ML19242C749
| ML19242C749 | |
| Person / Time | |
|---|---|
| Site: | 05000142 |
| Issue date: | 06/13/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Brown H CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
| References | |
| NUDOCS 7908130327 | |
| Download: ML19242C749 (8) | |
Text
UNITED STATES l'
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NUCLEAR REGULATORY COMMISSION y,
WASHINGTON, D. C. 20555
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- June 13, 1979 Docket No. 50-142 Mr. Harold B. Brow'n Environmental Health and Safety Officer University of California at Los Angeles Los Angeles, California 90024
Dear Mr. Brown:
Your Facility Operating License No. R-71 will expire March 30, 1980. Renewal of your license requires the 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 withstanciing prolonged use over the term of the renewal. General requirements are provided in Title 10 Code of Federal Regulations (1.0 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 renew 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 in response to your request of May 25, 1979 and 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, bert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reac+wrs
Enclosure:
License Renewal Review Items 55E.237 q 90BN
'A f
e ENCLOSURE '
LICENSE RENEWAL REVIEW ITEI45 A.
Contents of Acolication 1.
General Information (10 CFR 50.33)
Provide ap:licable infornation 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 Financial Considerations - The review process to satisfy 10 CFR (f)
- 50..ih f ) requires information that will show Pat the licensee possess the funds necessary to cover estimated cerating costs or that there is reasonable assurance of obtain'.ng the funds for the period of the license renewal plus the estirated costs of permanently shutting down the facility and maintaining it in a To facilitate reviewing the financial aspects, safe condition.
it is requested that the following information be provided in three signed and notarized originals and six additional copies:
The most recent published annual statement.
Indicate, or (1) 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.
The estimated annual costs to operate the reactor for the (2) additional license renewal period and a certification that amounts designated in your application for renewal of the facility will be included in future budgets.
The estimated costs of permanently shutting down the reactor, (3) a listing of what is included in these costs, the assumptions made in estimating the costs, the type of shutdown contemplated, and the scurce 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 tnis estimate, assumptions made in determining the cost, any interest rates assumed, and the source of funcs to cover this.
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a, The following is provided to assist in deter nining your estimated' costs for pemanently shutti.;g down your reactor. Choose the option (see i
Regulatory Guide 1.86) you deem most appropriate. The following is an example for a TRIGA reactor using the mothballing option for decomissioding.
"It is assumed that dismantling of the core structure and other radioactive portions of the reactor system will be perfomed 3 to 5 years af ter complete removal of the fuel. The following provides estimated decomissioning costs (1976 $ value):
.a.
Removal and disposal of fuel 9
$2,000.00/ fuel element Approx.150 x $2,000.00
$ 300,000.00 b.
Removal and disposal of core structure 20,000.00 c.
Removal and disposal of reactor tank, beamports, themal column, etc.
$ 250,000.00 d.
Removal and disposal of reactor exposure room and biological concrete shield
$ 750,000.00 e.
Decontamination 50,000.00 f.
Dismantling of reactor bridge and cooling system 10,000.00 g.
Unexcected expenses
$ 120.000.00 Total
$1,000,000.00
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Three to five (3-5) years cooling period af ter complete removal of the fuel is necessary before dismantling of the core st ucture and other radioactive 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 recem. ended by the Nuclear Regulatory Comission that the same security level be maintained during this period as described in tne Texas A&M University TRIGA Research Reactor security plan. Minimum :nonicoring 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 administrative procedure will be estaclished for the notification and reporting of abncmal occurrence.
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Estimated cost (1976 $ value) to maintain the shutdown facility in -
a safe condition:
Personnel a.
Radiological survey, maintenance and adminis tration
$ 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 $25,200.00) + $20,000.00
$ 151,000.00" The foregoing numbers, would of course, be different for your facility and also changed.if you choose a different option. This has been provided because of requests from other licensees on what criteria should be considered.
- 2. Filine of Acolica tions Provide applicable information as delineated in 10 CFR 50.30 as follows:
(e) Exempt (f) Environmental Considerations cr~,
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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 im:rct of research reactors and may be used as a reference in developing an Environmental Impact Acpraisal (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, an6, therefore, sufficient information must be submitted to support and develop the EIA. (See attached MSU EIA for a sample.)
