ML20059M308
| ML20059M308 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 10/27/1993 |
| From: | Fleming R MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | Michaels T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20059M309 | List: |
| References | |
| NUDOCS 9311190024 | |
| Download: ML20059M308 (8) | |
Text
i University of Michigan Michigan Memorial-Phoenix Project Office of the Director Ann Arbor, Mich2gan 48109-2100 a
Oc.ober 27, 1993 Docket 50-2 License R-28 United States Nuclear Regulatory Commission Document Control Desk Attn: Theodore S.
Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V,
and Special Projects Office of Nuclear Reactor Regulation Washington, D.C.
20555 i
Re:
Ford Nuclear Reactor License and Technical Specifiestions, Amendment 40 Ford Nuclear Reactor Safety Analysis, Revision 2 Implementation of 10CFR20 Effective January 1, 1993 General Update of Safety Analysis i
Dear Mr. Michaels:
j
)
The University of Michigan hereby submits the Amendment 40 to j
the Ford Nuclear Reactor License and Technical Specifications and Revision 2 to the Ford Nuclear Reactor Safety Analysis.
Amendment 40 accommodates the implementation of the new 10CFR20 as does Revision 2.
In addition, Revision 2 incltdes a general update of several sections of the Safety Analysis.
t' The changes to the License and Technic.
Specifications currently under your review in Amendment 39 are _ t included with this submittal.
All changes are delineated with the amendment or revision number in the right margin, and they are underlined (in red on the original).
In a few cases, the number next to a blank line indicates deletion of a line or section that is no longer applicable.
Sincerely
/GA<As Rbnald F.
Fleming
]
Director j
Michigai
..orial-Phoenix Project 1
9311190024 931027 f'
1 PDR ADOCK 05000002
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P PDR t
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' t Theodore S.
Michaels October-27,--1993 pace Section Description License' l
t 2
c.(2)
Change Amendment 39 to Amendment 40.
Technien1 Specifications
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4 1.0 In reportable Occurrence Nurber 6, proper reference in the new 10CFR20 inserted.
l 19 3.5.1 Proper reference in the new 10CFR20 inserted.
i 21 3.6.1 Release to Sewers definitions made consistent with new 10CFR20.
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1 21 3.6 Waste water is normally recycled as make-up to the
~j Bases reactor pool, but.the option to discharge to the i
sewer is maintained.
i 29 4.6.1 Waste water monitoring instruments calibrated only when waste water is to be discharged to the
~j sewer.
t 30 4.6 Waste water is normally recycled as make-up to the j
Bases reactor pool, but the option to discharge to the sewer is maintained.
i 31 5.1 Updated concerning apartment construction to the north and south of the University's North Campus.
31 5.1 Updated.to rei
- ct current _cnaracter of the j
University's North Campus.
A raw information center and headquarters for the Dean of Engineering will be i
built within 500 feet of the reactor, but will not contain any housing facilities.
i 1
32 5.3.4 Sealed tile drain to cold sump added to list of
-j openings into the reactor building, j
41 6.6.1.f.1.a.1.
Changed to " total gaseous radioactivity" to make the paragraph generic and all encompassing for any type of gaseous activity.
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i Theodore S.
Michaels L
October 27, 1993
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l Page Section-Description l
l 42 6.6.1.f.1.a.2.
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l Gaseous release concentrations, which are totally l
argon-41, are averaged over one year.
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i 42 6.6.1.f.1.a.4.
l Updated to reflect new 10CFR20.
l 42 6.6 1.f.1.b.
4 I
I Iodine releases evaluated only if iodine-131 is i
" consistently" identified in the primary coolant to indicate a fission product leak.
Iodine-131 is occasionally foond in very low levels in the coolant.
1 42 6.6.1.f.1.b.1.
l Simplified the wording without changing the intent.
l 42 6.6.1.f.1.b.2 1
Updated to reflect new 10CFR20.
42 6.6.1.f.1.c.1
" Particulate" added because section deals specifically with particulate activity.
