ML20148C793
| ML20148C793 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 10/12/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148C775 | List: |
| References | |
| R-028-A-025, R-28-A-25, NUDOCS 7811020146 | |
| Download: ML20148C793 (2) | |
Text
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- g NUCLEAR REGULATORY COMMISSION wAsHINoTON, D. C. 20066 GE' UNIVERSITY'0F'MICFIGAN eDOCKET'NO.~50-2 FORD NUCLEAR REACTOR AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No R-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by The University of Michigan (the licensee) dated June 27, 1977 and August 25, 1978, as supplemented June 12 and September 13, 1978, comply with the standards and re-quirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assu*ance (1) that the activities authorized by this amendment can be.:onducted without endangering the health l
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will r.ot be inimical to the comon defense and security or to the health and :;afety of the public; E.
The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required s:nce it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2),
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' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. R-28 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, are hereby incorporated in the license. The licensce shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12, 1978 l
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8 ATTACRMENT'TO LICENSE AMENDMENT NO. 25
' FACILITY LICENSE NO.~R-28 DOCKET NO. 50-2 Replace existing pages 18, 27, 35 and 37 of the Technical Specifications contained in Appendix A with the attached revised pages 18, 27, 35 and
- 37. The changed areas on the revised pages are shown by marginal lines.
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TABLE 3.2 REQUIRED SAFETY RELATED INSTRUMENTATION l
Minimum Number i
Instrumentation Setpoint Required Function
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Linear Level Channel As Required 1
Linear power level measurement and input for the automatic i
control mode I
Power Level Deviation Interlock 95% of control 1
Return reactor to point setting manual control mode if setpoint is reached Reactor Coolant Inlet Temperature Not Applicable 1(a)
Provide information for the heat balance f
determination t
Facility Radiation Monitor
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System (b)
- 1. Building Air Exhaust 1 (1) mr/hr 1
Alarm, scram, initiate confinement evacuation
- 2. Reactor Bridge 30 (50) mr/hr 1
Alarm
- 3. NW Column 10 (50) mr/hr 1(c)
Alarm
- 4. N Wall 5 (50) mr/hr 1(c)
Alarm-
- 5. NE Column 2 (50) mr/hr 1(c)
Alarm
- 6. Hot DI 20 (50) ar/hr 1(c)
Alarm I
(a) Not required for natural convection operation.
l (b) The Facility Radiation Monitoring System consists of 7 radiation detectors which alarm and read-out locally, and are recorded in the control room. The normal setpoints for this system are shown. The value in parentheses is the maximum setpoint which uill be used depending on local conditions. Use of higher than normal setpoints will require approval of the Reactor Manager or the Assistant Reactor Managet. Any reactor staff member may adjust a setpoint lower than the normal value.
(c) Of the detectors labelled 3-7, any one unit may be out of service for a period not to exceed 7 days w1thout requiring reactor shutdown or replacement by a locally alarming monitor with similar range.
Should a second of these units require repair, such repair must be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or reactor shutdown or replacement of the second unit with a locally alarming monitor of similar range is required.
l
' Amendment No. 25 7
. In the radiography of explosives, the explosive devices will be contained, during exposure, inside a blast-proof box which will be located above the pool at the end of the beam tube. The box will not be coupled to the beam tube and will be constructed to fully contain any blast effects or missiles which might be generated by an accidental detonation.
Specifications 3.8.e and 3.8.f conform to the Regulatory Position put forth in Regulatory Guide 2.1 issued November 1973.
3.9 FISSION DENSITY LIMIT APPLIC BILITY This specification applies to fission density limits in FNR fuel.
OBJECTIVE To prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products.
SPECIFICATION 21 a.
The FNR fission density limit shall be 1.5 X 10 fissions /cc.
BASES l
The fission density limit is below operational fission densities reached in other operating reactors using the same kind of fuel without failures attributed to the fuel.
An experimental data base which supports the safe use of UA1 fuel in the FNR up to the fission density was deriv!d and U 038 from irradiation tests performed in the Materials Test Reactor (ICR), the Engineering Test Reactor (ETR), and the Advance Test Reactor (ATR) at the Idaho National Engineering Laboratory, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, and the German Karlsruhe FR2 reactor.
l Amendment No. 25
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' b.
The contents of every tank rwieased shall be sampled and evaluated prior to its release.
BASES Experience with the counting equipment used in measuring the radioactivity in the waste tanks suggests that the above period is a suitable calibration frequency.
4.8 FISSION DENSITY LIMITS N CABILITY This specification. applies to the surveillance requirements for fission density 1haits.
OBJECTIVE To assure that the fission density limits of Specification 3.9 are not exceeded.
SPECIFICATION a.
The fission density of all fuel elements which have Uranium-235 burunp shall be calculated at least quarterly.
BASES Determination of fission densities on a quarterly basis will ensure that the fission density limics of Specification 3.9 are not exceeded. Fuel element swelling will be kept well below levels which could result in clad ruptura and release of radioactive fission products.
Amendment No. 25 i
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5.2 REACTOR FUEL The fuel elements shall be of the MTR type, consisting of plates a.
containing uranium-aluminium alloy, uranium aluminide (UAl ), or x
uranium oxide (U 0 ) fuel (uranium enriched in the isotope U235).
38 clad with aluminium. There shall be eighteen fuel plates containing 140 (t 2%) grams of uranium-235 in the standard fuel elements, and nine fuel plates containing 70 (+2%) grams of uranium-235 in the con-trol room fuel elements. Partially loaded fuel elements in whidh some of the plates do not contain uranium may be used.
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b.
Standard, aluminum clad elements with 10 fuel plates containing up to 169 (+ 2%) grams of uranium-235 in the form of uranium-
- aluminum allow may be utilized up to a maximum reactor power of 4
1 megawatt. Ten-place elements may be intermixed with 18-plate elements in the enre. Reactor scram setpoints will be set at 1.2 megnwat,ts when the 10-place elements are in use.
5.3 REACTOR BUILDING The reactor building is a vindowless, four story, reinforced concrete building with 12 inch walls structurally integral with the footings and foundation macs. The building is approxi=ately 69 f eet vide x 68 feet long x 70 feet high with approximately 44 feet exposed above grade. The building has the following general f eatures:
a.
The reactor is housed in a closed room designed to restrict
- leakage, b.
The reactor room is equipped with a ventilation system designed to exhaust air or other gases present in the building atmosphere into the inlet air region for the building cooling tower which exhausts a minimum of 45 feet above_ ground level.
c.
The ventilation system protides ventilation for certain storage and experimental facilities and exhaust these a minimum of 54 feet above ground level.
d.
The openings into the reactor building are the equipment access door, the personnel doors, the equipment access hatch, the air intake and exhaust d'icts, the room 3103 fume hood exhaust duct, the beam port vent 21. tion duct, the north wall door, the door between the hot cave operating face and the beam hole floor, and the pneumatic system for sample transfer between the TNR and several laboratories in the Phoenix Memorial Laboratory.
5.4
_ FUEL STCRACE a.
Irradiated fuel elements and fueled devices shall be stored in
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an array which will permit suf fieledt natural convection cooling Amendment No, jtI,15 O
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