3.
Technical Information (10 CFR 50.34)
(a) FSAR - (acelicacie Scrtions) of 10 CFR 50.35(51 A compie:e review of ycur Safety Analysis Report (SAR) will be conducted to ensure nc significant safety ha:ard exists. A preliminary review of your SAR ir.:icates it must be u: data :: current analysis tech-iques and inf:rmation.
.s the cri;inal licen_e :as evalua ed for a specific term, tne fact :na s:me ;?.*:s obvicusly have wern and -here is some detericration of the reac cr structure :ne atility of tne facility to operate safely for the requested rerewal period is a safety cuestion. Therfare, the SAR shculd include information :na cescribes tne facility and all changes made during the license peried; the design basis and
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limits on its. operation; and a safety analysis of the structures; components and systems showing they will be able to perform their intended function; updated infomation 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 TRGA reactor is a singel fuel element leaking in air; etc.
It is suggested that you contact Dr. Nils Diaz (904-392-1401), University of Florida, Dr. Richard Hendrickson (515-294-5840), Iowa State' University, and Dr. Tom Parkinson (703-961-6590) regarding a standard DBA for Argonaut Re, actor Facilities.
(b) 10 CFR 50.34(b)T61 - Acolicable cortions The following pertains to specific items:
(v) Emercency Plannine The ~ plan should contar, but not be limited to the elements listed in Section IV of Appendix E to 10 CFR Part 50. Attached are draft ccpies of ANS 15.,16 " Standard for Erargency Planning for Research Reactors," and Regulatory Guide 2.6 (issued for j
cocrent) "E=ergency Planning for Research hactors."
j Altho ~ gh in draft ' form they are being used by Staff reviewers to u
ensure compliance with Appendix E, you are requested to use these documents as guides in preparing the emergency plan portion of your application.
(vi) Proposed Technical Specifications (TS) in accordance with 10 CFR 50.36)
_ A review of your license and TS reveals that it does not conform in content to current standards.
The T5 shall include items in the categories delineated in 10 CFR 50~.36(c)
" Safety Limits - Limiting Safety System Settings - Limiting Control Settings - Limiting Condition for Operation = Surveillance Requirements
' Design Features - Admin-istrative Controls." Each specification shall list the " Applicability
- Objective - Statement of the Specification - A Sumary Statement of the Bases (or reason for the specifications). Each specification is derived from the SAR and therefore should include the limiting conditions of operation and surveillarce requirements described in the SAR that will substantiate that there are sufficient checks and controls established to provide early detection of deterioration of systems, components and structures and operating limits to ensure safe operation for the renewal period. We have no typical updated Argonaut TS available.
Attached is a recently approved TS for Union Carcide that you may use as a guide in revising yours.
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f 5-t Also attached are a draft copy' of ANS 15.18, " Standard for Administrative Controls for Research R3 actors," and an administrative control section guidance previously provided to all research reactor facilities. You also are requested to review the administrative sections using this guidance I
and consider any changes you may want.
l The following guidance previously provided should be consicered in your review process:
(a) ALARA consideration should be incl.uded in the TS, as delineated in 10 CFR 50.36a'(see ANS 15.12 attached).
(b) Provision regarding the insertion and irradiation of explosives must be included in the TS or not be handled at all. All research reactors licensees were advised of this requirenent June 1971. Previous concerns
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are reiterated in the following:
"An increasing number of programs being performed at.rgsearch and testing reactor facilities involving the radiography of explosives. The presence and irradiation of explosives in a reactor facility must be evaluated The use of carefully because the potential for damage to the reactor.
explosives within a reactor f acility is considered to be an unreviewed safety question pursuant to Section 50.59 of 10 CFR Part 50 ur.less such If you presently-usage has been reviewed and approved by the Coemission.
receive, or have plans to receive and handle explosives, an evaluation of the consequences of accidental explosions should be made and submitted to the Commission's Director of Reactor Licensing. Proposed operating restrictions that provide for safe usage of explosive ntaterials should be submitt'ed for inclusion in your TS. In this context, "expl3sives" include all materials that would constitute 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 should contain sufficient information to establish operating restrictions; should indicate the maximum quantity of explosives (in pounds of equivalent TNT) allowed in the facility, the form of the explosives, the controls exercised when handling and storing explosives, the cumulative radiation exposure limits for explosives, the utili:aticn of explosives within the facility, and the maximum quantity of explosives that could be involved in postulated accidents; and shculd include an assessment of tne probability and the potential ccnsequences of an ex:lc-sion occurring".
