ......5 3.0 Plant Instrumentation Systems... . . . . . . . . . . .5 3.1 Reactor Tank Instrumentation for Fuel Storage.. .. . ... . . . . . . . . . . .....5 3.2 Radiation Effluent Monitors Required During Fuel Storage. .... . . .. .. 6 3.3. Radiation Area Monitors Required During Fuel Handling Operations. . .. . .. .6 3.4 Radiation Effluent Monitors Required During Fuel Handling Operations. .. . . .7 4.0 Engineered Safety Systems.. . . . . . ....7 5.0 Reaaor Tank Water Conditions. . . .

.. 8 6.0 Airtome Effluents. . .. . . . . . . ... .. .9 6.1 Stack Exhaust Effluent Radiation Limit..... . . .. . . . . .. . ......9 6.2 Building Air Effluent Radiation Limit.. ... . . . . . . . . . . . . .9 7.0 Liquid Effluents. .. . . . . . . .. . . .. .. 9 8.0 Surveillance Requirements.. .. . .. . .. . . .10 8.1 Plant instrumentation Systems. . . . . . .. . . . .. .. . .. 10 -

8.2 Radiation Monitoring Systems. . . . . . .. .... . . . .. . . . . . .10 8.3 Engineered Safety Feature (Containment) Tests . . . . . . .. . . . . . . .. . .10 8.4 Other instrumentation System Surveillance.. . . . . . . . . .. .... 11 8.5 Reactor Fuel Shielding Water Monitoring .. . . . .. . . . ... .. . . .. 11 9.0 Plant Design Features. . . .. . . . . . . .12 9.1 Site Description.. . . . . . .. . . . . . . . . . .. . .. .. . .... .. . . . 12 9.2 Containment Building.. . . .. . . . . . . ... . . .. .12 9.3 VenNlation Systems. . .. . . .. . . .. . . .. 12 9.4 Reactor Tank. .. . . . .. . .. . . .. .. .. .. .. .. . . 13 3 9 5 Reactor Fuel. . .. .. . . . . . . . . . . . ... .. 13 9.6 Control Blades. .. . .. . .. . . . . .. . . . . . . . . . . . . . . . . . . 14 10.0 Fuel Storage and Transfer. . . .. . . . . . . . . ....14

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10.1 Cold Fuel Storage . . . . . . . . . . .. . . 14 10.2 Storage of the BMRC Fission Plate. . . . . . . . . . .. . . . . . . . . . 14 PAGE 1 Amendment No. 24 i

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I 10.3 Irtzdiated Fu:1 Storage end Transf r.......... .. . . ...... . . .. .. ...... ...... . ..... .............15 11.0 Administration . .. ......... .. ... . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......................17 ,

11.1 Organizational Structure . .. ...... ... ......... .. . .. ... . ... . .. . ...... .. ... .. ......... .. ....... ...~ 17 11.2 Minimum Staffing Requirements... ....... . ... .......... . , . . . . . . . . . . . . . . . . . . . . . . .18 11.3 On-Call Staffing Requirements . .......... .. . ... . . ... .... .. .. .... .... ..... . .... . .. ........ 18 11.4 Operational Requirements.,. . . . ... . .. ... ..... .... ...... ..... .. . . ................18  :

11.5 Review Functions. .. .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 19 12.0 Actions To Be Taken in the Event of a Reportable Occurrence. ... . .. .. .. . .. .... .. . . . .. 20 13.0 Written Procedures... ... . . . . . . . . . . . . . . ..................................................21 13.1 Required Procedures.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 21 13.2 Approval, Review and Update . .... ...... .. . ... . ... ... ..................................21 13.3 Tempomry Deviation from Written Proceduros.. ... ............... .. . .. .. . . ...... . ... .. .. 21 14.0 Record Keeping.. . . . . . . . . . . ... . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . 22 14.1 Records Which Shall be Retained for Five Years... . . .. .. . . ....... .. .. . . . . .. .. 22

........................22 14.2 Records Which Shall be Maintained for the Life of the Facility..

15.0 Reporting Requirements... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . 22 15.1 Annual Technical Report . . .. . . . . . . . . . . . . . . , .... . . . . . . . . . . . . . . . . . . . . . . 22 15.2 Reportable Occurrence Reports. . . . . . . . . . . . ....................................23 15.3 Safety Event Reports.. ... .... ... ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............23 15.4 Special Nuclear Materials Status Reports.. . . .. .. ... .... .. . .......... ........ .. . . ... 24 Table 1-Fuel Assemblies in Reactor Tank as of June 30, 1994 . . . . . . .. . . . . . . . . .. . . . . . . 2 5 Figure 1-Organizational Chart.. .... . .... ............ .. ... . . . . ... .......................26 PAGE 2 Amendment No. 24

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1.0 Definitions , *' '

Certified Fuel Handler: An individual who is authorized to supervise or perform fuel  !

handling pursuant to an NRC approved program. l l

Channel Calibration: A channel calibration is an adjustment of the channel so that its output corresponds, with acceptable accuracy, to known values of the parameter that the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall include a channel test. l Channel Check: A channel check is a qualitative verification of acceptable l performance by observation of channel behavior. This verification should include l comparison of the channel with other independent channels or systems measuring l the same variable, where this capability exists.  !

Channel Test: A channel test is the introduction of a signalinto the channel to verify that it is operating.

Cold Fuel: Cold fuel is any combination of fuel elements which may be stored within the fuel storage vault (s), in such a manner as to create a radiation level of not )

more than 5 mrem per hour at any accessible outer boundary of the vault. 1 Control Blade: A neutron absorbing blade with negative reactivity worth. .

Experimental Facility: An experimental facility is any structure or ' device associated with the reactor that is intended to guide, orient, position, mar,ipulate, or j otherwise facilitate a multiplicity of experiments of similar character.

, Fuel Assembiv: A grouping of 25 Pulstar fuel pins in the standard Zircalloy box and aluminum structures.

Fuel Canister: A canister (typically aluminum or stainless steel) which is used to store fuel pins.

Fuel Element: A single Pulstar fuel pin.

Fuel Hardlina: The manipulation, movement, or transfer of irradiated reactor fuel within or between fuel storage facilities.

