ML20196D395
| ML20196D395 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 06/15/1999 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20196D385 | List: |
| References | |
| NUDOCS 9906240269 | |
| Download: ML20196D395 (37) | |
Text
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TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R-38 A
- ! 1999 Proposed Amendment 36 9906240269 990615 PDR ADOCK 05000089 P PDR
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- .. i 83 S'iE-c eft % k h TABLE OF CONTENTS 1.0 Definitions . . . . ............ .. , . . . . . . . . . . . . . . .. . ... .. ... . .. .. ... . .... 1 2.0 Site . .. .. . .. . .. ............................................... 46 2.
3.0 Reactor Building-Peel . . . . . . . . . . . . . . . . . . . . . . .. .... ... .. .... . . . . 45 2., 4.0 Reactor Pool-Gore ... . . . . . . . . . . . . . . . . . . . . . . . . ....... . ... . .. 66 2. 5.0 Rea ctor Fuel. . . . . .. . . .. . . . . . . . . . . .. . . . .... . .. .. ..... .. . .... . .. . . . . . . . -66 3 f43.0' Control ar:d Safety Systems . . . ..... . .. . . . .. ... . .... ... .... ... . #3 66.1 Control Systems .. . ... ... . .... . .. ...... . .. . . .. ....... . . . &3 66.2 Safety Systems . . . .. . . . . . . . . . . . . . ..... .... ... . . .. . . . . .. 87 3 6.-3 i. .A. : n.e.n.~.
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79.0 Administrative $ P. ."I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . +76'3 79.1 Orga nization . . .. . . . ... .. . . .. . . .. . . ... ..... .. .. . . . .. .. . . . . .. 476 3 79.2 Criticality and Radiation Safety Rcylcw Committee ... ........... . .. 487 4 79.3 Written Procedures ..... ... .. .. . . .. ... ........ . ..... .... ..... . . . 4GB 5' 79.4 Action to be Taken in the Event of a Reportable Occurrence . . . . 3649 4 79.5 2S4)6Y !: d _ p Sg Records .... .. ... . . . .. . .. . . . . .... ......... . .. . .. . 2949Q 79.6 Reporting Requirements ...... ..... . ....... ... . . .... . ... ..... .. ... .. .2J39 7 l T'ak.. in t. R.A.
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8.0 Facility Operations....... .. ... ... ..... .. .. ......... . ... . . . . . . . . . .. -33 < 1 1 1 1 Amendment No. 365 i t J
1 l l l APPENDIX A LICENSE NO. R-38 TECHNICAL SPECIFICATIONS FOR THE TORREY PINES TRIGA MARK i REACTOR I 1 D "'- DATE: JANUARY 21,1972 ! b,y Ndrl 1.0 N c & \ Asp >larhnu Mt f DEFINITIONS l l ( C., 'D 1.1 FacilityReacter Shutdown Facility means the building housing N disassembled reactor plus systems, components, etc. associated with possession ertly of the reactor. Reaetor-shutdcwn abc!! rncan that th; rccctor ic cubcritical at c!! timcc b" at !ccat onc dc!!cr of-reaetw+ty-
&1 D 1,2 FacilityResetor Secured anl de'-om *I M i o n inb deemehtinW9 AcVd'es an._,
Facility-Reseter secured shall mean that condition where nopere-is in progress !~'e!"eg-icmc:c! ci autavolod 6, uvisias,,,,,wvJ isarJwaru vi maieriai s'aviq,the facility, m
-(a)-The rccetcr ic chut down, and
-(b}-no-work-is-in-progress 4nvolving-handling-oMuel-experiments-or-fesotor-core-related maintenance opcretionc, or comova! cf ac:lvatcd hardware 4 rom thc pool-
% C. 1.3 Facility Reactor Operation Facility Reactor operation shall mean any condition wherein the facility reaetor-is not secured shutdown D 1.4 Decommissioning Activities Decommissioning activities shall mea 8 hose activities required to remove the facility safely from service and reduce residual radioactivity to a level that permits the release of the facility l to unrestricted use and termination of the license. These activities willinvolve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility.
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-,,, ) status means that the facility u vus sou s c ul h. has been cense amended to withdraw authorization to operate the reactor and authorize possession only of the reactor, and that the fuel has been removed from the reactor and is maintained in a safe and secure manner in}n approved location outside the Mark I facility.
