ML19247B044

Forwards List of Specific Items That Will Be Reviewed Prior to Renewal of License R-70,expiring on 800629.Licensee Reminded of Procedural Requirements for Submittal of Application

ML19247B044
Person / Time
Site:	University of Maryland
Issue date:	06/21/1979
From:	Reid R Office of Nuclear Reactor Regulation
To:	Elkins W MARYLAND, UNIV. OF, COLLEGE PARK, MD
References
NUDOCS 7908070036
Download: ML19247B044 (9)

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g3 WASHINGTON, D. C. 20555 uune 21, 1979 gv*....f Docket No.: 50-166 Dr. Wilson H. Elkins, President University of Maryland College Park, Maryland 20740

Dear Dr. Elkins:

Your Facility Operating License No. R-70 will expire June 29, 1980.

Renewal of your license reqaires 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 withstanding pro-longed use over the term of the renewal. General requirements are provided in Title 10 Code of 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 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.

If possible, a submittal of at least six months prior to expiration is desired te pernit sufficient time to complete the necessary reviews and issuance of required notification prior to the end of your present license period. You are further advised to review 10 CFR 50.51 to assist you in determining the period of the re-newal.

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 assi;ned project manager for your facility.

Sincerely, gam Racert W. Reid, Chief Operating Reactors Branch !4 Division of Operating Reactors

Enclosure:

License Renewal Review Items cc w/ enclosure: Mr. Ralph Belcher h

University of Maryli.id 7908070 6 M-

ENCLOSURE LICENSE RENE'4AL RCVIE'a' ITEMS _

A.

Contents of Acolicatien 1.

General Infomation (10 CFR 50.33)

Provide a::licable infoma-ion delineated in the referent regulation.

The folicwing 10 CFR 50.33 paragrachs cbtain and additional guidance is provide herein:

(e)

!nclude all NRC licenses issued for use en the cam us Financial Consideratiom - The review process to satisfy 10 CFR (f)

.,.oEaticn that will show that the licensee 50.33(f) require:

possess the funds necessary to cover estimated opera-ing costs there is reas nacle assurance of cotaining :ne funds for or :ha:

• ne perind of :ne license renewai alus one estirated costs of cemanently shutting down :ne facility and maintaining it ir a safe condition. To facilitate reviewing the financial ascects, it is requested that the following inicmaticn be :rovidec in three signed anc notarized Originals and six additicnal copies:

(1) The mest recent published annual statement.

Indicate, or provide separately, that portien of the budge: wnich clearly delineates the sources of funds to be utilized to cover costs of operation of your react:r #acility.

(2) The estimated annual costs to ocerate the react:r for ce additional license renewal period and a cartification that amcunts designated in your a:clication for renewal of the facility will be incluced in future budgets.

The estimated costs of cernanently shuttih.g cown the react:r, (3) a listing of wnat is included in these costs, the assumoti:ns made in estimating the costs, the type of shutdcwn ccatem_::iated, and the scurce of funcs :: ::ver these costs.

(a) An estimate of the annual cast to maintain the shutdown f acilities in a safe concition.

Indicate wna is included in :nis es-imate, assum:: ions made in determining tne ::st, any interest rates ass =ed, and One source of runcs : caver Inis.

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The following is provided 0 assist in determining ycur es:imated costs for permanently shu ing down your reactor. Choose the a :;on (see Regulatory Guide 1.56) you deem most appr:priate. The folicwing is an l

example for a TRIGA reac r using the metnballing option for decommissicding.

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"It is assumed that dismantling of the core structure and other radicactive portions of the reactor system will be performed 3 to 5 years af ter ccmplete removal of the fuel. The folicwing provides estimated decommissioning costs (1975 5 value):

e a.

Remcval and dis:csal of fuel @

S2,000.00/ fuel element l

l Ae:rax.150 x S2,000.00

$ 300,000.00 i

5.