Measured Value: The measured value of a process variable is the value of the .

variable as indicated by a measuring channel. l Measurina Channel: A measuring channelis the combination of sensor, amplifiers, I and output devices that are used for the purpose of measuring the value of a process variable.

Operable: Operable means that a component or system is capable of performing its intended function in its normal manner.

Operatina: Operating means that a component or syste . cerforming its intended function in its normal manner.

Permanent Experimental Facility: Those experimental facilities that would require considerable effort and planning to remove or alter such as the thermal column. .

1 Potentially Radioactive Liquid Effluents: Those liquid effluents from the facility l including from sinks, sumps, floor drains, etc., which have a reasonable potential to l PAGE 3 Amendment No. 24

cont:in rrdiorctivity et a lavalin exc:ss of 0.01% of tha efflu nt limit prescrib:d by 10 CFR 20.

Removal of a Control Blade: Means to disconnect and physically remove a control blade assembly (blade, shroud, and extension) from its gridplate position.

Reportable Occurrence: A reportable occurrence is any of the conditions described in Section 12.1 of these specifications.

True Value: The true value of a process variable is its actual value at any instant.

PAGE4 Amendment No. 24

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l 2.0 Do.s. session -dnly, Lint. iti ~ ' .- ' ..

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2.1 Authorized Activities

1) The BMRC reactor is licensed for " Possession Only' and no operation of the reactor is allowed. .

2.2 Fuel Quantity Limit

! 1) The storage of irradiated reactor fuel within the reactor tank or within en l altemative storage facilities pursuant to Section 10.3.3, shall tio .imited to the

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fuel that was present within the tank on June 30,1994, and no additional fuel

. elements may be introduced into the reactor tank or irradiated fuel storage facilities. This limit will prevent the introduction of additional cold clean fuel into

the tank.

1 j 2) At no time may more than 15 fuel assemblies be stored on the reactor gridplate.

This limit will prevent criticality even if all control blades are completely i withdrawn. The theoretical minimum number of cold clean fuel assemblies

required for criticality is seventeen. The average bumup of the existing fuel  ;

i arsemblies is more than 13,000 MWD / Tonne.

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j ').O Plant InstrumentatL6n Systemd y, ' [t ,'! ' ' . . . ..

! 3.1 Reactor Tank instmmentation for Fuel Storage 4

i Specifications The following plant instrumentation systems shat! be maintained.

1) High and Low Water level annunciators.

j 2) Rcactor Tank temperature indicator. ,

l 3) Primary pump suction valve interlock. l

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l In the event that these systems are tempormily out of service (such as for repair) compensating actions such as periodic monitoring, or additional administrative '

controls may be substituted. i 1

Applicability These specifications shall not apply if there is no fuel in the reactor l tank.

Specification 3.1.3 (suction valve intedock) shall not apply if the reactor tan < water i primary circulation pump is permanently disabled or electrically disconnected.  !

Basis

1) Specification 3.1.1 (HiGh and Low Water Level annunciation) will wam staff l members that the reactor tank water level is higher or lower than normal. i 1

2) Specification 3.1.2 (Pool Temperature monitrr) enables the staff to monitor the temperature of the reactor tahk waten PAGE5 Amendment No. 24 l

3) Sp cification 3.1.3 (Suction Valve Clos:d) disabl:s ths primcy pump so that it may not be started while the core outlet isolatien valve is closed. Starting the pump with this valve closed could damage the N-16 delay tank.

3.2 RadimEon ENiuent Monitors Requirted During Fuel Storage 6pplicability These specifications apply to the permanently mounted radiation monitors in the containment building, all of whn.h are equipped with remote read-out in the reactor control room.

Obiective The objective of these specifications is to set a minimum level of performance for the area radiation monitoring systems.

Specifications

1) Effluents from the containment building, exhausted inrough the Building Exhaust System (containment roof), will be continuously monitored for gaseous radioactivity by tne Building Gas Monitor. Values will be recorded at intervals not to exceed 15 minutes.

2) The setpoint for the BuUding Gas Monitor sha!! be specified in writing by the

, Operating Committee.

3) The Building Gas Monitor may be out of service for up to 10 days provided that

no fuel handling takes place.

Basis

1) Continuous operation of the Building Gas Monitor ensures that any gaseous i fission product fuel leak will be detected. i

2) Specification 3.2.2 will ensure that the alarm set point is clearly stated, cannot l be changed without management review, and can be maintained at the lowest possible level commensurate with facility conditions and operational requirements.

3) Specification 3.2.3 allows for repair or replacement of the Building Gas Monitor.

3.3. Radiation Area Monitors Required During Fuel Handling Operations l

Specifications i

, 1) Reactor Fuel shall not be handled in the reactor tank, unless the Reactor bridge j l U4onitor is operating. For purposes of this specification, any fuel handling in the Hot Cell which includes insertion of fuel into the pass-through tube, shall be considered "in the reactor tank."

2) The Set Point for the Reactor Bridge Monitor shall be specified in writing by the 4

Operating Committee and may not exceed 75 mR/hr.

3) in the event of failure of the Bridge Monitor a portable unit shall be substituted and shall be frequently monitored, and a qualified individual shall be stationed in i

the control room to initiate manual damper scram if necessary.

Basis

1) The Bridge Radiation Monitor will provide redundant waming to the reactor operators in the event of lowpool water level, and will warn ope.rators of 4

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unusually high radiation Isvsts should they occur during fusi handling operations.

2) Specification 3.3.2 will ensure that the alarm set point is clearly stated, cannot be changed without management review, and can be maintained at the lowest possible level commensurate with facility conditions and operational requirements.

3) Specification 3.3.3 will ensure that radiation levels will be adequately monitored if the Bridge Monitor is not operational. .

34 Radiation Emuent Monitors Required During Fuel Handling Operations Specification -

1) Reactor fuel shall not be handled in the reactor tank or the Hot Cell un! ass the Stack Particulate, Stack Gas, Building Particulate and Building Gas Monitors are operating.

2) The alarm set points for these monitors shall be specified in writing by the Operating Committec.

3) During Fuel handling operations, the outputs of the monitors shall be recorded on a strip chart, a data logger, videographic recorder, or equivalent, or shall be logged at intervals of not more than every 15 minutes.