6 4-4--Standard Control-Red A-standard-control-fod4s-e-control-fod-having-rach-and-pinion-electrio4notor-drive-and setam capabiPtica. lt may Scv; a fuc!cd fc!!cwcr acetion-13 4-s-Transient-controimod i Amendment No. 365 L. _
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Q y 1. 40 Abnormal Occurrence Reportablo Occurrense An abnormal reportable occurrence is an observed inadequacy in the implementation of either administrative or procedural controls such that the , inadequacy caused, or could have caused, the existence or development of a condition which resulted, or could have resulted, i meterric." c' % ~Mr outside the requirements of the Technical Specific ions.i-end any-of-the4onowing whichecours4uring4eactor-possession > c .l; &, a [rac.;l l 3 Amendment No. 365 L
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5 i Amendment No. 365 - i l i
T' dash 2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area. D 3.0 ftEACTOR BUILDING U Y Until such time as all SW- -_"5.. 5..Y.... .g. ..u u,. . ..- Y.. .U.. ..$'.**-- .. ..E.. the facility, the following ventilation requirements shall apply: 3.1 Controls for the ventilating system shall be located in the facility. l 3.2 The reactor room ventilation shall be separate from the rest of the building ventilation. h 3.3 Adequate recietance to !cakage of cir from the reactonoomshahe-veritified annua 4y, (inter /c! not to exceed 46-monthsbend anytime the roG? hatch-has beenopened-and-reclosed:
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ctcmsaJ d w.Oe4 3.3 During to ensure the:- issionin decoq??!?%g activities, +c;r.h.~.<sh&ll w kerh t'sL ua b& opwable is maintained at a negative pressure with respect to the surroundin areas,uk % WM h k Wr~ % M
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43.0 REACTOR POOL h- pt(cqM-Qif R pb sk 6 b.- emnd.' d' *** 3 T)f 43.1 Until drained as a part of decommissioning, the minimu levelof the pool water shall be nc !ccc th~ 12 inches below the referencef5Yt e top of the pool. The reactor cccc cha!! be "Why naturc! convective water--flow: Obeve the top-of-grid plate. Tha- reb x - p.4;d is 4hPol % ? M b lac fu!. 9, A,1 4. , ,3 wWg ekh
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E? k$ D . w lit toI'*4tr?nrJ. 4.2 Llc Jue taiUnfilsuch time l water Is drained as aas partthe pobv'ipM va.Nd*4 of decommissioning, all M' *ll N Bh fuc! c!cmontc, control-roder end major cativated-components of thc rocctor havo bcon rcmovedircm thc rccctorpoc! cnd, the pool water shall be sampled for conductivity at least weekly. The conductivity of the coolant shall not exceed 5 micro-mhos per centimeter averaged over any one calendar month. 3 3.5 The rocciorsha4-not-beeperated whi!c the bulk-pooMemperature-exceeds 650G: 5.0 REACTOR FUEL p* -6+ No reactor fuel elements or control elements with fuel followers shall be located in, stored in, or moved into, the reactor core structure or reactor facility.
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o,cm,nryno wv ivv cnom. e g A1 The core-shalLbc cn acccmbly of4tandard41ranium-zircontum-hydride 4uek4ements placed-if146ght watcr except for-ad i acenter-nonadjacent positionseasufned-by startup-sourocc, vc-tica! thimb!cc, voidsr oontrobrodsrm-coreexperimentsr and rabbit 4acilities g 4.2 Standard 4uetelemente chc!! have the-fo!!cwing characteristiost a) Maximum-uranium-content in 94wt-%
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F 1 i 3ak 65.0 CONTROL AND SAFETY SYSTEMS-i B 65.1 Control Systems l l The poison section of the control rods which may remain in the facility shall contains j borated graphite or stainless steel, B4 C powder or boron or its compounds in solid l form, cadmium, or the rare earth poisons in solid form clad with the materials authorized for fuel-element cladding. The control rods may contain flux traps and I may be equipped with fueler non-fuel followers. G,F 64.2 No reacter fuc! c!cmente or-sentrot-c!cmente with fac! fc!!cwcrc chc!! be i Ae0,ie M gucA located in, ctored in, or-moved into, the reactor-core-structure-Ya bbd - 5.1.3 l f\ delete l A -5.1 A dc!cic l l Fh ---5.1.5 dc!cte 65.2 Safety Systems i 6 5.2.4 The reacter cafety cyctemc and the accosiated-metruments neccccarj to l provide the cerams-#sted in Tab!c ! cha!! be-soerable-durmg-reacter operate-S 5.2.2 During4eactor Operationrthe applicab!c interlocks chown in Table-1-shall-be opcrab\c. D 5-24 Until such time as h..?."N..W...... ..M-Y. ,.5..
