ML19225D015
| ML19225D015 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 06/15/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Draper L TEXAS, UNIV. OF, AUSTIN, TX |
| References | |
| NUDOCS 7908030542 | |
| Download: ML19225D015 (8) | |
Text
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UN TED STATES y h e( 3)
NUCLEAR REGULATORY COMMISSICN
-C WASHINGTON, D. C. 20555 o.
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June 15,1979 Docket No.: 50-192 Dr. Linn Draper, Jr., Director Nuclear Reactor Laboratory University of Texas College of Engineering Austin, Texas 78712
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Dear Dr. Draper:
Your Facility Operating License No. R-92 will exoire February 12, 1980.
Rer.ewal 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 withstanding pro-longed use over the tem of the renewal. General requirements are provided in Title 10 Code of Federal Regul~ tions (10 CFR).
Parts 50, a
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 tem) of your application.
If possible a submittal of at least four months prior to expiration is desired to permit 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 licerse renewal process.
Please do not hesitate to contact Steve Ramos (301-492-7435) who has been assigned project manager for your facility.
Sincerely,
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1 Robert W. Reid, Chief Cperating Reactors Branch !4 Division of Cperating Reactors
Enclosure:
License Renewal Review Items
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79080'30547_
440 202
ENCLOSURE
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LICE!;SE :.ENEWAL REVIE'd ITEMS A.
Centen:s of A::lication 1.
General Infomation (10 CFt 50.331 Provide a::licable infor.atien celineated in the referent regulation.
The follcwing 10 CFR 50.33 paragraphs obtain and additional guidance is provide herein:
(e)
Include all NRC licenses issued for use en the c2m US
- inancial C nsiceratiens - The review process to satisfy 10 CFR (f) requires inicr atien that will-snow that the licensee 50.33(f)
- 0ssess tne funds necessary to cover estimated ocerating c
- sts-cr : hat tnere is reas na:le assurance of cbtaining de funcs for tne pericd of the license renewal plus the estirated c sts of per anently shutting dcwn tne facility and maincaining it in a safe condition. 70 facilitate reviewing the financial aspects, g
I it is requested cat the following infomaticn be provided in three signed and notari:ed originals and six additicnal copies:
(1) The = cst recent published annual statemeilt.
Indicate, or provide separatel,v, that portien of the budget which clearly delineates the sources of funds to be utilized to cover l
costs of c;eration of your reactor facilr y.
(2) The estimated annual costs to operate the reactor for the j
additional license renewal period and a certification that.
amounts designated in your application for renewal of the f acility will be included in future budgets.
The estimated costs of permanently shuttir.g d wn the reactor, (3) a listing of what is included in these costs, the assumptions
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made in estimating the costs, the type of shutdown contam.clated, l
and the scurce of funds to cover these c:sts.
(a) An estimate of the annual c:st to maintain the shutdewn f acilities in a safe condition.
Indicate what is included in this estimate, assu.9ntions made in detemi.ing tne c:st, any interast rates t
asstred, and One source of runes to c:ver this.
1 440 103
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The folicwing is provided to assist in de ermining ycur estimated costs a_. for permanently shutting dcwn your react:r.
Choose e ::icn (sea Regulatory Guide 1.56) ycu deem :s: appropriate. The folicwing is an example for a TRIGA reactor using the : thballing Opti:n for decomissieding.
1 i
"It is assumed that dismantling c' the core structure and cther radicactive portions of the reactor sys em will be perfor cd 3 :: 5 years after cen;ie e I
receval of the fuel. The folicwing provides estimated dec:missioning c:sts (1976 5 value):
i i
a.
Removal and dis:csal of fuel 0 52,0CO.00/ fuel element A;;rox. 150 x $2,000.CO
. S
'00,CC0.00 5.
Receval and disposal of c:re structure 5
20,CCO.CC I
c.
Rem: val and disposal of reac:Or tank, beamper s, 5
250,000.00 I
thermal column etc.