Basis,

1) Specification 3.4.1 ensures that the staff will promptly be alerted to any releases to the environment, or gaseous rele.ases of radioactivity resulting from fuel cladding failure.

2) Specification 3.4.2 ensures that the alarm set points are cleady stated, can not be changed without management review, and can be maintained at the lowest possible levels commensurate with facility conditions and operational requirements.

3) Specification 3.4.3 ensures that any airbome radioactivity releases resulting from fuel failure shall be documented and can be quantified.

4.0 Engineered Safety Systems Applicability These specifications apply to the facility containment vessel and ventilation systems. <

Objectives The objective of these specifications is to control the release of airbome

. radioactivity in the event of the failure of the fuel cladding.

Specifications The reactor fuel shall not be handled in the reactor tank, Hot Cell, or in attemative facilities pursuant to Section 10.3.3 unless:

1) The Trt ,k door is closed and sealed, end at least one of the doors for each

! airlock is closed and sealed. All other penetrations such as piping and electrical l shall also be sealed.

2) The stack exhaust system fap located within the University Power House is operating.

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3) Th3 Building Air exh ust fan locat:d within the Control D ck fan room is operating.

4) The air pressure within the reactor containment is negative relative to the outside air pressure.

5) For manipulations within the Hot Cell, the pressure in the stack exhaust system, at the suction side of the basement stack fan, must also be negative relative to the containment pressure.

6) A HEPA filter is installed in the emergency exhaust duct and the modulating damper (6") and its controller are operable.

7) The dampers (Pratt dampers) within the containment ventilation ducts are operable and capable of closing in 5 seconds or less. They must close automatically in response to coincident high level alarms conditions for the Building Air (gaseous radioactivity) and Reactor Bridge (area) radiation monitors, or in response to a manual signal.

Basis

1) Specification 4.0.1 ensures that containment penetrations other than the ventilation ducts are closed, preventing the unmonitored and uncontrolled release of airbome radioactivity.

2) Specification 4.0.2 and 4.0.3 ensure that fans are operating to maintain the containment and stack exhaust system at negative pressure under normal or emergency conditions.

3) Specification 4.0.4. ensures that all containment leakage is inward.

4) Specification 4.0.5 ensures that in the event of fuel compromise within the Hot Cell, airbome radioactivity shall be exhausted by the stack and shall not immediately diffuse though the Hot Cell wall penetrations.

5) Specification 4.0.6 ensures that in the event of fuel compromise, negative pressure within the containment may be maintained in a controlled manner, without unnecessary releases of radioactivity to the envircnment.

6) Specification 4.0.7 ensures operability of the containment isolation systems in

! the event of fuel cladding compromise.

! 5.0 Reactor Tank Water Conditions . ..

Applicability These specifications apply to the purity of the reactor tank water whenever fuel is stored within the tank. These specifications also apply to any water which is in contact with fuel stored within altemative storage facilities pursuant to section 10.3.

Obiectives The objective of these specifications are to limit corrosir.1 of the reactor fuel and other in tank materials.

Specifications

1) The pH of the reactor tank water shall be maintained between 5.0 and 7.5.

2) The Resistivity of the reactor. tank water shall be maintained at an average of not less than 200,000 ohm-centimeters. For purposes of interpreting compliance PAGE8 Amendment No. 24 I

with this sp:cification, the minimum level must be met when av: rag:d ov3r any 30 day period.

Basis Specifications 5.0.1 and 5.0.2 will prevent excessive corrosive attack of the fuel cladding and hardware, control blades, and other activated in-tank components. It also provide adequate clarity of the shielding water so that fuel may be visually monitored. Limits are imposed on the average values because the time weighted values will determine corrosion rates, and short term deviations will not create a safety hazard. ,

6.0 Airtsorne EfR6ents

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Applicability These specifications apply to the levels o' radioactivity disch'arged to the environment th' rough the building air and povfer plant exhaust ducts.

Objective The objective of these specifications is to ensure that persons within the facility and persons outside of the facility are not exposed to concentrations of airbome radioactivity in excess of the limits established by 10 CFR 20.

Specifications 6.1 Stack Exhaust EfHuent Radiation Limit i 1

1) The concentration of radioactivity in the stack exhaust air, at the point of release  !

(top of stack), shall not exceed 700 times the effluent limit established in 10 l CFR 20, when averaged over the calendar year.

6.2 Building Air EfHuent Radiation Limit

1) The concentration of radioactivity in the Building Air Exhaust, at the point of release (containment roof), shall not exceed the effluent limit established in 10 CFR 20, when averaged over the calendar year.

Basis Specification 6.1 ensures that the ground level concentration when averaged over the calendar year will be less than the NRC effluent limit. This limit was derived from calculations which demonstrate tilat the minimum worst case dilution factor for the stack exhaust is 10,000, with an annual wind direction persistence of 0.28. A conservative error factor of 50 was further used to allow for correlation error, and the proximity of the 10 story Veterans Administration Medical Center located adjacent to the campus (10,000 x 1/50 x 1/0.28 = 714; rounded to 700).

Specification 6.2 ensures that the concentration of radioactivity in the air which exits through the containment roof, is below the NRC limit. Since the NRC Effluent Limits are lower than the Derived Air Concentrations, workers within the containment building will not be exposed to gaseous radioactivity in excess of occupational limits. Because the sampling point is downstream of the HEPA filters, for airbome particulate radioactivity, the relationship between effluent levels and potential occupational exposures, will depend on the officiency of the HEPA filtration system.

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7.0 Liquid Effiuents . . .' . , .

Applicability These Specifications apply to liquid radioactive effluents to the Sanitary Sewer System.

Obiectives The Objectives of these specifications are:

1) To Prevent unmonitored discharges of radioactivity to the Sanitary Sewer.

2) To ensure that discharges to the Sanitary Sewer are within the limits prescribed by 10CFR Part 20.

Specifications

1) All potentially radioactive liquid effluents shall be collected and retaine'd in a hold tank (s).

2) Before release to the Sanitary Sewer the contents of the tank (s) shall be mixed and a representative sample shall be drawn and analyzed for radioactive content.