. . . -F, M.. . ..."."..~.'.~d c~"poncnt: cf *ho reec!cr ha': bcon rc... . J :.G.T the facility, radiation monitoring systems shall be operable as follows:
- a. An area radiation monitoring system capable of activating an evacuation alarm. '
C b. When the facility reacter is not secured, a continuous monitoring system for airborne activity having a readout and audible alarm which can be heard in the facility 4 easter-and-sentro! rooms. b c. dc!cte These systems shall be calibrated annually and their setpoints verified monthly. For periods of time for maintenance or repair to the above systems, or during periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate alternate or portable radiation monitoring system (s). 8 Amendment No. 365 l i
%B.OA g 6 2.A The4eactor-safety-systemeW a etc%p-channel-shan-be-verified-to-be ! operab!c at !ccct once-euch day the-reactoras-operated;-unless-the operation extends-continuocc!y beyond-onc day, ' which--case-the ; operabinty-of-the-reacter cafety cyctem need on!y be verifMxi-prior-to-lhe l extendedoperation l A -&2E dc!cte S &3 Fe!!owing maintenanceer-moddicahon-of-the-control-or-reactovdety-systemsA l affected-syctcm cha!! be verified-to-be-operable-before-ocmmening-a-reactor operation: (, Following maintenance ormodification of the radiation monitoring systems, tho affected system shallbe verified to be operable before returning it to routine operations. i l 1 i I i l l 9 Amendment No. 365
bass _ B 6-0--FUEL-STORAGE g e4 ,
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6 7-5 The maximunweactivity worth-of any trancient centrol-rod-sha"r-ce $3.00. l l l 10 Amendment No. 365
S 8.0 EXPERAENTS h de m
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ms- , 1 pJ might4esuit-from+xperiment malfunctionr experiment '!cadinger j void +ng, removal or insertierroMperiments:
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Q> r--Experimente having4eactivity-worths-greater-than44-004ha4-be securely 40cated-cr factonedhprevent inadvertent reactivity 4hanges during4eactor-operations-
@ 8:2-2-Explccive materiais-suches-gunpowder, dynamite, TNTrnitroglycerintor PETN may be irrad+ated in the reactor coreer-reactor-pooksubject404he follow +ng4cnditionc:
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f3 8.2 A Fueled +xperiment: which are noteovered-elsewhere in the Tectwcal L, Amendment No. 365
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l 13 l Amendment No. 365
h7LeEG B " Sottoints40percenteboveendtetow-theeperating-current setting-for4he-fumace-g 8.2.6 The4n-coreessemblies4romene-ormerepneumatie4ransfersystemsmay be uccd in con} unction-with-the4rradiationef-materials-These-units-may remain in the core duringether reactoreperation-The-pneumatio-transfer systems-may-be-actuated 4y-underpressurser-overpressure-of-gas propc!!cnt. ,^ny in cere-pneumatic acccmbly4erminue may be-shielded-with absorber-of thermal-neutronsprovided the neutronebsorber4s-en4ntegral part-of4hc ccccmblymonstruct+on-6 8.2.7 Specimens-of-U-235-dispersed 4n-graphtte-cr in the formof-coatedmarbide partic!cc may be4rradiated-under-cond+tionc which ! cad 4c c tota! inventory of4od+neasotopcc 121 135 inexcccc of 5 curiec but no grector than46 curiester-spec + menr provided that the operimensere40ubly-encapsulated orr4f cing!y casapsulatedrplaced in Occ!cd camp!c container-The capse!cc cha!! be !ccated at !cact464eet-below4he-poc! curface during irradiation-T3 8.2.8 !f-anexperiment fails cadfc!caccc material-whishan4he-judgmentef4he Physicist-in-Chargecr hic designated-altemater could4amage4he-reactor fuekor-structure 4y-corrosen-cr other meanc, phycica! inspection +han be performed 