I d.
Removal and disposal of reactor exposure rocm and l
biological concrete shield S
250,000.00 e.
Dec:r.tami na tion S
50,000.00 f.
Dismantling of reactor bridge and c cling system S
10,C00.00 1
12^v
"^^0 Cn j
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Unexpected expenses To tal 51,000,0C0.00 Three to five (3-5) years ccoling pericd after complete" ra.moval of the fuel is
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necessary before dismantling of the core structure and other radicactive portiens i
of the reactor a.isembly.
During i.his pericd the reem housing the react:r structure i
will be maintained as a restricted area under a NRC ;;ssession-only license.
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!: is racemended by the riuclear Regula:Ory C:maissicn..u : the same security level be maintained during this period as described in the Texas A&M University TR*1R Research Reactor security plan. Minimum =cnitoring systems will be such as
- i,sure -ha: the heal:n and safety of the public is nc: endangered. A facility radia-icn survey, an environmental survey and an administrative precedure will se-M ished for the notifica-icn and rescr ing.cf abn r.al occurrence,
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h Estimated cost (1975 5 value) :: maintain the shutdown facility in a safe condition:
.rersonnel l
a.
Radiological survey, maintenance and j
a dministration S 25,2CO.00/yr.
b.
Supervisory and to prepare and coordinate detailed plan for dismantling and dispcsal cf structure 5 20,000.00 e-
.n otal amount r.:r a maximum period o, a years (5 x S25,200.00) - $20,000.C0 5 151,000.00' i
The foregoing numbers, wculd of course, be different for your facility and also changed if you choose a different option. This-has been provided because of requests frem ::her licensees en what criteria sheuld be consicered.
- 2. Filine of Acolicaticns Provide applicable informatier as delineated in 10 CFR 50.30 as foilews:
I (e) Exemp (f)
Environmental Considerations Attached is a memorandum, "Environmer.tal Considerations Regarding the Licensing cf Research Reacters and Critical.:acilities" dated January 23, 1974, frem D. Muller ta D. Skovholt, that provides the general envirer. mental impzct of research reactors and may be used as a reference in devel:;ing an Envir r. mental Impact Apariisal (EIA). As a -result of the attached memorandum, it was deter.
mined that an Envir:r. mental *: pact Statament (EIS) is not recuired for research react:r s authorized to Operate at 2 MW(t) and less. Mcwever, an EIA is required, and, therefore, sufficient information must be submitted to supccr: and develcp One EIA.
(See attached MSU EIA for a sample.)
3.
Technical Information (10 C.:R 50.32)
( l ',- TSAR - (1:slicable :crtiensi of 10 C.:R 50.35(b)
A ::::lete revie/ Of y:ur Safe y Analysis Re;cr: (SAR} will be c:nducted o ersure ne significan; safe y na ar exists. A preliainary review Of y:u-5AR 4,..
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- licusly lave
- e. r". 100 ~h3re is s0me deteriCF3tiCC Of thi rei !:P struc*..re; *.ne i:iZ.
f :ne ff~i'ig :O 0"erate safely fOr the recuestid renehal :eri d is 2 I2fe y Uesti0n.
7"erfore,19 3AR shCuld i Cluds i f0rta i;" Onat des ribes n
- ne facility an; ill :."anges Tade dur'ng the licensa ?eri: ; the desiCn b' sis and 440 205
4 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 Licensing Board Hearings in regard to the Columbia University TRIGA reactor, April 6,1971 and May 18, 1972.
