ML20196C357
| ML20196C357 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 06/16/1999 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20196C354 | List: |
| References | |
| NUDOCS 9906240010 | |
| Download: ML20196C357 (45) | |
Text
{{#Wiki_filter:i TRIGA Reactors Facility l TECHN CA_ SPECIFICATIOhS TRIGA NARK F REACTOR 1 l Facility License No. R-67 i hBS55 Tu n e_. h =MAY 1999 Proposed Amendment 45 9906240010 990616 .ci PDR ADOCK 05000163 P PDR m
Bads , srS6s 9 I his weul fe (led.:. TABLE OF CONTENTS ihe-$ci oT j adg 6 'as. Page No. 1.0 Definitions... . .. 1 2.0 Site .
. . 2 3.0 Reactor Building.. .. .. . . .
2 4.0 Reactor Pool .. . 3 5.0 StoredReastor Fuel Description Gore... . . . . 3 6.0 Control and Safety Systems.. . . . . . 6 .r 6.1 Control Systems.. . . . . . . 6 5' 6.2 Safety Systems . . .. . .& y 7.0 Fuel Storag& . ... . . . Ca 8.0 Administrative Requirements. . . . . . .Ne) C, 8.1 Organization.. . . 7fetC, 8.2 Criticality and Radiation Safety Committee.. . .4 fay 7 8.3 Written Procedures.. . . . 8 8.4 Action to be Taken in the Event of an Abnormal Occurrence. Sfe)- T 8.5 Facility Records.. . . . .. .. .8(a} 9 8.6 Reporting Requirements.. . .. . . &(by 9 9.0 Facility Operations.... .. . . . . . 10 I I OA-Reactor-Operatienc . 8 9.d himumoperatingPower-L+ve! . 8 9.2 Transient-Operation . 8 0.3 LowPc'ver and-Suboriticc! Recotivity-Worth of-Experimentc. . .
.9(a) 9.4 SpectaLGorec.. .
10 40:O-Experimentc. . 10(a) 10.1 ExperimentakApprovaLProcedurec . 10fa) 10.2 Experimento! Limitationc. 11 Tablo !- Mimmum Reactor 4afety-Systei.SScrame . 16 Table 4!: Minimum Interlock . . 16 Amendment No. 45 3
f Appendix A License No. R 67 l ' TECHNICAL SPECIFICATIONS for THE TORREY PINES TRIGA MARK F REACTOR h @~ Date: September 27,1968 C Jhe d!mancinac, cccureman'c enri n'har niimaricel "3'ues gb>en la thccc cpecificatienc-een hw -d!!for from actua! "e'uee cedng te 'hc normc! ccnciruct!cn and manufactur!ng tolerenm nr _ r ne ral no}c ncrmai accmacy of tiiMiuiiiantatier.. 1
.p <>nsM e a te & M DEFINITIONS ree-c.1w (wc.T)1.0 gy 1.1 Facility Rcactor Shutdc=n sp Mb Facility means the building housing disas mbled reactor plus systems, components, etc. associated with possession f the reactor, including fuel storage. Reaetor chutdown cha!! mean that4hc reactor ic cubestieal-et-e#-4imes by at Iccci cac dc!!cr of rccc4ivity-1.2 FacilityReac4er Secured 13 3 '
Facility-Reaeter secured shall mean that condition whereiruno 4ecee/c:p::i; imh 6 My achvihas or p'c;'ccc !~:c!v ng handling of fuel,cr rcmce;l af actlvated or ccntaminc!sd. ?n' in groyress at; hard: ara 0, i;;;;;rlc! ?cm the facility. (a)-- The rccctor ic chut down c-and (b) nc work ic in progrecc involving-hand!!ng of fuc!, experimenic or feaeter eere-related maintencnce operationc or removc! Of activated componente-from-lhe-pool-8d 3 1.3 Facility Reseter Operation FacilityReactor operation shall mean any condition wherein the facility reactor is not secured shutdown g 1.4 Decommissicning Activities Standard-Gontrol-Rod Standard eentrebfod chc!! mcon any centrol rcd having rack cad pinion, c!cotri(HRotor-d4VO cnd ccram-eapabilities-Decommissioning activities shall mean those activities required to remove the facility safely from servica and reduce residual radioactivity to a level that permits ; the release of the facility to unrestncted use and termination of the license. l These activities willinvolve the handling, surveying, packaging, and ' dispositioning of radioactive matarials in the facility.
