ML19259C511
| ML19259C511 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 05/14/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Wilbur L WORCESTER POLYTECHNIC INSTITUTE, WORCESTER, MA |
| References | |
| NUDOCS 7906230054 | |
| Download: ML19259C511 (10) | |
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'o UNITED STATES l'S
^,7, NUCLEAR REGULATORY COMMISSION
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aE WASHINGTON, 0. C. 20555 May 14, 1979 I
Docket No. 50-134 Dr. L. C. Wilbur, Director Nuclear Reactor Facility Worcester Polytechnic Institute i
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Worcester, Massachusetts 01609
Dear Dr. Wilbur:
This letter is provided in response to your request of April 23, 1979. As stated in your letter, your License No. R-61 will expire November 23, 1979.
Renewal of license requires submission of an application that demonstrates the reactor can continue to be operated safely and that the reactor com-ponents and systems will be capable of withstandi_ng prolonged use over the i
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term of the renewal. General requirements are provided in Title 10 Code of i
Federal Regula-tions (10 CFR), Parts 50, 51, 55 and 73.
Enclosed are specific
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items that will be reviewed prior to renewal of your license.
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You are reminded that 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 detemini_ng.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 (301492-7435) who has been assigned project manager for your facility.
Sincorely, M
Robert W..Reid, Chief
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Operati_ng Reactors Branch #4 Division of Operati_ng Reactors
Enclosure:
License Renewal Review Item 2283 354 7906230bF[
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I LICENSE RENEWAL REVIEW ITEMS A.
Contents of Application 1.
General Information (10 CFR 50.33)
Provide applicable information delineated in the referent regulation. The following 10 CFR 50.33 paragraphs obtain and additional guidance is provided herein:
(e) Include all NRC licenses issued for use at the facility.
(f) Financial Considerations - The review process to satisfy 10 CFR 50.33(f) requires infomation that will show that the licensee possesses the funds necessary to cover f
estimated operating costs or that there is reasonable
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assurance of obtaining the funds for 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 i
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additional copies:
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(1) The most recent published annual statement of I
the University.
Indicate, or provide
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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 pemanently 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 afinbal 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, a..J the source of funds to cover this.
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2 a.
The following is provided to assist in determining your estimated costs for permanently shutting down your reactor.
Choose the option (see Regulatory Guide 1.86) you deem most appr:priate. The following is an example for a TRIGA reactor using the mothballing option for decomissioning.
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It is assumed that dismantling of the core structure and other radioactive portions of the reactor system will g
be performed 3 to 5 years af ter complete removal of the g
fuel. The following provides estimated decomissioning costs (1976 $ value):
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Remov'l and disposal of fuel i
a.
a 9 $2000.00/ fuel element Approx.150 x $2000.00
$ 300,000.00 b.
Removal and disposal of core structure 20,000.00 c.
Removal and disposal of reactor tank, beamports, thermal column,
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etc.
$ 250,000.00 d.
Removal and disposal of reactor exposure room and biological concrete shield 5 250,000.00 I
e.
Decontamination S
50,000.00 l
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Dismantling of reactor bridge and cooling system 10,000.00 g.
Unexpected expenses
$ 120,000.00 Total h
$1.000,000.00 l
Three to five (3-5) years cooling period after complete removal of the fuel is necessary before dismantling of the core structure and other radioactive portions of the reactor l
assembly. During this period the room housing the reactor i
structure will be rr.aintained es'*a restricted area under a NRC possession-only license.
The same security level shall be maintained during this period as described in the Washington State University Research Reactor security plan. Minimum monitoring systens will be such as to insure that the health and safety of the public is not endangered. A facility radiation survey, an environmental 2283 356
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survey and an administrative procedure will be established for the notification and reporting of reportable occurrences.
Estimated cost (1976 5 value) to maintain the shutdown facility in a safe condition:
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Personnel
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Radiological survey, maintenance
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and administration 3 26,200.00/yr.'
b.
Supervitory and to prepare and coordinate detailed plan for disr.antling and disposal
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of structure
$ 20,000.00 e
f Total amount for a maximum period of 5 years (5 x $26,200.00) + $20,000.00
$151,000.00 i
The foregoing numbers, would of course, be different for your facility and also changed if you chotse a different option. This has been provided because of requests from other licensees on what criteria should be considered.
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2.
Filine of Aeolications Provide applicable information 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 impact of research reactors and may be used as a reference in developing an Environmental Impact Appraisal (EIA).
As a result of the attached memorandum, it was determined that an Environmental Impact Statement (EIS) is not required for research reactors 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.
Also attached is a copy of Michigan State University's EIA that you will find helpful in preparing your EIA.
3.
Technical Information (10 CFR 50.34)
(a) FSAR - (acolicable portions) of 10 CFR 50.34(b)
A review of your Safety Hazards Report (SAR) will be conducted for completeness and to ensure no significant safety hazard exists.
Data should be included to update the SAR with regard to natural and unnatural phenomena and incorporate all changes made during the licensed period. This information must use current analysis techniques and information. Further, a description and analyses of the structures, systems and components of the facility, with emphasis on the operational performance and the ability to function properly and safcly for the term of the license. This is particularly important because the original license was evaluated for a specific term. As some parts have obviously worn and there is some deterioration of the structure, the ability of the facility to operate safely
, for the requested term is a safety question.
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b (b) 10 CFR 50.34(b)(6) - Applicable portions
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The following pertains to specific items:
f (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
" Emergency Planning for Research Reactors" (issued for corrent).
