ML19225A720
| ML19225A720 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 05/30/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Miley G ILLINOIS, UNIV. OF, URBANA, IL |
| References | |
| NUDOCS 7907190840 | |
| Download: ML19225A720 (8) | |
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NUCLEAR REGULATORY COMMISSION (y
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May 30,1979 Docket No. 50-356 Mr George H. Miley, Chairman Nuclear Engineering Program University of Illinois 216 Nuclear Engineering Laboratory Urbana, Illinois 61801
Dear Mr. Miley:
Your License No. R-117 will expire November 1,1979. Renewal of your license requires submission of an application that demonstrates the reactor can continue to be operated safely and that the reactor components and systems will be capable of withstanding prolonged use over the term of the renewal. General requirements a.re provided in Title 10 Code df Federal Regulations (10 CFR),
Parts 50, 51, 55 and 73. Enclosed are specific items that will be reviewed prior to renewal of your license.
You are reminded that if you are planning to 3 enew your license,10 CFR 2.109 requires a timely filing (at least 30 days prior to expiration of your current ~.
license term) of your application. You are further advised to review 10 CFR 50.51 to assist you in determining the period of the renewal.
The foregoing has been provided to assist you in the license renewal process.
Please do not hesitate to contact Steve Ramos (301-492-7435) who has been assigned project manager for your facility.
Sincerely,
/
e o ert W. Reid, Chief Operating Reactors Branch f4 Division of Operating Reactors
Enclosure:
License Renewal Review Items 417 001 (F
70071008V0
LICENSE RENEWAL REVIEW ITEMS _
A.
Contents of Applicatiun 1.
General Infomation (10 CFR 50.33)
Provide applicable infomation delineated in the referent regulation.
The following 10 CFR 50.33 paragraphs obtain and additional guidance is provide herein:
(e)
Include all NRC licenses issued for use on the campus (f) Financial cor.siderations - The review process to satisfy 10 CFR 50.33(f) requires infcmation that will show that the licensee possess the funds recessary to cover estimated operating costs or that there is reasonable assurance of obtaining the funds foc the period of the license renewal plus the estimated costs of pemanently shutting down the facility and maintaining it in a safe condition. To facilitate reviewing the financial aspects, it is requested that the following information be provided in three signed and notarized originals and six additional copies:
(1) The most recent published annual statement.
Indicate, or provide separately, that portion of the budget which clearly delineates the sources of funds to be utilized to cover costs of operation of your reactor facility.
(2) The estimated annual costs to operate the reactor for the additional license renewal period and a certification that amounts designated in your application for renewal of the facility will be included in future budgets.
(3) The estimated costs of permanently shutting down the reactor, a listing of what is included in these costs, the ~ assumptions made in estimating the costs, the type of shutdown contemplated, and the source of funds to cover these costs.
(4) An estimate of the annual cost to maintain the shutdown facilities in a safe condition. Indicate what is included in this estimate, assumptions made in detemining the cost, any interest rates assumed, and the source of funds to cover this.
417 003 a_. The following is provided to assist.in determining your estimated costs for pemanently shutting down your reactor. Choose the option (see Regulatory Guide 1.86) you deem most appropriate. The following is an example for a TRIGA reactor using the mothballing option for decommissioding.
"It is assumed that dismantling of the core structure and ot.her radioactive portions of the reactor system will be performed 3 to 5 years after complete removal of the fuel. The following provides estimated 6comissioning costs (1976 $ value):
a.
Removal and disposal of fuel 0
$2,000.00/ fuel element Approx. 150 x $2,000.00
- 300,000.00 b.
Removal and disposal of core structure 20,00r.00
- . Removal aild disposal of reactor tank, beamports, themal column, etc.
$ 250 000.00 3
d.
Removal and disposal of reactor exposure room and biological concrete shield
$ 250,000.00 e.
Decontamination 50,000.00 f.
Dismantling of reactor bridge and cooling system 10,000.00 g.
Unexpected expenses
! 120,000.00 Total
$1,000,000.00 Three to five (3-5) years cooling period after complete removal of the fuel is necessary before dismantling of the core structure and other radicactive portions of the reactor assembly. During this period the room housing the reactor structure will be maintained as a restricted area under a NRC possession-only license.
It is recommended by the Nuclear Regulatory Comission that the same security level be maintained during this period as described in the Texas A&M University TRIGA Research Reactor security plan. Minimum monitoring systems will be such as to insure that the health and safety of the public is not endangered. A facility radiation survey, an environmental survey and an admini3trative procedure will be established for the notification and reporting of abnomal occurrence.
417 003 O
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Estimated cost (1976 $ value) to maintain the shutdown facility in a s #e condition:
Perso.1 el a.
Radiological survey, maintenance and administration i
$ 26,200.00/yr.