3) The contents of the tank (s) shall not be released to the sanitary sewer unless the analysis demonstrates that the release shall be within the limits prescribed by 10 CFR 20.

4) For purposes of determination of the effluent discharge concentration in 3) above, the dilution by the most recently established Sewage flow rate of the Winspear Avenue trunk may be incorporated.

8 0 Surveina'n c.e Requirements .

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Lh Applicability These specifications apply to the surveillance requirements for reactor control systems, radiation monitoring systems, and engineered safety systems.

Objective The objective of these specifications is to prescribe the minimum surveillance activities to maintain the reactor in a safe, subcritical mode, to protect the safety of the reactor staff and the public.

Specifications 8.1 Plant Instmmentation Systems

1) The reactor tank low and nigh water level annunciators shall be tested monthly, at intervals not to exceed 6 weeks.

8.2 RadiationMonitoring Sfstems ,

1) The Reactor Bridge Monitor and the Effluent Radiation Monitors shsti be tested for operability monthly, at intervals not to exceed 6 weeks.

2) The Reactor Bridge Monitor and the Effluent Monitors shall be calibrated Quarterly, at intervals not to exceed four months. For the purpose of meeting this requirement, the monitors shall be calibrated by determination of their response to appropriate reference sources.

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I 3) Any radiation monitors associitid with Furi Storaga Fcciliti3s utiliz:d pursuint to Section 10.3, shall be calibrated before fuel is installed in the facility, and shall be Operability checked as appropriate.

8.3 Engineered Safety Feature (Containment) Tests The following items shall be tested quarterly at intervals not to exceed four months:

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' 1) All ventilation isolation dampers close in less than 5 seconds in response tp both manual trip and simultaneous alarm signals from the Buiiding Gas and Bridgo Monitors. ,

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2) The Control Systems maintain negative pressure in the building unde (normal

! and emergency conditions.

• 84 Other instrumentation System Surveillance The following addhional instrumentation systems shall be calibrated or tested quarterly at intervals not to exceed four months:

1) Pool Temperature Monitor

2) Suction Valve Closed pump inhibit interlock.

These specifications shall not apply if there is no fuel in the reactor tank.

Specification 2) shall not apply if the reactor tank water primary circulation pump is permanently disabled or electrically disconnected.

l 8.5 Reactor Fuel Shielding Water Monitoring Applicability These specifications apply to the surveillance and quality of reactor l tank water and are in effect so long as there is fuel in the reactor tank. These specifications similarly apply to any other on site fuel storage facilities for willen water is in contact with the Reactor Fuel.

Obiective The objective of these specifications is to ensure that water quality is measured frequently enough to prevent excessive corrosion of the system components cad to detect higher than normallevels of radioactivity in the system water.

Specifications I

1) System water pH, conductivity and gross Beta activity shall be measured  :

I weekly, at intervals not to exceed 10 days. l l 2) Gamma Spectroscopy of the system water shall be conducted three times per l year at intervals not to exceed five months.

3) Records shall be maintained of all pool water additions. I l Bases i

l Specification 8.5.1 ensures that poor water quality would be detected in a timely i

manner.

Specification 8.5.2 ensures that fuel leakage or excessive corrosion may be detected.

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Specification 8.5.3 provioss a m3ans to monitor for excessive water addition ratss, which could be indicative of system leakage.

9.0)lant Design Features '

9.1 Site Description The site of the BMRC reactoris the South East corner of the South campus of,the ,

State University of New York at Buffalo.

The South campus lies in a triangle bounded by Bailey Avenue, running almost due north and south, Winspear Avenue, running roughly east and west, and Ntain St.,

running north of Winspear Avenue. The nearest buildings are Acheson Hall, Howe Building, the McKay steam plant, and Clark Gym. A large Veterans Affairs Medical Center is situated approximately 2000 ft east of the BMRC. The nearest residential area is South of the reactor on the North Side of Winspear Avenue.

The reactor restricted access area consists of the containment building and the attached laboratory and office wing.

9.2 Containment Building The containment building is a flat roofed, right circular cylinder, nominally 70 ft. in diameter and 52 ft. high. The containment is constructed of normal density reinforced concrete. The 'valls are nominally 2 ft. thick and the roof is 4 inches thick and supported by steel and concrete beams. The bottom floor is nominally 3.5 ft.

thick and the entire building rests in bedrock. The total free volume of the building is approximately 186,000 cubic feet.

The building is equipped with two personnel airlocks and a single barrier " truck door". All electrical and piping penetrations are sea'ed. Drain lines which penetrate the containment wall are provided with 24 inch dip legs to maintain pressure seat.

9.3 Ventilation Systems Under normal conditions, the containment building is ventilated by a single p, ass system. Conditioned air is supplied to the containment through a 30 inch diameter duct. A second 30 inch supply system can also be employed, however, it is not necessary under most conditions.

Air from the general (occupied) areas of the containment, and certain low activity fume hoods, is exhausted through a 36 inch duct which penetrates the containment roof (commonly referred to as the " Building Air" system). The Building Air exhaust system is HEPA filtered and includes a vortex control damper on the suction side which is used to control the negative pressure in the containment building.

The reactor irradiation facilities and the high level fume hoods exhaust through an 18 inch duct which discharges at the top of the McKay power plant chimney (the

" stack exhaust"). This release point is 167 feet above ground. The stack exhaust may be driven by two blowers which operate in series, one of which is located in the BMRC sub basement, while the other is located at the power house. For routine radioactive materials handling op,erations, only the stack fan located in the power house is required to provide adequate flow.