Although in draft form they are being used by staff reviewers fdr 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 Attached are copies of Union Carbide's and University of Michigan's Technical Specifications, a draft copy of ANS.15.18
" Standard for Administrative Controls for Research Reactors" and Guidance provided in 1974 regarding Administrati've Controls.
Although there are considerable differences between your facility and Union Carbide and UM's facilities, the basic outline and fonnat is thatdesired for TS. In addition, there are certain portions of the license (i'.e., Records and Reports) that are more apropros in the TS.
In the course of license renewal, it is appropriate to upgrade TS and to bring them all up to a conmon reference level, consistent with current policy and within physical and operational constraints. You are requested to use the attached TS, ANS standard and administrative control guidance as guides to review your TS.
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6-The following guidance previously provided should be considered in your review process:
i (a) ALARA consideration should be included in the T.S.,
l as delineated in 10 CFR 50.36a (see ANS 15.12 j
attached).
(b) Provision regarding the insertion and irradiation of explosives must be included in the T.S. or not be handled at all.
All research reactors licensees were advised of this requirement June 1971. Previous concerns are reiterated in the following:
"An increasing number of programs being performed Et resaarch and testing reactor facilities involve the radiography of explosives.
The pres ence and irradiation of explosives in a reactor facility must be evaluated carefully because of 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 Sectior.
50.59 of.10 CFR Part 50 unless such usage has been reviewed and approved by the Comission.
If you presently receive, or have plans to receive and handle explosives, an evaluation of the consequences of accicental explosions should be made and submitted to the Cornission's Division of Reactor 1
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Licensing.
Proposed operating restrictions that provide for safe usage of explosive materials should be submitted for inclusion in your Technical Specifications.
In this context, " explosives" include all materials that would constitute Class A, ' -
Class B and Class C explosives as described in Tit'.e 49, Parts 172 and 173 of the Code of Federal Regulations, regarding transportation of explosives and other dangerous materials.
The Technical Specifications should contain sufficient information to establish operating restrictions; should indicate the maximum cuantity of explosives (in pounds of equivalent TNT) allowed in the facility, the form of the explosives, the
~ controls exercised when hand'.ng and storine i
exolesives, the cumulative radiaticn ex;csure limits for explosives, the utili:aticn cf expicsives i
within the facility, anc the maximum cua.- tity cf explcsives that could be involved in pcstulated accidents; and shculd. include an assessment of the probability and the potential consequences of an explosion occurring".
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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 Commission's Division of Reactor Licensing.
Proposed operating restrictions that provide for safe usage of explosive materials should be submitted for inclusion in your Technical Specifications.
In this context, " explosives" include all materials that would constitute Class A.
Class B and Class C explosives as described in i
Title 49, Parts 172 and 173 of the Code of Federal Regulations, regarding transportation of explosives and other dangerous materials.
l The Technical Specifications should contain i
sufficient infomation to establish operating I
restrictions; should indicate the maximum quaritity I
of explosives (in pounds of equivalent TNT) allowed l
in the facility, the form of the explosives, the g
controls exercised when handling and storing explosives, the cumulative radiation exposure limits for explosives, the utilization of explosives within the facility, and the maximum quantity of I
explosives that could be involved in postulated accidents; and should. include an assessment of the probability and the potential consequences of l
an explosion occurring".
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Also attached is one set of Regulatory Guides I
(2.1-2.5) that pertain to research reactors that
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should be used in developing your TS.
(c) Operator Licenses and Requalification Training Program (10 CFR Part 55)
(10 CFR 50.34 (b)(7) and (8).
(d) Physical Security Plan (10 CFR 50.34c))
r Your physical security plan will be reviewed in accordance with guidance provided June 1974 (copy attached) and 10 CFR Part 73 changes published since then.alf required, submit six copies of your revised physical security plan (PSP) with your renewal I
application. As your PSP 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 2283 361
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- t document. To facilitate further revisions made in accordance l
with 10 CFR 50.54(p) and amendments submitted for approval, it is requested that the PSP be in loose-leaf format. The following is an example of a license amendment making the PSP part of the license:
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"The 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, 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 letter 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 I
actual PSP.
Attached is a copy of proposed Regulatory Guide 5.XX.
It con-tains a format to ensure compliance with the regulations.
Although not yet issued, it does provide the essential fomat and guidance to be followed; therefore, it is requested you use this guide in developing your license renewal application.
Department of Energy and State Department have instituted a program to implement the Nonproliferation Act of March 10, 1978, by reducing the enrichment of fuels in nonpower reactors.
Con-comitant to this, the proposed 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; therefore, your license, which authorizes certain maximum possession limits of SNM (U235, Pu, U233), should be changed to reflect not only the total amount of SNM, but the i
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 foregoing with re-spect to your facility and ingjude your proposed SNM require-ments in your application.
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B.
Standards and Reculatory Guides For your information, our review will include your use of applicable ANS/ ANSI standards and NRC Regulatory Guides (2.1-2.5) for research reactors.
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- Note:
1.
All items for referenced 10 CFR articles not listed
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above are self-explanatory.
2.
Above subparagraphs are keyed to 10 CFR paragraphs.
Attachments:
1.
Muller /Skovholt Mero dtd.1/28/74 2.
Draft Copy ANS 15.16 - Emergency Planning
- 3. : Copy Reg. Guide 2.6 - Emergency Planning (Issued for Comr.ent) 4.
NRC Regulatory Guides 2.1-2.5 5.
Draft Copy ANS 15.18 6.
NRC Guidance for Adninistrative Controls.
7.
Draft Reg. Guide 5.XX - Physical Security Plan 8.
Draft Copy ANS 15.12 9.
Sample Union Carbide and University of Michigan TS
- 10. MSU Sample EIA 2283 a63 B
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