42 6.6.1.f.1.c.2 Gross alpha activity measurement required only when the experimental program is " expected" to result in the release of alpha emitters.
42 6.6.1.f.1.c.3 Samples are counted within two weeks of sample collection.
42 6.6.1.f.1.c.4 Updated to reflect new 10CFR20.
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43 0.6.1.f.2.a.
Modified to cover releases to the unrestricted area j
and to.the sanitary sewer.
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l Theodore S. Michaels.
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. October 27, 1993-l Engg section Description j
l 43-6.6.1.f.2.b.
.q Changed "the unrestricted area" to " unrestricted l
areas".
43 6.6.1.f.2.c.
j
- i Changed "the unrestricted area" to " unrestricted areas".
-F Alpha releases evaluated only if the experimental l
program is " expected" to result in'the release of alpha emitters.-
43 6.6.1.f.2.f.
l t
Reference to a specific 10CFR20 concentration limit i
has been deleted.
1 i
43 6.6.1.f.2.g.
i Updated to reflect new 10CFR20
-l 44 6.6.1.g.3.
l Eliminated highest and lowest concentration f
measurements because the environmental monitors are
.i scarcely above background.
The values reported are already from the point with the highest average concentration.
44 6.6.1.g.5.
Updated to reflect new 10CFR20.
percentage uptake levels increased from 1 % to 50 %
f of 10CFR20 limits.
Ten percent is a more reasonable trigger point for accurate measurement of i
environmental monitors and for evaluation.
i i
i Safety Analysis l
2 2.1 Updated to reflect curre.nt character of the University's North Campus.
A new information center and headquarters.for the Dean of Engineering will be built within'500 feet of the reactor, but will not contain any housing facilities.
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l Theodore S.
Michaels i
October 27,-
1993 j
i I
Engg SectioD Description 3
3.1 Sealed tile drain to cold sump added to list of j
openings into the reactor building.
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3.3 Neutron flux updated to more accurate value.
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12 4.1 New primary pump is 20 hp.
j 15 5.2 New air compressor setpoints.
- l 18 6.2 Automatic controller specifically listed for correctness.
l 19 6.2 Input signal is provided to the recorder and to the-controller individually.
I 19 6.3 Log N - period Channel changed to Safety System
-l period Channel C.
1
.j 20 6.4 Description of safety system action when a scram signal is initiated is clarified.
i 21 6.4 Shim range defeat scram is not required by Technical j
Specifications and was removed during a facility modification.
]
21 6.4 Thermal column door interlock scram is not required by Technical specifications.
The door operator was disabled and the scram function was removed during a
.1 facility modification.
21 6.5.1 A switch in the original, mechnaical temperature recorder activated an automatic rundown when any
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input temperature to the recorder reached 129 oF.
l When an electronic recorder was installed, the'129 j
o F automatic rod rundown could be programmed for j
individual temperatures.
Now, only primary coolant j
temperatures are programmed to cause the rundown.
j 22 6.5.3 The primary coolant demineralizer local area monitor was removed by license amendment 38.
i 22 6.5.3 An upgraded electronic recorder permits individual alarm setpoints to be programmed-24 8.1.3 Control elements have slots in the side plates that permit the elements to be handled with a hook tool.
26 9.1.3 The facility cobalt-60 Irradiator is' licensed for 25,000 curies.
5
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)
Theodore S.
Michaels October 27',
1993 j
Pagg Section Description-l l
28 9.2.1 Flux level listed is closer-to correct in-core l
value.
28 9.2.2 Reference to the specific number of pneumatic tubes has been deleted; the number may be changed.
30 10.1 Waste is stored in steel 55-gallon drums.
It is stored on site at present; it will be shipped when permitted.
30 10.2 Clarification on handling of facility waste water.
which is recycled to the pool.
I 31 11.1.4 Very high radiation areas added.
i 11.1.5 32 11.2.1 Frequency and number of floor smear surveys made consistent with current procedures.