Remaval and disposal of core structure 20 :00.00 2

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Re ceval ind disposal of reactor tank, beamparts, I

thermal column, etc.

$ 250,000.00 i

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(emoval and disposal of reactor expcsure recm and i

biological concrete shield 5 250,000.00 e.

Cec:ntamir;ation 50,0C0.00 Dismantling of reactor bridge and cocling system 10,000.C0 g.

Unexpected expenses

$ 120.0C0.00 9

To tal

$1,0C0,000.C0 Three to five (3-5) years c cling pcried after c:mplete removal of the fuel is necessary before dismantling of the core structure and other radicactive porticr.s of :ne react 0r assembly. During this period the recm nousing the reactor structure will be maintained as a rastricted area under a NRC pcssession-only license.

It is recommended by the Nuclear Regula: cry Ccamission tha: the same security level be maintained during :ni period as described in tne Texas A&M Un;versity TR'IA Research Reac:Or security picn.

Minimum menitoring systems will be such as to insure that the heal:n anc safety of the public is not endangered. A f acility raciatico survey, an environmen al survey and an administrative pr cedure will be esta lisned for the notification and reporting of abn rmai occurrence.

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I Esticated cos; (1975 5 value) to maintain the shutdown facility in a safe concition:

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Radiological survey, maintenance and acministration S 25,200.00/yr.

i b.

Supervisory and to prepare and coordinate detailed plan for dismantling and cisposal of structure 5 20,000.00 Total amount for a maximum period of 5 years (5 x S25,200.00) - $20,000.C0

$ I51,000.00" The foregoing numbers, would of course, be di ferent for your facility and also changed

'# you cheese a different option. This has been provided because of request' sn other licensees on wnat criteria shcuid be considered, e

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111ng or Accl1ca tions r

provide applicable information as delineated in 10 CFR 50.30 as folicws:

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( 7,3 Considerations

nvi ronmenta,l A:: ached is a memorandum, " Environmental Considerations Regarding the Licensing of Research Reacters and Critical Facilities" da:ed January 23, 1974, frcm

. Muller to D. Skovhoit, that provides the general envirer. mental im:rct of researca reactors,anc may be used as a reference in develcping an :nviron. ental

.impact s,coriisa,s t :in j. as a result or :ne attached emorandum, it,,as dt.ar-mined : hat an Envir:nmental Im:ac Statament (EIS) is nct required for resear:h reac: Ors authori:ed ;c operate at 2 MW(:) and less. Mcwever, an EIA is recuired, and, therefore, suf#icient information must be submitted to support and devel::

One EIA.

(See attached MS'J EIA for a sam:le.)

3.

Technical Information (10 CFR 50.34T (a) 05AR - (3:alicabie :ce-ic-si of 10 C. P 50.35(b)

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• 3 nnno pn si bOki dd n-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 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 reactor is a single fuel element leaking in air; etc., based on the decision of the Atomic Safety and LicensSg Board Hearings in regard to the Columbia University TRIGA reactor, April 6,1971 and May 18, 1972.

(b) 10 CFR 50.34(b)(6) - Acclicable cortions The following pertains to specific items:

('v) Emercency Plannino 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, "Stai for Emergency Planning for Research Reactors," and Regulat, vulde 2.6 (issued for cement) " Emergency Planning for Research Reactors."

Although in draft form they are being used by Staff reviewers to 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 preliminary review of your licensa and TS reveals that it does not confonn in content to current guidance to assure measures have been established for safe operrtion of the reactor during the period of the license renewal.

Each specification should be derived from the SAR and therefore would include i.he limiting conditions of operation and surveillance requirements described in the SAR that will substantiate that there are sufficient checks and centrois established to prov 4de early detection of deterioration of systems, comoonents and strur.tures and operating limits to ensure safe operation for the renewal period. Attached is a ccpy of a ccmoined Texas A&M and Washington State University TS that you can use as a guide in precaring your submission. We have recently completed our review of the University of California at Berkeley's TS for their TRIGa and will provide you a copy of it as soon as it is available.