40-determine the consequences-and-need4or-<x>rrective action: The resultsef4heinspection and-any-corrective action 4aken chc!! be reviewedty4heCiticality-and-Radiation Safety Comm+ttesend4etermined40 be-satisfactory-before-reactor-operation 4s-resumed: [3 8.2.9 ,^ ny-additions rmodificatione, or maintenance to the core-and4tsessostated support 4tructure, the poolor4tspenetrationc, thepooLoeolant-systemrthe rod-drivemechanicmc, or the roccior4afety-Gystem4ha4-be@ade-and tested 4n-accordance-with4he-spes+ficationc te which the cyctemc were originally-designed and fabrisateder4e4he+pecificationsepproved-by-the Gritica!:ty and Radiction Safety Committec. ^, cystem4haltnottemonsidered operable-untibafter it is cuccessfu4y4estedt g 8-2AO-Explosivematerialemaybefed+ographed-using-neutronteams4ronHhe reactor-subject 4o4he4ollowing4onditionst
- c. The radiographyof-exploravesprocent in thetcam at anyone4ime O sha44e4imited4edevicetroontaining4neggregato no more4han4 pound +quivalent-TNT-withmindividuct devicecontainingmore4han 0-2 pound-@t-gram)-equivalent TNT cacasedanemetal<ase-I4 Amendment No. 365
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yv. .e .h..e.i.t .A.n .n.,..i.n..i.m. ..i.,.~.4 l< l t l i 15 Amendment No. 365
ba#SS - D -- 3. Personnc! handling +xplostve-dovice: chc!! be provided-withend cha!! uce cpecial equipment-as4equiredrs uches-nonsparking toolsr oonductive footwearrpersonnc! protective +quipmentrand grc' *. . _~d ..^ d '.'.'^d.'~",'.'. .~~'". . ^~" . -C,,r"I^".I.'.'^.
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A PJ Unchic!dedrhigh-frequency-generetmgepparatusshaltnot-be operated within 504eet<f any type of detonators: 6 -E . t A.ppropr'm6n~ ~ .A,f,A.D. . A. .llM.t,'.'.' .. , . ~ .an
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f t".u, . .l n.otes, whicMdent#' y pctentic! hazards-to-personnc!, chc!! be !ncorporated-into4he work-procm~am .. ~..m..~,a .in.,n.~er aocuments <~m..
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@ --6. During prcconceef4xplccivcc in the reactor-roonh-no4mokinger c r.
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O 9. "'I wmumScrconnc! chaltbe-present during4adiographyof ex ^r '~^ , I. ". _ . b 40. Personnet-whawlf-perform the neutron radiography-shalf-have trammg4Mhehazards-ofexplccivc handimgend-shaltbe ap~r. ~. . .ma u.,y4u.~n,r.~n,.m. r.
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, . s, . .~ .hn.e 4074 16 Amendment No. 365
Y-msQ 79.0 ADMINISTRATIVEREQUIREMENTSCSITROL4 C, Y -U::lll cuch !!me es decc.~ mice!cn'ng ect!"itieg ere comp!e!ed !c tbc cMent that c!! major
-cct! cted h&edw&r& h&5 l a;; ti&&ii iiirruvud livius iis& faciliiy, iisa luiivwiriu adiarisulatrative r&qw&isi&iilo 5h&ll &pgly 79.1 Oraanization The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, both of whom shall be licensed senior operators of the facility.
The minimum qualification for the Physicist-in-Charge shall include a Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated alternate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart: f m { v b P = w ee Vice President m.___,a Cognizant vice v-v ~ '~~ eresiaent ~ Alternate Director Licensing, Safety
& Nuclear Compliance Criticality Healto riiys. -
Ph"e:8' in charr Committee
- r. me.m, e.,u Q Wkkl Direct Reporting
--- Functional Support / Oversight 17 Amendment No. 365
I 11 8 lI l l 1 1 1 ________--__._._g i l i l i I . ij li 11 i)f i i l l I I i 1 1 I I i I i i I i i f -- I e i i : 1 I I I I l i i 1 1 1 I I I I I l I i 1 il 11I 8 Il 4
Gads 79.2 Criticality and Radiation Safety Committee
~~D, F3 C a. There shall be a Criticality and Radiation SafetySafeguards Committee (CRSC).