PAGE 12 Amendment No. 24

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All cir which exhrusts though tha cont inm:nt cxhaust systems is HEPA filt*r:d. l l The~two 30' supply ducts, the 18" exhaust duct. and the 36" exhrust duct cra 1 equipped with "Pratt" hydraulic isolation dampers which:can be manually or l automatically triggered if high airborne radioactivity is detected.  ;

When the isolation dampers are closed, all fans in the containment and the basement stack exhaust fans, automatically turn off. The fan in the power house i remains on. Under these conditions the containment is maintained at a negative pressure by exhausting air through a 6" emergency bypass duct which is equipped

, with a HEPA filter. A second bypass damper in the power plant allows additional non-contaminated air to enter the duct on the suction side of the blosuer. This air provides dilution and prevents excessive negative pressure in the exhaust line. ,

9.4 ReactorTank The reactor tank is constructed of concrete with an aluminum liner. It is nominally 29 feet deep and will hold approximately 13,700 gallons of shielding water. When the reactor was in operation, the cooling system also included an N-16 delay tank, a heat exchanger and a circulating pump. The Heat Exchanger was permanently removed in 1994 and replaced with a pipe. Tne balance of the original cooling system can be used to circulate the shielding water, and to provide flow for the demineralizer system. However, these cornponents are no longer required and provide no safety functions. They may be removed without impacting upon reactor safety, as long as blocking flanges are installed outboard of the isolation valves.

Two demineralizer systems are required. One provides new "make up" water to replenish losses. The second is a " clean up" system used to maintain the quality of the water in the reactor tank. The clean up system and make up water addition system may be connected to the tank through the formerly utilized coolant circulation loop, or alternatively may be directly coupled to the reactor tank.

An emergency pool fill system is available for adding city water to the pool should this be desired, such as in the event of a gross leak in the tank. This system includes a manual valve at the top of the tank and an isolation valve in the BMRC sub-basement.

9.5 Reactor Fuel Fuel Assemblies are 3.15 by 2.74 inches in cross section and 38 inches high. Each assembly contains 25 fuel elements in a 5 x 5 array. The pins are positioned by aluminum gnds at each end, these grids each contain 25 holes 1/4 inch in diameter which were used for coolant passage. The lower end of the assembly includes an aluminum nosepiece that mates with holes in the reactor grid plate. The top of the assembly contains a bail for handling purposes. The vertical box itself is constructed of .060 in thick Zircalloy.

Each fuel element is made up of a Zircalloy cladding tube (.47 in OD) with a .0185 inch thick minimum wall. Each element contains 40 sintered UO-2 fuel pellets.

Welded caps form the closure of the cladding tubes. The fuel pellets are 0.42 l

inches in diameter and have a minimum density of 10.2 g/cc. Nominal enrichment is 6.0% The fueled height is nominally 24 inches PAGE 13 Amendment No. 24

Typical initial (cold /cisan) composition of a fusi assembly was:

Uranium 235 .. . ..... 0.768 Kg Uranium.... ... 12.83 Kg Uranium Dioxide... . 14.56 Kg e

Complete Fuel Assembly . 20.37 Kg Table 1 lists the irradiated fuel assemblies which were located within the reactor -

tank on June 30,1994 and their respective bumups.

9.6 Control Blades Gross reactivity control within the reactor core was provided by six controtblades of which five were scramming and one was not. Each blade is composed of nominally 80% silver,15% indium and 5% cadmium. The blades are 4.85 inches wide, by 0.18 inch thick, by 29 inches long and are plated with 0.003 inches of nickel.

Because the number of fuel assemblies stored on the gridplate is limited to fifteen, the control blades are not required to prevent criticality. Therefore, they may be disconnected from their drive units and there are no restrictions on their position.

10.0 Fuel Storage and Transfer * -

10.1 Cold Fuel Storage I

Applicability These specifications apply to the storage of cold reactor fuel (see definitions).

Objectives The objectives of these specifications are to maintain the fuelin a suberitical configuration, to deter the theft or diversion of the fuel, to detect such diversion should it occur and to prevent excessive exposures of personnel and the public from radiation arising from the fuel.

Specifications l 1) Cold fuel shall be stored within the containment building, in secure vaults, constructed of nonfiammable materials. Fuel shall be stored in rows of metal l

cylinders which have a minimum center to center spacing of five inches and the rows shall have a minimum center to center spacing of 16 inches. Each cylinder shall contain no more than 25 fuel elements. Those fuel storage vaults which were in use on June 30,1994, shall continue to be exempted from the criticality alarm requirements of 10 CFR 70.24.

2) Altematively cold fuel which has been packaged for shipment in accordance with NRC and DOT requirements may be stored within a locked room within the BMRC containment building, provided that appropriate administrative controls are instituted to prevent the introduction of the fission plate, or isotopic neutron sources within one meter of the packages.

Et Storage of the BMRC Fission Plate Applicability These specifications apply to the storage of the BMRC fission plate.

PAGE 14 Amendment No. 24

. - . - . - - - . . . _ - - . . _ ~ _- . . - . - . -

Obiective Tha obj::ctives of thasa specifications cra to prevent ths unsifs n:utron coupling of th3 fission plate with oth:r fissile materials, to deter the theft or diversion of the fission plate, to detect such diversion should it occur, and to prevent excessive exposures of personnel and the public from radiation arising from the fission plate Specifications

1) The Fission Plate may be stored within the fuel vault (s), a locked cask within the containment building, or within the dry chamber or thermal column. A minir,num distance of 16 inches shall be maintained between the fission plate and any other fissile material.

2) Altematively, the fission plate may be stored within a shipping containpr, within the containment building, in accordance with NRC and DOT regulations provided that appropriate administrative controls are instituted to prevent the  ;

introduction of other fissile materials, or isotopic neutron sources, within one meter of the package.

10.3 Irradiated Fuel Storage and Transfer l

Applicability These specifications apply to the storage and transfer of the irradiated '

fuel, which shall be limited to that fuel which was present within the reactor tank on June 30,1994.

Objectives The objectives of these specifications are to maintain the fuelin a

suberitical configuration, to deter the theft or diversion of the fuel, to detect such diversion should it occur and to prevent excessive exposures of personnel and the public from radiation arising from the fuel.

Specifications

1) Irradiated reactor fuel shall be stored within the reactor tank, the Hot Cell, or within altemative fuel storage facilities in accordance with Section 10.3.3. All fuel elements will be stored within the standard PULSTAR fuel assembly hardware, or within closed canisters of similar dimension, which may contain no

- more than 27 elements each. If canisters contain more than 25 fuel elements, (the number of fuel elements in a standard fuel assembly) the Reactor Decommissioning Safety Committee must approve the container design, I

, loading, storage and handling procedures.