The following are a few items noted during our review.

It is by no means complete and is provided to give you an idea as to the extent of our review.

L 1.11 - Should be changed to " Reportable Occurrence" - An abnor al occurrence is defined for the purpose of the reporting require-ments of the Act or an unscheduled incident or event which the Commission determines is significant from tt'a standpoint of public health or safety and is required to be submitted to the Congress.

3.3 - Safety Reactor System Specifications - should be changed as follows:

" Fuel element temperature 1

Scram at 400 C Reactor power level 2

Scram at 120% of full licensed power"

- As currently worded, it is confusing as to just what the scram point is.

Basis will also have to be corrected.

Area radiatio 7 monitor scram settings should be explicit and basis should include what radionuclides are applicable.

There are no surveillance or LCO's for the reactor pool water.

As the water is considered part of the shielding, there should be an alarm whenever the level falls to a certain minimum level above the grid plate. There should also be specifications covering the water chemistry and analysis for racianuclides.

Both of these are necessary to assure there are sufficient surveillance measures for the early detection of any deterior-ation of the fuel and reactor structure.

Also attached are a draft copy of AtlS 15.18, "Studard for Administrative Controls for Research Reactors," and an atninistrative control section guidance previously crovided to all research reactor facilities.

You also are requested to review the administrative sections using this guidance and consider any changes you may want.

Be folicwing guidance previously p.ovir ed should be considered in your review process:

( a_) ALARA consideration should be included f a the TS, as delineated in 10 CFR 50.36a'(see AftS 15.12 attached).

(1)

Provis~ ion regarding the inser icn and irradiation of explosives must be incluced in tne TS cr nc: be handled at ali. All researen reac::rs licensees were acvised of tnis requirement June 1971. ?revicus concerns are reiterated in :ne foilewing:

402 006

An increasing number of programs being performed at. research and testing reactor facilities involving the radiogra:ny of excicsives. The presence and irradiation of explosives in a reactor facili:y must be evaluated carefully because the potential for damage to the reactor. The use of explosius within a reactor facility is considered t; _e an unreviewed safety gastien pursuant to Section 50.59 of 10 CR Part 50 unless such usage has been reviewed and approved by the Ccanission.

If you pr esently -

receive, or have plans to receive and handle explosives, an evaluation of the consequences of accidental explosicns sh0uld be made and submitted

the C0 mission's Director of Reactor Licensing.

Proposed operating restrictions thet provide for safe usage of explcsive materiais shculd be submit ed for inclusion in your TS.

In this con ex:, "exolosives" include all materiais that would constitute Class A, Class 5 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 dange cus materials.

The T5 snculd contain sufficient infomation to establish operating restrictions; shculd indicata the maximum cuantity of explosives (in

0unds of equivalent TNT) ailcwed in the facility, the f0m of the explosives, the c

ntrols exercised when handling and storing expicsives, One cumulative radiation exposurs limits for explosives, the utili:a-icn Of explosives wi-hin the facility, and the maximum quantity of excicsives

na: could be involved in :cstulated accidents; and should include an assessment of the pr00ar41ity and tne potential consecuences of ar ex;ic-sian occurring".

( c_) "any of the research reactors sti;l use abnamal occurrences (AO) as previously used in Regula:Ory Guide 1.15.

It was used to designate any unscheduled or unanticipated operation event reported : the C0=issicn.

Included in these reported events were (1) events that would or did have significance frem the standpoint of public 5ealth or safety and (2) events repcrted to NRC for pc-formance evaluation and trend deteminations.

In

. Section 205 of the Energy Recrganization Act of 1974 (Pub. L. 33 438),

an "abncrmal occurrence" is defined for the purposes of the repcrting rec 0irements of the Act as an unscheduled incident or event which -he Cchission de: ermines is significant f :m :he stare in: Of ;;blic heal-h

r safe y.