)
b.
Supervisory and to prepare and coordinate detailed plan for dismantling and disposal of structure
$ 20,000.00 Total amount for a maximum period of 5 years (5 x $26.,200.00) + $20,000.00
$ 151,000.00" The foreo*g numbers, would of course, be different for your-facility and also ch' a if you chcose a different option. This has been provided because of requests from other licensees on what criteria should be considered.
- 2. Filing of Acolications Provide applicable infomation as delineated in 10 CFR 50.30 as follows:
(e) Exempt (f) Environmental Considerations Attached is a memorandum, " Environmental Considerations Regarding the Licensing of Research Reactors and Critical Facilities" dated January 28,1974, from D. Muller to D. Skovholt, that provides the general environmental imf r.t of research reactors and may be used as a reference in developing an Environmental Impact Appriisal (EIA). As a result of the attached memorandum, it was deter-mined that an Environmental Impact Statement (EIS) is not required for research reactor s authorized to operate at 2 MW(t) and less. However, an EIA is required, and, therefore, sufficient information must be submitted to support and develop the EIA.
(See attached MSU EIA for a sample.)
3.
cnnical Infomation (10 CFR 50.34)
(a) FSAR - (apolicable portions) of 10 CFR 50.35(b)
A complete review of your Safety Analysis Report (SAR) will be conducted to ensure nc significant safety hazard exists. A preliminary review of your SAR indicates it must be updated to current analysis techniques and information. As the original license was evaluated for a specific term, the fact that some parts obviously have worn and there is some deterioration of the reactor structure; the ability of the facility to operate safely for the requested renewal period is a safety question. Therfore, the SAR should includs information that describes the facility and all changes made during the license period; the design basis and 4U 004
-4 limits on its operation; and a safety analysis of the structures, components and systems showing they will be able to perfonn their intended function; updated information on meteorology, seismic and other natural and unnatural phenomena; analyses of a design bases accident (DBA) and the consequences thereto - for example the DBA for a TRIGA reactar is a single fuel element leaking f ri air; etc.
(b) 10 CFR 50.34(b)(6)'-' Apolicable portions The following pertains to specific items:
(v) Emergency Planning The plan should contain, but not be limited to the elements listed in Section IV of Appendix E to 10 CFR Part 50. Attached are draft copies of ANS 15.16, " Standard for Emergency Planning for Research Reactors," and Regulatory Guide 2.6 (issued for coment) " Emergency Planning for Research Reactors."
Although in draf t form they are +i used by Staff reviewers to ensure compliance with Appendix
.ou are requested to use these documents as guides in preparing the emergency plan portion of your application. As your advanced TRIGA and LOPRA share the same room, you should consider a single plan for both facilities.
(vi) Procosed Technical Specifications (TS) in accordance with'10 CFR 50.36)
A review of your license and TS reveals that, in general, it conforms in content to that prescribed in the regulations. The TS must have the limiting conditions of operation and surveillance requirements described in the SAR and that will substantiate that there are sufficient surveillance and limits established to provide early detection of deterioration of systems, components and structures and operating limits to ensure safe operatic, for the renewal period. Your LOPRA is rather unique and therefore there is no comparable comon TS.
However, attached is TRIGA TS that has recently been updated for you to use as a sample in revisf ag your TS.
Also attached are a draft copy of ANS 15.18, " Standard for Administrative Controls for Research Reactors," and an administrative control section guidance previously provided to all research reactor facilities. You also are requested to review the administrative sections Osing this l
guidance and consider any changes you may want.
The following guidance previously provided should be considered in your review process:
(a_) ALARA consideration should be included in the TS, as delineated in 10 CFR 50.36a (see ANS 15.12 attached).
417 005 M-(b_) Provision regarding the insertion and irradiation of explosives must be ip.luded in the TS o'r nct be handled at all. All research reactors licensees were advised of this requirement June 1971. Previops concerns are reiterated in the following:
"An increasing number of programs being performed at. research and testing reactor facilities involving the radiography of explosives. The presence and irradiation of explosives in a reactor facility must be evaluated carefully because the potential for damage to the reactor. The use of explosives within a reactor facility is considered to be an unreviewed safety question pursuant to Section 50.59 of 10 CER Part 50 unless such usage has been reviewed and approved by the Cor. mission.
If you presently-receive, or have plans to receive and handle explosives, an evaluation of the consequences of. accidental explosions should be made and submitted to the Comission's Director of Reactor Licensing.
Proposed operating restrictions that provide for safe usage of explosive materials should be submitted for inclusion in your TS.
In this context, " explosives" include all materials that would const.itute Class A, Class B and Class C explosives as described in Title 49, Parts 172 and 173 of the Code of Federal Regulations, regarding transportation of explosives and other dangerous materials.
