ML20148D808
| ML20148D808 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 10/13/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148D805 | List: |
| References | |
| R-028-A-026, R-28-A-26, NUDOCS 7811060015 | |
| Download: ML20148D808 (7) | |
Text
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- o;[n%,1 UNIT E D ST ATES 7
NUCLEAR REGULATORY COMMISslON 3
A.I. f W ASHINGTON, D. C. 205SS Ne y/ '/
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THE UNIVERSITY OF MICHIGAN DOCKET NO. 50-2 FOR_D NUCLEAR _ REACTOR AtjENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. R-28 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by The University of Michigan (the licensee) dated June 27, 1978, as supplemented September 14 and 28,1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulatiot.o; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required since 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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m 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) lows:of facility Operating License No.__R-28 is hereby amended to read as fol
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(2) -echnical Specifications The Technical Specifications contained in Appendix A, as ~
' revised through Amendraent No. 26, are hereby incorpor-ated in the license.
The licensee 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 TWCLEAR REGULATORY COMMISSION
'O
' j -< A,h ! a '~s,, '
l g'obertW.Reid, Chief R
Operating Reactors Branch f4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 13, 1978 O
e
ATTACHMENT TO LICENSE AMENDMENT NO. 26
~
FACILITY OPERATING LICENSE NO. R-28_
DOCKET NO. 50-2 Replace existing pages 10, 17, 37 and 38 of the rechnical Specifications contained in Appendix A with the attached revised pages 10, 17, 37 and 38.
The changed areas on the revised pagc, are shown by a marginal line.
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- beight of water above the top of the core (H), and core exit t
temperature (T,).
OBJE'CTIVE To assure that automatic protective action is initiated to prevent a safety li:1: being exceeded.
_ SPECIFICATION-The limiting safety systen settings for reactor thereal power a.
(?), prinary crolant IIcw through the core (W), height of veter above the top cf the core (H), and reactor coolant exit terperature (T,) shall be as follows:
Varhble
_LSSS 2.4 Mw or 1.2 Mw (See Spec. 5.2)
P (Max.)
V (Min.)
900 gpa H (Min.)
19 Teet 129 T T, (Max.)
BASES The 11=iting saf ety syster sc: tings specified above have been chosen j
auteratic pretective action will correct the cost to assure th::
severe abner'nal situatio: an:icipated before a safety limit is exceeded. The safety ca: gin that is previded between the LSSS and the SL also allcws icr :he cost adverse ceabination of instrument uncertainties associa:cd with reasuring the above observable uncertaintics include a power level par ace t e r s.
These instrutent variabic of five percent, a pool water icvel varisticn of six and a core inlet tecpera-inches, a flow varis: den of ten percent, These values were chosen ture variation cf rwo degrees Fahrenheit.
to be conservative.
With Tigure 2.2 shows the basis for selection of these LSSS values.
9 and a possible pcwer Ocasurecent a LSSS for reactor power of 2.4 !.
the true value of thersal power could be 2.52 Mw.
errer of 5 percent, temperature Auto-Eundown functien setpoint With the raxi ue exit of 129'T, the true value of the taximum te=perature could be 131*T.
cc rinntion of true value of' inlet temperature Figure 2.2 shcws the and core flow rate at which the manicum fuel plate temperature of the " bot channel" reaches the boiling point te perature of the coolant.
It also shows the true value of coolant inlet tecperature bN AtnendmentNo.[,26
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TABLE 3.1 REQUIRED SAFETY CH/2:NELS Minimum Munber Channel Setpoint Required Tunction Log Count Eate 2 cps 1
Rod Withdrawal Interlock 1
Wide range power level Log N-Period and input for period scra:
Period Safety 5 see 1
Scra:
Level Safety 120% (2.4 Mw or 2
Scra:
1.2 Mw)**
High Pcver/
(a) 900 gp 1
Scram 3,100 Kw No Water Flow (b) hold-up tank isolation valve l
not fully open (c) hold-up tank static pressure l
1 psig below f
full power valu e i
High Fever /
1 Scram 2,100 Ku Header Down Beader Up/
No Water Flea 900 spa 1
Scram Building Exhaust Radiation Level 1 cr/hr 1
Scram Euilding Alarm i
l Fbnual Switch 1
Scram Manual Scra: Switch 1
Scram f
1 Scram i
Magnet Power Keyswitch Reactor Coolant l
Exit Terp.
129'T 1-Auto Rundown Pool' Level 1 foot below pool 1
Auto Rundown i
overflow Iridge Not Clamped When clamps released 1 Scram i
Values listed are limiting setpoints.
For operational convenience, setpoints may be changed to core conservative values.
- See Specification 5.2 for setpoint depending on reactor fuel.
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Amendment No. 26 L
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e
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r 5.2 REACTOR FUEL The fuel assemblies shall be of the MTR type, consisting of plates containing uranium-aluminium alloy, uranium aluminide (UA1 ), or x
uranium oxide (U 0g) fuel (uranium enriched in the isotope U235),
3 clad with aluminium. Partially loaded fuel assemblies in which some of the plates do not contain uranium may be used.
The authorized fuel assembly designs are:
No. Fuel Plates Grams of Uranium-235_
18 140 + 2%
9 70 + 2%
10 169 + 2%
The 9-plate fuel assembly shall be used in all loadings for the control rods fuel assemblies. The reactor power level and scram setpoints for authorized core loadings shall be:
Fuel Loadinc Power Level LSSS Normal 18 plate core 2 Mw 2.4 Mw Fringe
- 18 or 10-plate with 2 Mw 2.4 Mw center of 18-plate core Intermixed (nonfringe*) 18 and 10 fuel plate core 1 Mw 1.2 Mw west and south locations
- Fringe fuel assemblies are those in east, L5, L6, L7, L8, L9, L10, L20, L30, L40, L50, L60, L70, L75, L76, L77, L78, L79 and LBO.
es.4 4
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/sendmentNo,h,h,26 N
5.3
_31 ACTOR BUILDING The reactor building is a vindoviess, four story, reinforced concrete building with 12 inch walls structurally integral with the footings and foundation cats. The building is approximat'ely 69 feet wide x 68 feet ler.g x 70 feet high with approximately 44 feet exposed above grade. The building has the f ollowing general f eatures:
a.
The reactor is housed in a closed room designed to restrict
?.e aka ge,
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 f eet above ground level.
c.
The ventilation system provides 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 ducts, the roon 3103 fume hood exhaust duct, the beam port ventilation 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 FNR and several laboratories in the Phoenix Memorial Laboratory.
5.4 FirEL STORACE a.
Irradiated fuel elecents and fueled devices shall be stored in an array which will permit suf ficient na tural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed 100*C.
b.
All reactor fuel elements and fueled devices shall be stored in a geccetric array which assures suberiticality.
The array spacines will be based on the experimental results reported in OENL-C7-55-9-;D for storage array' e>:periments performed with ORR and IST fuel elements Amendment No.26 L
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