In order to be consis ent wi-h this definition, the events creviously designated as "acncmal occurrences" are new designated

're;ortable occurrences." The decision to chance the designation to

abncr al occurence rests with the C aission.

!! s: a-achec is one se: Of RegCa:;ry Lices (2.1-2.5)

."a percain 0 esear: rea:: rs :na snculd be ; sed in :eveicting y:ur 75.

(:) 0:e-a cr Licenses and Recual"ication Trainine procram (10 CF0 ?t: 551 (10 CFR 50.24{b)(7) and (3).

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MWNM 402 007

. (} Phvsi:al Security Plan (10 CR 50.34(cli Your pnysical security plan will be reviewed in accordance with 10 CFR Part 73.

If required, submit six copies of your revised physical security plan (PSP) with your renewal application. As ycur PSP will bec:me 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 accorcance with 10 CR 50.52(p) and amendments submitted for a: proval, it is recuested tra: the PSP be in loose-leaf format. The folicwing is an example of a license amendent making the PSP par: cf the license:

"The licensee shall maintain in effect and fully implement all previsions of the NRC S:aff-approved pnysical security plan, including amendments and changes made pursuan: to the authority of 10 CFR 50.5 (p).

The approved security plan consists of documents withheld fr0m public disclosure pursuant to 10 CFR 2.790, collectively titled, " Veterans Acminist.ation Hospital, Omaha, Nebraska, security Plan," as folicws:

Origi al, submitted with letter dated May 31, 1973 Revision 1, submitted witn letter dated Ncvember 25, 1973

evision 2, submitted with le::er dated January le, 1974

evis;0n 3, submitted with letter dated March 11, 1974" This, Of ccurse, is only an example anc does not reflect your actual P5P.

A : ached is a cc:y of prc;csed Regula:Ory Guide 5.XX.

It contains a for a

ensure ccm::liance with the regulations. Althcugh not yet issued, it does

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vice One essen:ial fer a and guidance to be foli wec; :nerefore, it' is re:ueste: ycu use this guide in develcping ycur license renewal a; plication.

De::artment o f Energy and State has e instituted a program to im::lement the Ncnercliferation Act of March 10, 1978, by reducing the enrichment of fuels in non:cwer react:rs. Ccncomitant to :nis, the presosed Regulation 573. 7 is ce.icned ::: implement the US/IAEA Agreement wnen ap roved by the Senate. 5ctn of :5ese 1cti0ns are keyed to :ne enrichmr'; of fuei and 0:ner SZ, therefq ;.

ycur license, wnich au:ncrizes certain :.1 mum posses i0n limits Of SNM (UG Ou, U223), snculd be cnanged to reflec: not only :he :stal amcunt of SNM, but

ne :ercent enrichrent cf each; the accunt of SNM exemot and new exem:0 (i.e.,

10 CFR 73.6(b)); and the amount of SNM nonexerot.

This will establish the basis for tne levei of protection of your PSP.

You are reauested to review the fore-going wi th respect to your facility and include your croposed SNM requirerTnts in your application.

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40-

.. 3.

Standards and. Regulatory Guides For your information, concomitant to the review of items in A above, all documents will incluce a persual to ensure you have included references and use of applicable ANS/ ANSI standards and NRC Regulatory-Qices (2.1 - 2.5) for research reactors.

• NOTE:

1.

All items frem reference 10 CFR articles not listed above are self-explanatory.

2.

Above subparagrachs are keyed to 10 CFR paragraphs.

Attachments:

1.

Muller /Skovholt Memo dtd.1/28/74 2.

Craft Copy ANS 15.16 - Emergency Planning 3.

Copy Reg. Guide 2.6 - Emergency Planning (Issued for Comment) 4 NRC Regulatory Guides 2.1 - 2.5 5.

Draft Copy ANS 15.18 5.

NRC Guidance for Administr'itive Controls 7.

Craft Regulatory Guide 5.X. - Physical Security Plan 3.

Draf; ANS 15.12 9.

Samole TS

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