The CRSC or a subcommittee thereof which shall review activities of the facility to assure criticality and radiation safety. This Committee shall be composed of at least four members selected by the Cognizant Vice President, or a designee, considering their experience and education with regard to the various aspects of nuclear physics, chemistry, radiological health and statistics, as well as appropriate experience in other disciplines such as metallurgy and engineering. Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned the responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with the that facility,
- b. The Criticality and Radiation Safety Committee shall be in accordance with a written charter including provisions for:
A 1. Holding meetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chairman of the CRSC at times when such meetings are deemed appropriate. k 2. Having a quorum when a majority of the members attend. A 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or his designee. Evidence of approval of the participating members of the CRSC shall be obtained before distribution, k A dc!ctc 4 5. dc!cte A S. dc!ctc
- c. The Criticality and Radiation Safety Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the Facility annually, but at intervals not to exceed fifteen (15) months.
- d. The responsibilities of the Committee or designated subcommittee thereof include, but are not limited to, the following:
g -b Review and approva! cf experimente eti!!:ing thc4cacter faci!:tice in accordence with Section 8.1 i l
\
i i i l l l 18 Amendment No. 365
6356_ l i A 12. Review and approval of all proposed changes to the facility, procedures, ' and Technical Specifications; F 3FN 23. Determination of whether a proposed change,-testrer experi.Mo constitute an unreviewed safety question or a change in the Technical Specifications;
- 34. Review of Facility records;
- 45. Review of abnormal performance of plant equipment and other anomalies; and pq2
- 56. Review of unusual or abnormal occurrences an44ncidentsM h are Reportable Occurr{nces under 10 CFR 20 and 10 CFR 50.
79.3 Written Procedures , Written instructions shall be in effect for the following items. The instructions shall be adequate to assure the safe possession of the reactor but shall not preclude the use of independent judgment and action should the situation require such: B,'D a. Testing and calibration of instrumentation, controls, and radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications. A b-delete k bo. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support. l'6 --d--Fuel c!cmont end experiment loadmger-unloadmg-
% 0. delete BJ of. Maintenance of systems necessary for assuring the integrity of the fuel-or otherwise maintaining the reactor in i'OL ctets aCCoc h w J M L Jhensc.
p dg. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormalfeactivity changes. D e. Decommissioning activities (consistent with an approved Decommissioning Plan). 19 Amendment No. 365
StQS. Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC). Temporary changes to the procedures that do not change their original intent and do not constitute an unreviewed safety question (as defined in 10CFR50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented E and subsequently reviewedpy the CRSC. ha up . E. 79.4 Action to be Taken in the _Event of!@r% eta Occurrence V b in the event of a abnormal repciab!c occurrence, as defined in Section 1.7-40 of the Specifications, the following action shall be taken:
- a. The Physicist-in-Charge or designated alternate shall be notified and corrective action taken with respect to the operation involved.
-A b. The Physicist-in-Charge or other person notified under Section 79.4a shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, ideatified in Section 79.1.
- c. A report shall be made to the CRSC which shallinclude an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence.
A d. A report shall be made to the NRC in accordance with Section 79.6 of these Specifications. C 79.5 facifty-Plant Operating Records _ in addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared of at least the following items and 1 retained for a period of at least five (5) years: d.[ a. Normal reactorplant operation and atus;
- b. Principal maintenance activities; E c. Abnormal $0% $10 occurrences;
- d. Equipment and component surveillance activities required by the Technical Specifications;
- e. Gaseous and liquid radioactive effluents released to the environs; l
20 Amendment No. 365
i W*0Lk f, Off-site environmental monitoring surveys;
}:~ Skk-97--Fue! irventories-and4ransfersa d I Facility radiation and contamination surveys; D [4t"'M$ PrErM ddf' %* 'Mr oc W sopri d bad *" 28 p.
J . Radiation exposures for all personnel; 3 + . Experimente pedermed Wth the reactor; l A Mpdated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility). T),f\ lf Decommissioning / dismantlement activities. , 79.6 Reportina Requirements i In addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows:
- a. A report within 24 hours by telephone or facsimile to the NRC Operations Center:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personalinjury, or exposure; Y
A 2. Any abnormal occurrences as defined in Section 1.%f0 of these Specifications.