The TS sh'ould contain sufficient infomation to establish operating restrictions; should indicete the maximum quantity of explosives (in pounds of equivalent TNT) allowed in the facility, the fota of the explosives, the controls exercised when handling and storing explosives, the cumulative radiation exposure limits for explosives, the utilization of explosives within the facility, and the maximum cuantity of explosives that could be involved in postulated accidents; a?. anould include an assessment of the probability and the potential consequences of an explo-sion occurring".
(c_) Many of the research reactors still use abnormal occurrences (AO) as previously used in Regulatory Guide 1.16.
It was used to designate any unscheduled or unanticipated operation event reported to the Comission.
Included in thesc *eported events were (1) events that would cr did have significance from t!.2 sf aadpoint of public health or safety and (2) events reported to NRC for performance. evaluation and trend deteminations.
In Section 208 of the Energy Reorganization Act of 1974 (Pub. L.83-438),
an " abnormal occurrence" is defined for the purposes of the reporting reqQirements of the Act as an unscheduled incident or event which the Commission detemines is significant from the standpoint of public health or safety.
In order to be consistent with this definition, the events previously designated as " abnormal occurrences" are now designated
" reportable occurrences." The decision to change the designation to
" abnormal occurence" rests with the Commission.
(d) Also attached is.one set of Regulatory Guides (2.1-2.5) that pertain to research reactors that should be used in developing your TS.
i i
417 006 1
e
. (c) Operator Licenses and Recualification ~Trainino Procram (10'CFR Part 55)
(10 CFR 50.34(b)(7) and (8).
(d) Physical St eurity ~ Plan ~ (10 CFR 50.34(c))
Your physical security plan will be reviewed in accordance with guidance provided Jur.e 1974 (copy attached) and 10 CFR Part 73 changes published since then.
If required, submit six copies of your revised physical security plan (PSP) with your renewal application. As your PSP will 1
become part of the license and referenced as such in the renewed license documentation, it is further requested that the plan be reconciled into a single document. To facilitate further revisions made in accordance with 10 CFR 50.54(p) and amendments submitted for approval, it is requestrd that the PSP be in loose-leaf format. The following is an cample o a license amendment making the PSP part of the license:
"The licensee shall maintain in 6ffect and fully implement all provisions of the NRC Staff-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved security plan cor.sists of documents withheld from public disclosure pursuant to 10 CFR 2.790, collectively titled, " Veterans Administration Hospital, Omaha, Nebraska, Security Plan," as follows:
Original, submitted with letter dated May 31, 1973 Revision 1, submitted with letter dated November 26, 1973 Revision 2, submitted with lett.ar dated January 14, 1974 Revision 3, submitted with letter dated March 11, 1974" This, of course, is only an example and does not reflect your actual PSP.
Attached is a copy of propaed Regulatory Guide 5.XX.
It contains a format 7
to ensure compliance with the regulations. Although not yet issued, it does provide the essential fomat and guidance to be followed; the.efore, it is requested you use this guide in developing your license rensal application.
Department o f Energy and State have instituted a program to imple.nent the Nonproliferation Act of March 10, 1978, by reducing the enrichment of fuels in nonpower reactors. Concomitant to this, the praposed Regulation 573.47 is designed to implement the US/IAEA Agreement when approved by the Senate. Both of these actions are keyed to the enrichment of fuel and other SNM; theref your { cense, which authorizes certain maximum possession lim 3,
Pu, U 3), should be changed to reflect not only the total amount of SNO, but the percent enrichment of each; the amount of SNM exempt and how exempt (i.e.,
10 CFR 73.6(b)); and the amount of SNM nonexempt. This will establish the basis for the level of protection of your PSP. You are requested to review the fore-going with respect to your facility and include your proposed SNM requirements in your application.
B.
Standards and Reculatory Guides Fcr your information, concomitant to the review of items in A above, all documents will include a persual to ensure you have included references and 417 OD7
use of applicable ANS/ ANSI standards and NRC Regulatory Guides (2.1-2.5) for research reactors.
- NOTE:
1.
All items from referenced 10 CFR articles not listed above are self-explanatory.
2.
Above subparagraphs are keyed to 10 CFR paragraphs.
Attachments:
1.
Muller /Skovholt Memo dtd.1/28/74 Draf t Copy ANS 15.16 - Emergency Planning 2.
Copy Reg. Guide 2.6 - Emergency Planning (Issued for Coment) 3.
4.
NRC Regulatory Guides 2.1-2.5 5.
Draf t Copy ANS 15.18 5.
NRC Guidance for Administrative Controls 7.
Draf t Regulatory Guide 5.XX - Physical Security Plan 8.
Draft ANS 15.12 9.
Sampla TRIGA TS
- 10. Sample EIA 417 003
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