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... (,c) Many of the research reactors still use abnomal occurrences (AO) as previously used in Regulatory Guide 1.16.
It was used to designate any unse.heduled or unanticipated operation event reported to the Codission.
included in these reported events were (1) events that would or did have significance frcm the standpoint of public health or safety and (2) events reported to NRC for perfomance evaluation and trend determinations. In Section 208 of the Energy Reorganization Act of 1974 (Pub. L.83-438),
an " abnormal eccurrence" is defined for the purposes of the reporting req 0iremehts of the Act as an unschedulec; incident or event which the Commission determines is significant from lhe standpoint of public health or safety. In order to be consistent with this definition, the events previously designated as "abncmal occurrences" are now designated
" reportable occurrences." The decision to change the designation to
" abnormal occurence" rests with the Comission.
(dj 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.
(c) Ocerator Licenses and Recualification Training Procram (10 CFR Part 551 (10 CFR 50.34(b)(7) and (8).
(d) Physical Security Plan (10 CFR 50.34(c))
Your physical security plan will be reviewed in accordance with 10 CFR Part 73. If required, subnit six copies of your revised physical security plan (PSP) with your renewal application. As your PST will 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 F) CFR 50.54(p) and amendments submitted for approval, it is requested the.: the PSF be in loose-leaf format. The folicwing is an example of a license amenL' ment making the PSP part of the license:
"Tht. licensee shall maintain in effect 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 consists of documents withheld from public disclosure pursuant to 10 CFR 2.790, collectively titled, " Veterans Administration Hospital, Cmaha, Nebraska, Security Plan," as follows:
Original, submitted with letter dated May 31, 1973 Revision 1, submitted with letter dated November 25, 1973 Revision 2, submitted with letter dated January la,1974 Revisicn 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 proposed Regulatory Guide 5.XX.
It contains a format to ensure ccmpliance with the regulations. Alchcugh not yet issued, it dces provide the essential fema and guidance to be followed; therefore, it' is requested you use this guide in developing your license renewal application, sea?d3
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Department o f Energy and State have instituted a program to implement the Nonproliferation Act of March 10, 1978, by reducing the enrichment of fuels in nonpower reactors. Concomitant to this, the proposed Regulation 173.47 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; therefgra your gqense, which authorizes certain maximum possession limits of SNM (U43 Pu, U 8), shculd be changed to reflect not only the total amount of SNM, but
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the percent enrichment of each; the amount of SNM exempt and how exempt (i.e.,
10 CFR 73.S(b)); and the amount of SNM nonexempt. This will establish the basis for the leve, of protection of your PSP. You are requested to review the fore-
- ir;.!t respect to your facility and include your pro;csed S"" re;uirements in your a
- clication.
B.
Standards and Regulatory Guides For your infomation, concomitant to the review of items in A above, all documents will include a persual to ensure you have included references and use of applicable ANS/ ANSI standards and NRC Regulatory. Gides (2.1 - 2.5) for research reactors.
- NOTE:
1.
All items from reference 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 2.
Draft Copy ANS 15.16 - Emergency Planning 3.
Copy Reg. Guide 2.6 - Emergency Planning (Issued for Coninent) 4.
NRC Regulatory Guides 2.1 - 2.5 5.
Draft Copy ANS 15.18 6.
NRC Guidance for Administrative Controls 7.
Draft Regulatory Guide 5.XX - Physical Security Plan 8.
Draft ANS 15.12 9.
Sample TS
- 10. Samole EIA G552M