- b. A report within 10 days in writing to the Document Control Desk, USNRC ,
Washington, D.C. 20555: g 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written report (and, to the extent possible, the preliminary telephone or facsimile report) shall describe, analyze and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event. Y A 2. Any abnorma! occurrence as defined in Section 1.X40 of these Specifications. 21 Amendment No. 365
h,s c
- c. A report within 30 days in writing to the Document Control Desk, USNRC ,
Washington, D.C. 20555: B 4, ,A,m,,,
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Amendment No. 365 1
1 bads - I g 6. .^cummary of4he-natureendemeuntef4ad+oactive c5fluents40!ccced er discharged 4c the envirenc beyond the effective control of the licencec 0c meccured-ater-prior 4e-the-pointef-such4elease+r dissharger g 7 ^ dessription of any environmenta! cuveyc performed-outsde4he facility: C 8. ^ cummaryeffadiationexposurerrressived by the facility personnel and vicitors, including the dctec and time of-significant expccure, and a brief summar/ cf4hefecu!!c of radiction andsontamination curscyc l performed-within the facility: E,F df. Commencing in 2000 4999, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission by April 15 of each year, providing the following information: 3D 1. A brief narrative summary of: (1) hNhb ayEN 7 e
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- 2. Discussion of the major maintenance operations performed during%a g,'the period, including the effects, if any, on the safe possession of the reactor, and the reasons for any corrective maintenance required.
- 3. A summary of each change, if such changes have been made, to the facility, or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.
- 4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.
- 5. A description of any environmental surveys performed outside the facility.
l 6. A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility. T), (~ 8.0 FACILITY nPPRA TInNR QV The following activities shall be conducted in the facit. J rs.it % W % .tce d 1 D p' a) Maintenance, monitoring, controVprotection of personnel, and security activities
$ as defined in approved procedures (see Section 7.3).
b) Decommissioning in accordanc e with tb. Oc cpprovc:ChlicmsW T)y VR# a yrcccdurcc (consistent with an approved Decommissioning P an} 1 l l l 23 ' Amendment No. 365
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TRIGA Reactors Facility l TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R-38 JUNE 1999 Proposed Amendment 36
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i TABLE OF CONTENTS - I Page No. 1.0 Definitions.... . . - . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 Site................................................................ . . . . . 2 3.0 : Reactor Buliding.... . . . . . .. . .......... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 Reactor Pool . .. .... .... ..... ...... ....................................... 2 1 5.0 Reactor Fuel... .. .. . . . . . .. . . . . . .. . ..... . 3 I 60 - Control and Safety Systems .. . .. . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.1 Contiol Systems . . .. ......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 3 6.2 Safety. Systems ..... . ........ . . . ..... . .... .. . .... . . . . . . . . . . . . . . 3 ; 7.0 Administrative Requirements ........... .. . ... .. . ........ . . .... ... . .... .. .. .. 3 7.1 Organization ....... ... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7.2 Criticality and Radiation Safety Committee . .. ... ........... . . . . . . . . . 4 7.3 Written Procedures ... .. .. ... ... ....... . .. ......... ....... . .. . . . . . . 5 7.4 Action to be Taken in the Event of a Reportable Occurrence . . . . 6 7.5 Facility Records . .... ..... ...... . . . . . . . . . . . . . . . . . . . . . . . . 6 7.6 Reporting Requirements .... ...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 8.0 Facility Operations.. . .. .. . .. ... . .. .. . .. .. .. . . ... .. . .. . . .. ... .. . .. .. . . 8 1 1 1 i l 1 i Amendment No. 36
l l l APPENDlXA l License No. R-38 TECHNICAL SPECIFICATIONS : FOR THETORREY PINESTRIGA MARKI REACTOR l DATE: JANUARY 21,1972 1.0 DEFINmONS l 1.1 Facility l l Facility means the building housing the disassembled reactor plus systems, components, etc. associated with possession and decommissioning of the reactor. 1.2 Facility Secured l Facility secured shall mean that condition where no decommissioning activities are in progress in the facility. 1.3 Facdity Operation Facility operation shall mean any condition wherein the facility is not secured. 1.4 Decommissioning Activities l Decommissioning activities shall mean those activities required to remove the facility I safely from service and reduce residual radioactivity to a level that permits the ! release of the facility to unrestricted use and termination of the license. These activities will involve the handling, surveying, packaging, and dispositioning of radioactive materials in the facility. 1.5 Decommissioning Status Decommissioning status means that the facility license has been amended to withdraw authorization to operate the reactor and authorizes possession only of the reactor, and that the fuel has been removed from the reactor and is maintained in a safe and secure manner in an approved location outside the Mark i facility. 1.6 Operable A system or device shall be considered operable when it is capable of performing its intended functions in a normal manner. 1.7 Operating Operating means a component or system is performing its intended function. 1 Amendment No. 36
o { l 1.8 Abnormal Occurrence f An abnormal occurrence is an observed inadequacy in the implementation of either ) administrative or procedural controls, such that the inadequacy caused, or could have caused, the existence or development of a condition which resulted, or could have resulted, in a facility condition outside the requirements of the Technical Specifications. 1.9 Measured Value The measured value is the magnitude of that variable as it appears on the output of a ! . measuring channel. 1.10 Measuring Channel l A measuring channelis the combination of sensor, interconnecting cables or lines, amplifiers, and output device which is connected for the purpose of measuring the value of a variable. 1.11 Channel Calibration l l A channel calibration consists of comparing a measured value from the measuring j channel with a corresponding known value of the parameter so that the measuring channel output can be adjusted to respond, with acceptable accuracy, to known values of the measured variable. 2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area.