(b) 10 CFR 50.3a(b)(6) - Apolicable cortions The foiiowing pertains to specific items:
(v)
Emergency 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, " Standard for Emergency Planning for Research Reactors," and Regulatory Guide 2.6 (issued for comment) " Emergency Planning for Re. search 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 review of your license and TS reveals that it does not conform ir, content to current standards. The TS shall include items in the categories delineated in 10 CFR 50.36(c)
" Safety Limits -
Limiting Safety System Settings - Limiting Cont-ol Settings -
Limiting Condition for Operation - Surveillance lequirements -
Design Features - Administrative Controls." Eac! specification shall list the " Applicability - Cbjective - Statament of the Specification - A Sumrary Statement of the Bases (or reason for the specifications t " Each specificaticn is derived from the SAR and therefore would incluce tne limiting conditions of operation and surveillance requirements described in the SAR tnat will sub-stantiate that there are sufficier. cnecks and controls establisned to provide early detection of deterioration of systems, cceconents and structures and operating limits to ensure safe operation for the renewal period. Attached is a copy of a ccmoined Texas A&M and Washington State University TS that you :an use as a guide in preparing your submission. We have recently completed our review of the University of California at Berkeley's TS for their TR:GA and will provide you a cooy of it as soon as they are available.
440 206
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, i ATso attached are a drrft copy of ANS 15.18 " Standard for Administrative Centrols for Research Reactors," and an administrative control section guidance previously provided to all researen reactor facilities. You also are requested to review the administrative sections using this guidance and consider any changes you may want.
The folicwing guidance previously provided should be censidered in ycur review process:
(a) ALARA censideraticn should be included in the 75, as delineated in 10 CFR 50.26a'(see ANS 15.12 attached).
(1) Pr0visien regarding the insertien and irradiatien of explosives mu.
be included in the TS or not be handled at ali. Ali research reac::-s licensees were advised of :nis requirement June 1.971.
Previcus concerns are reiterated in the following:
"An increasing number of prc; rams being perfcEed at raseeren and testing reac:Or facilities involving the radiograpny of excicsives. 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 reacter facility is considered to be an unreviewed safety questien pursuant to Section 50.59 of 10 CFR Part 50 unless such usage has been reviewed and a; proved by the Cccnissicn.
If you presently-receive, or have plans to receive and handle explosives, an evaluation of the ccnsequences of accidental explosions shculd be made and submitted to the Corr.ission's Director of Reacter Licensing. Proposed operating res ricticns that provide for safe usage of ex:losive materials should be submit:ed for inclusion in your TS.
In this centext, "excicsives" include all materials that would const tute Class A, Class 3 and Class C explosives i
as described in Title 49, Parts 172 and 173 of the Code of Federal Regulations, regarding trans:cr:ation cf explosives and other dangerous materials.
The T5 snculd centain sufficient infernatien :: establisn operating astricticns; shculd indicate the maximum cuantity c' ex:lesives (in pouncs cf equivalent TNT) allcwed in :ne facility, tne fer : of -he ex:lesives, the controls exer:' sed wnen hancling and s:crirs explosives, ne cumulative radia-icn ex::csure limi s for explcsives, the utiliza-icn cf excicsives within ne facility, and the maximum cuantity of explcsives
- na: cculd be involved in ccstulated ac:' dents; and snculd include an cf ne proba:ili y and :ne ;cte.:ial censecuences cf ar ex;l:-
assessmen:
sica cccurring '.
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5 (c) Many of the research reactors still use abncmal cc:urrences (AO) as previcusly used in Regulatory Guide 1.15.
It was used :: designate any unscheduled or unanticipated operation event re;;rted :: the Con:-ission.
Included in these rescrted events were (1) events that would or did have significance from the standcoint of public health or safety and (2) events reported to NRC for perfomance evaluation and trend deter ninaticns.
In Section 208 of the Energy Recrgani:ation Act Of 1974 (Pub. L.83-433),
an "abncrmal occurrence" is defined for the pur;cses of' the reporting req 0 ire ents of the Act as an unscheduled inciden er event which the Ccm-ission detemines is significant fr:m the stand: int of ?.;blic health or safe y.
In order to be consistant with-ti:i.s defini. tion, t.Te even s previously designated as "abncmal cc urrerces" are ccw :esignated
re;:rtable cc urrences." The decision t: cnan;e the designation :0
' abner.al occurence rests with :ne C:=nission.