I 10.3.1 Storage within the Reactor Tank

1) Up to 15 fuel assemblies may be stored on the grid plate in attemate rows.

Unused grid plate locations will be plugged to prevent storage of more than 15 assemblies. I e

2) Within the reactor tank, fuel may be stored in the existing pool storage racks. ,

The storage racks are in linear array with a minimum center to center spacing of l five inches.

3) Additional fuel storage racks may be installed within the reactor tank so long as they provide equivalent subcriticality margin, mechanical strength and seismic performance. -

4 PAGE 15 Amendment No. 24

() During fu:1 tr:nsf r or loading oper:tions, up to two ess;mbli s mny be pl:ced in interim storage racks or holding devices on the pool shelf or Hot Cell pass through tube.

10.3.2 Storage within the Hot Cell

1) irradiated fuel may be stored within the Hot Cell subject to following requirements:

2) Calculated or demonstrated Keff of the storage array must be less than or, equal to 0.85 for the flooded condition.

3) Transfer of the fuelinto and out of the Hot Cell must be in accordance with detailed written procedures, approved by the Operating Committee. ,

4) If more than 374 fuel elements are located within the Hot Cell, it must be equipped with a neutron sensing criticality alarm. (note: 375 fuel elements is equivalent to 15 fuel assemblies)

5) In order to prepare fuel for shipment to a disposal facility, fuel may be manipulated in the Hot Cell such as to load fuel elements into shipping / storage canisters. Written procedures shall ensure that criticality margins are maintained during such manipulations.

10.3.3 Storage Within Altemative Facilities irradiated fuel may be stored within attemative facilities within the containment building subject to the following requirements.

1) Calculated or demonstrated Ken of the storage array must be less than or equal to 0.85 for the flooded condition.

2) Transfer of the fuelinto and out of the Storage Facility (from the Hot Cell or Reactor Tank) must be in accordance with detailed written procedures, approved by the Operating Committee.

3) If more than 374 fuel elements (375 fuel elements are equivalent to 15 fuel assemblies) are located within the storage facility, it must be equipped with a neutron sensing criticality alarm.

4) Shielding must be adequate to reduce the radiation level such that the radiation levels at the outer boundary of the Storage Facility will not create a High Radiation Area as defined by 10 CFR 20.

5) Use of the storage facility must be approved by the Reactor Decommissioning Safety Committee.

6) The facility must be vented to the Stack Exhaust system.

10.3.4 Transfer of Fuel between Fuel Storage Facilities in addition to the requirements of sections 3.2,3.3,3.4 and 4.0, the following additional requirements must be met when fuelis being transferred )etween fuel storage facilities (Pool, Hot Cell, or Altemate facilities)

1) The airlocks an 1 truck door are sealed.

~

2) The containment pressure is negative with respect to outside at'mosphere.

PAGE 16 Amendment No. 24

l l

l 3) Hydraulic pressura is av:ilabla to closs the v:ntilation isolation damp rs.

l 4) Fuel storage canisters, transfer casks, or baskets, shall be:

l

. DOT certified packaging or

. Equipped with bales, handles or lifting lugs and or cables or similar lifting gear which are capable or supporting at least twice the weight of the load in i air. In addition appropriate safety margins will be used in designing such equipment, and

. Shall be designed so that fuel elements or assemblies will not spilfout in the event the load is dropped.

5) The transfers must be conducted in accordance with a Radiation Work Permit approved by the Radiation Safety Officer.

6) A criticality alarm (s) shall be operating in appropriate location (s), if greater than 374 fuel elements are located in the transfer container, unless the container is DOT certified packaging.

7) Items (1),(2), and (3) above ao not apply when handling fuel which is contained in sealed DOT approved canisters or containers.

10.3.5 Fuel Handling within the reactor tank In addition to the requirements of sections 3.2.,3.3,3.4 and 4.0, whenever fuelis handled in the reactor tank the following requirements shall apply: l

1) The airlocks and truck door are sealed.

2) The containment pressure is negative with respect to outside atmosphere.

3) Hydraulic pressure is available to close the ventilation isolation dampers.

4) If fuel assemblies are being placed into a geometric configuration which has not been previously loaded, a neutron count rate monitor shall be operating and monitored.

5) The neutron count rate monitor is not required when fuel assemblies are being loaded into or transferred between the standard fuel racks which were originally installed in the reactor tank, or similar racks installed pursuant to 10.3.1 (2),

which utilize an identical geometry. This would include the transfer of fuel assemblies from the grid plate to the fuel racks.

.11.0 Administration

• 11.1 Organizational Structure l 1) The organizational structure shall be as illustrated in Figure 1.

l l 2) The Acting Director of Environmental Health and Safety Services bears direct l administrative and Safety responsibility for the Facility.

l l PAGE 17 Amendment No. 24

3) Tha BMRC Director bears dir:ct r:sponsibility for til surveill:nc;s, op:rctions, testing and experiments conducted at BMRC.

4) The Radiation Safety Officer bears direct responsibility for all aspects of radiological safety at BMRC and is empowered to stop, or modify any activity for purposes of ensuring the radiological safety of the staff and the public, s) The Operations Manager is responsible for all activities related to safe storage and handling of the reactor fuel, maintenance and testing of plant safety systems and other engineered safety systems, the training and supervisivo of licensed operators and Certified Fuel Handlers. ,

11.2 Minimum StafHng Requirements

~ .

As long as irradiated fuel is stored within BMRC, the University staff shall include at minimum:

1) The Acting Director of Environmental Health and Safety Services

2) The Directorof BMRC

3) The Operations Managerof BMRC

4) The Radiation Safety Officer

5) At least one licensed Sr. Reactor Operator or Certified Fuel Handler.

For purposes of meeting the requirements of 11.2:

1) A single individual may serve as both the BMRC Director and Acting Director of Environmental Health and Safety Services, or a single individual may serve as both Director and Operations Manager.

2) The Operations Manager may be the Senior Reactor Operator or Certified Fuel Handler, provided there is at least one additional licensed Reactor Operator or Certified Fuel Handler on staff.

j 3) Staff members may perform collateral duties in other areas of the University or be part time employees.