32 11.2.2 Clarification on contamination clean-up responsibilities.
i 32 11.2.4.3 proper reference in new 10CFR20 inserted.
33 11.2.5 Frequencies made consistent with current facility 11.2.6 procedures.
33 11.2.7 Reference to Technical Specifications eliminated.
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59-C4 14.3 New 10CFR20 names, values, and references inserted.
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-OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS
.{
Ford Nuclear Reactor i
I Docket 50-2, License R-28
.j Amendment 40:080193.
License. Renewal Issue With Amendments 1-32: 110384 f
Amendment:
33:080489 34:070191 35:040792 36:050192 j
37:062592 38:100792 39:051493 40:080193 i
i FORD NUCLEAR REACTOR j
i The University of Michigan i
]
Docket 50-2 OPERATING LICENSE R-28 l
1 l
A.
This license applies to'the Ford Nuclear Reactor owned by l
The University of Michigan.
The facility is located in Ann Arbor, Michigan, and is described in the application dated
{
November 30, 1984, as supplemented.
1 B.
Subject to the conditions and requirements incorporated j
4 herein, the Commission hereby licenses The University of Michigan-(1)
Pursuant to Section 104c of the Act and 10 CFR Part.50, f
" Domestic Licensing of Production and Utilization Facilities," to possess, use, and-operate the facility j
at the designated location in Ann Arbor, Michigan, in l
accordance with the procedures and. limitations set l
forth in this license, i
(2)
Pursuant to'the Act and 10 CFR Part 70, " Domestic l
Licensing of Special Nuclear Material," to receive, possess and use up to.a maximum of.18 kilograms of contained uranium 235 at enrichments equal to or less.
j than 20% in connection with operation of the. reactor.
(3)
Pursuant to the Act and 10 CFR Part'70, " Domestic Licensing of Special Nuclear Material", to possess, but i
not to use, a maximum of 8 kg of contained uranium at
[
greater than 20% enrichment until the existing j
inventory of high enriched uranium is: removed from the
[
facility.
a (4)
Pursuant to the Act and 10 CFR Part 30, " Rules of
[
General Applicability to Domestic Licensing of i
Byproduct Material," and Part 70 " Domestic Licensing of Special Nuclear Material," to possess, but not to j
separate, such byproduct and special nuclear materials as may-be produced by the-operation of the facility i
I f
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.I
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i
OPERATING LICENSE'AND TECHNICAL. SPECIFICATIONS f
Ford Nuclear Reactor Docket.50-2, License R-28 Amendment 40:080193 i
C.
This license shall be deemed to contain and is subject to the conditions specified in parts 20, 30, 50, 51, 55, 70, t
and 73 of 10 CFR Chapterf1, to all applicable provisions of the Act, and to the rules, regulations and orders of the.
i Commission now or hereafter in effect and.to the additional conditions specified below:
- j i
(1)
Maximum power Level The licensee is authorized to operate the1 facility at-power-levels not in excess of two megawatts (thermal).
(2)
Technical Specifications r
i The Technical Specifications contained-in Appendix A, t
are hereby l40
[
as revised through Amendment No. 4 0,,
incorporated in the license.
.The licensee shall operate the facility in accordance with the technical' specifications.
(3) physical Security plan 4
E The licensee shall fully implement and maintain in l37 effect all provisions of the physical security plan approved by the Commission and all amendments and changes made i
pursuant to the authority of 10 CFR'50.90 and 10 CFR j
50.54(p),.respectively.
The approved plan, which is exempt-from public. disclosure pursuant to the provisions of 10 CFR 2.790(d)(1), is entitled " Ford Nuclear Reactor Security Plan," Revision 1, submitted by letter dated May 17,.1991, and supplemented February 17, 1992, t
D.
This license is effective as of the date of issuance and shall expire twenty' years from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Director
[
Division of Licensing Date of Issuance: July 29, 1985
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Enclosure:
Appendix A, Technical Specifications
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