(0
-1I attached is one se: Of Reg latory Guices (2.1-2.5) that pertain ::
research react:rs that sh:uld be ; sed in devel ;ing i:ur TS.
(c) C:erator Licenses and Recualification Trainine Precram (1C CFC par: 55)
(10.CFR 50.24(b)(7) and (8).
(c')
Physi:al Security Plan (10 CR 50.34/c))
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Your physical security plan will be reviewed in accaretance with 10 CFR Par. 73.
If required, submit six cocies of your revised physical g
security plan (PSP) with your renewal application. As ycur PSP will
~-U' r[WMT beteme part of the license and referenced as such in the renewed license documentation, it is further requested that the plan be reconciled into a CLb) single dccument.
To facilitate further revisions made in ac:Ordance with 10 CFR 50.54(p) and amendments submitted for a: proval, it is recuested G:pc7
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Ona: the FSF be in loose-leaf for at.
The folicwing is an example of 3 Am license amen' ment making the PSP part of the license:
C R.
d "The licensee shall maintain in effect and fully im;Iement all I
- rovisions of the NRC Staff-apartved :hysical security plan, including ['M amendments anc changes made pursuan:
9 The a: proved security plan consists of dccuments witn. eld from :u lico tne a disc csure pursuan: :: 13 CFR 2.790, collectively -1: led, "ye arans Acministration Hospital, Cmana, Ne:raska, Security Plan," as folicws:
D Cri;inal, submitted wi-h letter dated May 31, 1973 bm Eevisi:n I, submi:ted witn le-er dated Ncvem:er 25, 1973 Eevisi:n 2, su::i: ed wi:n Ie::er dated January 1,1972 Revision 3, surmi::ed sitt le::er da ed var n 11,19 "
'nis, of ::urse, is only an example anc d es n:: reflect your a::ual 5P.
A::a:ned is a :::y of ;re;cse: Reguia: ry Guide 5.XX.
I: ::ntains i far a:
er.sure ::m liance,,i:n :ne regulati:ns. AI:ncuir not ja: issued, i: ::es Or vice ne eisentiaI f ":d and guidance :: he f0$IcWe0', : are#Cre, i t" is reOues sc J0u use this guice in devel::ing four Iicer.se ene..al a:;li a! ion.
440 20 8
. Department of Energy and State have instituted a program to implement the Monoroliferation Act of March 10, 1978, by reducino the enrichment of fuels in nonpower reactors.
Conccmitant 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 authori::es certain naximum possession limits of SNM (U 35, Pu, UZ33), should be changed to reflect not nly the total amount of SNM, but the percent enrichment of each; the amount of SNM exerrpt and hcw exempt (i.e.,10 CFR 73.6(b)); and the amount of SNM nonexemot.
This will establish the basis for the level of protection of your PSP.
You are requested to review the foregoing with respect. to.your facility and include your proposed SNM requirements in your application.
B.
Standards and Reculatory Guides For your information, concomitant to the review of items in A above, all documents will include a persual to ensure you have included references and use of appli-cable ANS/ ANSI standards and NRC Regulatory Guider (2.1 - 2.5) for research reactors.
- NOTE:
1.
All items frca reference 10 CFR articles not listed above are sel f-explanatory.
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2.
Above subparagraphs are keyed to 10 CTR paragraphs.
Attachments:
1.
NRC Regulatory Guide 2.1 -2.5 2.
Copy Reg. Guide 2.6 - Emergency Planning (Issued for Coment) 3.
Draft ANS 15.12 4.
Draft Copy ANS 15.16 - Emergency Planning 5.
Draft Copy ANS 15.18 6.
NRC Guidance for Administrative Controls 7.
Draft Reg. Guide 5.XX - Physical Security Plan 8.
Muller /Skovholt Memo dtd.1/28/74 9.
Sample EIA
- 10. Sample TS 9
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