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3.0 REACTORBUILDING Until such time as all decommissioning activities have been completed in the facility, the following ventilation requirements shall apply: 3.1 Controls for the ventilating system shall be located in the facility. 3.2 The reactor room ventilation shall be separate from the rest of the building ventilation. 3.3 During decommissioning activities, tenting or an equivalent confinement barrier shall be placed around the work area and an associated air ventilation HEPA system shall be operating to ensure the work area is maintained at a negative pressure with respect to the surrounding areas and the exhaust pathway to the environment is controlled and monitored. 4.0 REACTORPOOL 4.1 Until drained as a part of decommissioning, the minimum level of the pool water shall be 12 inches below the reference point at the top of the pool. The reference point is marked on a straight edge affixed to the liner at the top of the pool. This point is located 91/2 inches from the top flange of the poolliner. 2 Amendment No. 36
l l 4.2 Until such time as the pool water is drained as a part of decommissioning, the pool water shall be sampled for conductivity at least weekly. The conductivity of the coolant shall not exceed 5 micro-mhos per centirneter averaged over any one calendar month. 5.0 REACTOR FUEL No reactor fuel elements or control elements with fuel followers shall be located in, stored in, or moved into, the reactor core structure or reactor facility. 6.0 CONTROL AND SAFETY SYSTEMS 6.1 Control Systems l The poison section of the control rods which may remain in the facility contains borated graphite or stainless steel, B4 C powder or boron or its compounds in solid form, cadmium, or the rare earth poisons in solid form clad with the materials authorized for fuel-element cladding. The control rods may contain flux traps and may be equipped with non-fuel followers. 6.2 Safety Systems Until such time as decommissioning activities are completed in the facility, radiation monitoring systems shall be operating as follows: l
- a. An area radiation monitoring system capable of activating an evacuation alarm.
- b. When the facility is not secured, a continuous monitoring system for airborne activity having a readout and audible alarm which can be heard in the facility.
These systems shall be calibrated annually and their setpoints verified monthly. For periods of time for maintenance or repair to the above systems, or during periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate alternate or portable radiation monitoring system (s). Following maintenance or modification of the radiation monitoring systems, the affected system shall be verified to be operable before returning it to routine operation. 7.0 ADMINISTRATIVE REQUIREPENTS 7.1 Organization The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, both of whom shall be licensed senior operators of the facility. The minimum qualification for the Physicist-in-Charge shall include a Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated 3 Amendment No. 36
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c 1 1 I alternate, for safe possession of the reactor and its associated equipment and for I limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart: VI Ps af.nt
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--- Functional Support / Oversight 7.2 Criticality and Radiation Safety Committee
- a. There shall be a Criticality and Radiation Safety Committee (CRSC). The CRSC or a subcommittee thereof shall review activities of the facility to assure criticality and radiation safety. This Committee shall be composed of at least four members selected by the Cognizant Vice President, or a designee, considering their experience and education with regard to the various aspects of nuclear physics, chemistry, radiological health and statistics, as well as appropriate experience in other disciplines such as metallurgy and engineering.
Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned the responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with the facility. l b. The Criticality and Radiation Safety Committee shall be in accordance with a l written charter including provisions for: 4 Amendment No. 36
- 1. Holding meetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chairman of the CRSC at times when such meetings are deemed appropriate.
- 2. Having a quorum when a majority of the men'bers attend.