11.3 OrcCad Staffing Requirements As long as irradiated fuel is stored within BMRC, the University shall meet the following "on-call" requirements.

1) The Operating Committee will maintain a roster of personnel who are trained in j appropriate aspects of facility operation and health physics.

2) At least one individual from this roster will remain within a 50 mile radius of the facility at all times and be reachable by phone, pager or radio.

11.4 Operational Requirements

1) All fuel handling must supervised or performed by a licensed Sr. Reactor Operator or Certified Fuel Handler. Non-licensed personnel may assist in the conduct of the manipulations, but must receive training commensurate with their level and nature of participation.

2) Alllicensed Operators or Certified Fuel Handlers shall participate in the BMRC l Requalification program or CFH recertification respectively, as a condition of PAGE 18 Amendment No. 24  ;

1 th:ir continued essignm:nt to operator or C::rtifi:d Fuel Htndlir duti;s. The i

Requilificati:n program shall be commensurate and consistent with the current scope and nature of operational activities on site. ,

11.5 Review Functions i 1

11.5.1 Reactor Decommissioning Safety Committee

1) A Reactor Decommissioning Safety Committee (RDSC) shall exist for the i

+

purpose of reviewing matters related to the health and safety of the public'and  !

the staff, in accordance with the Constitution and Bylaws of the committee. )

2) The RDSC shall report to the Associate Vice President for Facilities who shall

appoint the members and Chair. '

3) The RDSC shallinclude at least eight members including as ex-officio members the BMRC Operatiens Manager, BMRC Director, the Radiation Safety Officer, and the Acting Director of Environmental Health and Safety. The BMrtC Director and Operatiens Manager shall be non-voting membe s.

4) The RDSC shall meet at least three times per year. l

5) A quorum of the RDSC shall consist of at least six members, and all questions l before the Committee must be approved by a simple majority of the voting members present, but by not less than four voting members, a) Minutes of all meetings will be maintained on file and distributed to all members.

7) The RDSC shall review and approve the following: t A) The substantive aspects of short and long term action plans relative to the j reactor decommissioning, reactor plant maintenance and monitoring, except  ;

for those which mey be reviewed and approved by the Operating Committee. 4 1

B) Reportable Occurrences related to health and safety, and corrective actions.

C) Notices of Violation related to health and cafety and corrective actions.

D) Applications for amendment to NRC licenses.

E) Changes in Procedures or facilities implemented in accordance with 10 CFR 50.59, in Post Audit, after Operating Committee approval. i 11.5.2 Operating Committee 1

1) An Operating Committee shall exist as a sub-group of the RDSC.  !

2) The Operating Committee shall consist of the ex-officio members of the RDSC plus additional members appointed pursuant to the by-laws.

3) The Operating Committee shall meet as often as required and minutes shall be kept of all formal meetings,

4) The Operating Committee is authorized to act for the RDSC regarding routine  !

occurrences, and approvals for which the safety implications are minor, are well l understood, and are witti:n the scope of past practice. This would include but j not be limited to: . I i

PAGE 19 I Amendment No. 24

~. .

A) Applications for lic:nse or Plan cm:ndmants such as to update nam:s, equipment lists, procedures etc.

B) Operating Procedures, Emergency Procedures, Health Physics Procedures, or Maintenance Procedures.

C) Changes in procedures, equipment of facilities pursuant to 10 CFR 50.59.

D) Audit Reports.

11.5.3 Audits and Reviews .

1) An independent audit shall be conducted annucIly of BMRC decommissioning, maintenance, operations, and surveillance activities. The auditor (s) shall have appropriate experience and education. The audit may be broken into fnodules, using the same or separate auditors. A written report (s) shall be provided to the BMRC Director, and shall be reviewed by the Reactor Decommissioning Safety Committee. The audit shall include at minimum a review of:

. Operational records for compliance witti intemal rules. procedures, policies, regulatory compliance, and license compliance.

. Aduquacy of Procedures.

. Plant equipment Performance and surveillance requirements.

. Records of release and discharges of radioactivity to the environment.

2) Radiation Safety and ALARA Review shall be conducted pursuant to 10 CFR 20 requirements.

12.0 'Act' ions To - e Tpken in the Event of a Reportable Occurrence A reportable occurrence shall be any of the following:

1) Release of fission products from a leaking fuel element.

2) An uncontrolled or unplanned release of radioactive materials from the restricted

area of the facility which when averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period exceeds the i applicable limits established by 10CFR20 or Technical Sp.Bications, whichever

~

is greater.

3) An uncontrolled or unplanned release of radioactive matenals that results in concentrations of airborne radioactive materials within any portion of the restricted area which results in measured or calculated exposures to personnel in excess of 40 DAC-hours.

4) Decbration of an Emergency pursuant to the BMRC Emergency Plan.

5) An observed inadequacy in the implementation of administrative or procedural controls that caused or threatens to cause the existence or development of a immediately dangerous or otherwise significant unsafe condition in connection with the operation of the facility, in the event of a reportable occurrence, as defined above, the following shall occur:

l 1) Immediate steps shall be tak'en to correct the situation and to mitigate the I

consequences of the occurrence.

1 PAGE 20 Amendment No. 24

2) Ths Op:rcting Committre will investigata the occurrence and its caus:s, and will report its findings to the Reactor Decommissioning Safety Committes and to the Senior Vice President, and Associate Vice Pre ,ident for University Facilities.

3) A report shall be filed with the NRC which shallinclude an analysis of the causes of the occurrence, the effectiveness of corrective actions taken and recommendations of measures to be taken to rnvent or reduce the probability or consequences of recurrence.

13.0 Written ProcedureP ,

1 13.1 Required Procedures ,

Written procedures will exist that define how and when various aspects of facility 1

operations will be performed. These procedures may include " Operating i Procedures",

• Emergency Procedures" and " Maintenance and Calibration  ;

Procedures."  !

Written procedures shall at minimum address the following areas: j i 1) Fuel Handling Operations, f

2) Use, surveillance, and maintenance of auxiliary systems. l

3) Abnormal and emergency situations. l

4) Required reactor electrical and mechanical surveillance and maintenance.

5) Operation and calibration of fixed radiological monitors as required by this l

Technical Specification.