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- 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or i his designee. Evidence of approval of the participating members of the j CRSC shall be obtained before distribution. '
- c. The Criticality and Radiation Safety Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The l CRSC or a subcommittee thereof shall audit the Facility annually, but at intervals not to exceed fifteen (15) months,
- d. The responsibilities of the Committee or designated subcommittee thereof I include, but are not limited to, the following:
- 1. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications:
- 2. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or a change in the Technical Specifications;
- 3. Review of Facility records;
- 4. Review of abnormal performance of plant equipment and other anomalies; and
- 5. Review of unusual or abnormal occurrences and incidents which are Reportable Occurrences under 10 CFR 20 and 10 CFR 50.
l 7.3 Written Procedures ! Written instructions shall be in effect for the following items. The instructions shall ; be adequate to assure the safe possession of the reactor but shall not preclude the ' use of independent judgment and action should the situation require such:
- a. Testing and calibration of instrumentation, controls, radiation monitors and radiation protection systems necessary to meet the requirements of the Technical Specifications.
- b. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.
- c. Maintenance of systems necessary for maintaining the reactor in accordance with the license.
- d. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal changes.
5 Amendment No. 36 i
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- e. Decommissioning activities (consistent with an approved Decommissioning Plan).
Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC). Temporary changes to the procedures that do not change their originai intent and do not constitute an unreviewed safety question (as defined in 10CFR50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed and approved by the CRSC. 7.4 Action to be Taken in the Event of an Abnormal Occurrence in the event of an abnormal occurrence, as defined in Section 1.8 of the Specifications, the following action shall be taken:
- a. The Physicist-in-Charge or designated alternate shall be notified and corrective action taken with respect to the operation involved.
- b. The Physicist-in-Charge or other person notified under Section 7.4a shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 7.1.
- c. A report shall be made to the CRSC which shallinclude an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence.
- d. A report shall be made to the NRC in accordance with Section 7.6 of these Specifications.
7.5 Facility Records in addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared of at least the following items and retained for a period of at least five (5) years:
- a. Normal reactor operation and facility status;
- b. Principal maintenance activities;
- c. Abnormal or reportable occurrences;
- d. Equipment and component surveillance activities required by the Technical Specifications;
- e. Gaseous and liquid radioactive effluents released to the environs;
- f. Off-site environmental monitoring surveys;
- g. Fuel inventories and transfers;
- h. Facility radiation and contamination surveys; 6
Amendment No. 36 l I
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- 1. Experiments performed with the reactor or in support of decommissioning; J. Radiation exposures for all personnel;
- k. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility).
- l. Decommissioning / dismantlement activities.
7.6 Reporting Requirements in addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows:
- a. A report within 24 hours by telephone or facsimile to the NRC Operations Center:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personalinjury, or exposure;
- 2. Any abnormal occurrences as defined in Section 1.8 of these Specifications,
- b. A report within 10 days in writing to the Document Control Desk, USNRC , l Washington, D.C. 20555:
- 1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written report (and, to the extent {
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possible, the preliminary telephone or facsimile report) shall describe, analyze and evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event.
- 2. Any abnormal occurrence as defined in Section 1.8 of these Specifications.
- c. A report within 30 days in writing to the Document Control Desk, USNRC ,
Washington, D.C. 20555:
- 1. Any significant changes in facility organization or personnel for which minimum qualifications are specified in these specifications.
- d. Commencing in 2000, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission by April 15 of each year, providing the following information:
- 1. A brief narrative summary of: (1) actions taken for decommissioning of the facility, (2) current facility status, (3) any changes to the l decommissioning schedule, and (4) a summary of radioactive material shipments.
7 l Amendment No. 36 l l
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- 2. Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe possession of the ;
reactor, and the reasons for any corrective maintenance required.
- 3. A summary of each change, if such changes have been made, to the facility, or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.
- 4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.
- 5. A description of any environmental surveys performed outside the facility.
- 6. A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief
- summary of the results of radiation and contamination surveys l performed within the facility.
8.0 FACILITY OPERATIONS l The following activities shall be conducted in the facility: a) Maintenance, monitoring, control of radioactive material, protection of personnel, and security activities as defined in approved procedures (see Section 7.3). J b) Decommissioning in accordance with the facility license and consistent with an approved Decommissioning Plan. 8 Amendment No. 36 l}}