I 13.2 Approval, Review and Update l 1) Operating Procedures and Maintenance and Calibration Procedures will be reviewed and updated as appropriate, but such review shall be no less frequent than once every two years.

! 2) Emergency Procedures shall be reviewed and updated in accordance with the l i BMRC Emergency Plan.

I 3) All new or revised procedures sha!! be approved by the Operating Committee.

i 13.3 Temporary Deviation from Wntten Procedures Temporary changes to written procedures that do not change the original intent may j be made with the approval of a Sr. Reactor Operator, the Operations Manager, or the Director. All such changes shall be documented.

PAGE 21 Amendment No. 24

14.0 Record Keeping 14.1 Records Which Shall be Retained for Rve Years in addition to the requirements of applicable regulations, the following records and logs shall be maintained in a manner reasonably convenient for review, and retained for at least five years:

. Operation and Maintenance Logs and records

. Records and reports related to " reportable Occurrences" as defined by sedion 12.

. Logs end records which document the conduct of test, checks, and measurements in comoliance with surveillance requirements established by Technical Specifications

. Records of experiments performed

. Operator Requalification progrsm records

. Facility radiation and contamination surveys

. Minutes of Operating Committee meetings

. Pnncipal Maintenance records 14.2 Records Which Shall be Maintained for the t.ife of the Facility f

The following records shall be maintained for the life of the facility;

. Records of radioactive materials discharged to the air or water (sewer)

. Radiation exposure records for all facility personnel

. Fuel inventories and transfer records

. U;xiated, corrected, and as-built facility drawings

. Mir.utes of Reactor Decommissioning safety Committee, (formerly the Nuclear Safety Committee) Meetings l

. Off Site environmental radiation monitoring surveys 15.0 Reporting Requirements 15.1 AnnualTechnical Report A report summarizing technical operations will be prepared for each calendar year.

A copy of this report snall be submitted to the Director , Office of Nuclear Reactor Regulation, with a copy to the Regional Administrator (Region 1) by March 31 of each year. The report shall include the following:

1) A brief narrative summary of changes in facility design or performance that relate to nucicar safety and results of surveillances tests and inspections.

2) Discussion of major maintenance operations performed during the period including the effects if any ora nuclear safety and the reason for any orrective maintenar$ce required.

PAGE 22 l

Amendment. No. 24

3) A brief description of any changes in the facility to the extent that it changes a description of the facility in the Safety Analysis Report.

4) A brief review of changes test and experiments made or conducted pursuant to 10 CFR 50.59 including a summary of the e,afety evaluation of each.

5) A summary of the nature and amount of radioactive effluents discharged or released to the environment.

s) A description of environmental radiological surveys conducted outside the facility.

7) A summary of radiation exposures received by facility personnel and visitors, including details of any unusual exposures.

s) A summary of the results of radiation and contamination surveys perfonned within the facility, s) Any changes in facility organization.

10) A discussion of major operaticas performed during the reporting period related to decontamination, dismantling or decommissioning of the facility.

15.2 Reportable Occummco Reports 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 or facsimile, to the NRC Operations Center and Region I, fulowed by a wntten report within 14 days to the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, ATTN: Document Control Desk, with a copy the Regional Administrator of Region I, in the event of a ,

reportable occurrence as defined by technical specification. The written report, and j to the extent practicab:e, the initial notification, shall: '

1) Describe, analyze, and evaluate safety implications.

2) Outline the measures taken to ensure that the cause of the condition is determired.

3) Indicate the corrective action taken to prevent repetition of the occurrence, including changes to procedures.

4) Evaluate the safety implications of the incident in light of the cumulative experience obtained from the report of previcus failure and malfunction of similar systems and components.

15.3 Sofety Event Reports A written report shall be forwarded within 30 days to the U.S. Nuclear Regulatory Commission, Washington, D.C. 2r 55, ATTN: Document Control Desk, with a copy the Regional Administrator of Reg ' in the event of:

1) Discovery of any substantial errors in the transient or accident analysis or in the methods used for such analysis as described in the Safety Analysis Report or in the basis for Technical Specifications

2) Discovery of any substantial variance from performance specifications contained in the Technical Specifications or Safety Analysis Report.

I PAGE 23 Amendment No. 24

L

3) Discovery of any condition involving a possible single fa. lure which, for a system designed against assumed failure, could result in a loss of the capability of the system to perfomi its safety function.

15.4 Special Nuclear Materials Status Reports Matenals status reports and nuclear materials transfer reports for special nuclear material. shall be made in accordance with applicable section of 10 CFR 70.

t PAGE 24 Amendment No. 24

. Table 1-Fuel Assemblies in Reactor Tank as of June 30,1994 Assembly Number Bumup (MWD / Tonne U) 1 17470.38 2 14606.14 3R 12189.11 .

4R 14751.23 5 16160.89 6 14918.24 '

7 18104.11 '

8R 14906.87 9R 13633.79

, 10 18917.42 11R 16163.94 12R 13S78.76 13 19523.86 14 18875.81 15 19030.08 16 18265.14 17R 13443.08 18R 10555.88 19R 10769.17 20R 10700.76 21R 5176.49 22R 14929.68 23 16540.68 24 14025.08 25R 14868.15 1 26R 11690.76 l 27R 15897.91 l 28 19352.25 ,

29R 9203.55 30R 10329.85 31R 1826.54 32 18525.83 33R 1578.72 34R 332.30 36R 6620.32 37 15625.35 38 15833.18 40 12943.25 42 16904.13 Can #25 > 10000 PAGE 25 Amendment No. 24

Figure 1 Senior Vice President -

V Associate Vice President Reactor Decommissioning for University Facilities 4 Safety Committee V

Acting Director Environmentai Health & Safety V

Director Y Buffalo Materials Research Center Radiation Safety Officer '

-V Operations Manager ,

Buffalo Materials Research Center D V '

V V Operators / Buffalo Materials Research Center Radiation Protection Services Certified Fuel Handlers Health Physics Staff Campus Staff

^

f V '

[ Campus ,

l Environmental Health & Safety

? g Pragram  ;

y Effective March 1,1997

__ . _ _ _ _ _ . . _ _ _ _ _ _ . ._ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ ,.