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- 1. 5 Dee eWYn ?bnse Status Pccoah acmaiM.
w a v. , 9u,4_'tM-.~a {!'CL) status means that the facility license has been amended to withdraw authorization to operate the reactor and authorizes , 1 possession only of the reactor, and that the fuel has been removed from the i reactor and is maintained in a safe and secure manner in the facility. { l Amendment No. 45 3 ' 1 l J
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@ 1.5 T ran !cn' Centrc! Red Tran;!cn cartre! red chc!! mean any centro! rnd cperated pncumaticc!!y-and with-seram-espabilities-1.6 Operable A system or device shall be considered operable when it is capable of performing its intended functions in a normal manner.
O O *"# "' O 1.4*y Abnormal O cu s w. npExpcrsmont e-a, po< ,} <,e spf u p% ;,.y As idk*d* 't GOlse. E , Tb , G-An abnormal occurrence is: any of the follov, ng which occur; during rccator
- pec;cccion: Experiment cha!! mcca Ony device er meterial which ic expc;cd to cign:ficant radiction frcm the rcccict and is not a norma! part of the reactor.
Q 3 (1,. (a) Any unanticipated or uncontrolled change in subcritical multiplication during fuel storage or handling, Rcutin Expct; ment; cha!! mcon thc;c cxperiment; which have beca prev!cuc!y podccmed ", th!; rcccier. ( (b) An observed inadequacy in the implementation of eijher administrative or procedural controls, such that the inadequacyf880fd*Ve existence or the developm nt nVd tRM NN*A
'a s., pomccia" cf "'c "~ .h-...y ae gjon u'T5Td~
lligpghich,hYca sg the requirements of the Technical Specifications; and-Modified-Routine-Gxperiments-shall4nean thecc cxperiments-not-prewcu;!y performed-irrthis4eactor-whose haccrd; cre ncither cignificantly different nor grcatcr than thc;c for a cimilar reutinc cxperiment pedermedet-the-General ^.tcmics TRIGA Reactors-Facdity-or 6 (ll a w % 4fu l N d. 6 C, (c) Release of fission products from a fuel element,during fuel storage er 3 handling. Special-Experiment cha!! mean c!! cxperiments-which-ere not-routine-or-modsedwoutine-experiments-Q 12 Reacter Scfety System: Reactor-scfety cyctc=0 cha!! mean thc;c cystemsrmoludmg-their-assoc 4ated input circuit;, .vhich cic d;0!gned ic !"t!cic c reacter ; cram for the primary purpc0c c' prciccting the r000:0r. [f 13 Experimen' Safety Syctcm; Experimcri cafety cyclem; chc!! mean thecc cy;tems, including their c000etated input-circuits, .vhich Orc dc0!gned to-initiate-e-scram-for4he-primary-purpose-of protecting an experiment
@ 140-standard-Thermocouple A Otandard thermcccup!c cha!! mean a cheathed chrcm;! O!umc! cr equ:vc! cal thermcccup!c imbedded in the fuc! near the fuc! c!cmenic' vc-tica! midplanc at a-point !c00 tharrenc half thc radiaf4 stance meccured4 rom-the-center-of-the fuc! body.
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6 ftM , 2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area. 3.0 REACTOR BUILDING . . as 4 d dea.o+44b e*%( d'. Until such time as all fuel
'T) y [ ^ ^^"-'"-' " !cd following ventilation requirements shall apply.
"=rd=a om removed from the faciligt the 3.1 The reactor .shall be housed in a closed room built to restrict leakage. The minimum free i volume i:1 the reactor room shall be 11,700 cubic feet. l I
3.2 Controls for the ventilating system shall be loaated in the facility-contro!4oom. 3.3 All air or other gas exhausted from the reactor room during reactor-operation shall be released to the environment at a minimum of 20 feet above ground level. 1 3.4 The reactor room ventilation system she.Il be separate from the rest of the building j ventilation. i h 3. 5- Adequate resistance-to-leakageof-air 4 rom-the recctor4oom.shall be-verified-by measurement-annuallyr(intervaLnot.toaxceed-15 months)-and-anytima-the4oof hatch has been opened and reclosed. v or when a charcoal filter is required for reactor . operations.-The resistance to air leakage shall be at least fle,- where e = 6.38 x-10tm sec/kg, ort /h,' j
} 3. 5 During decommis ning activl' ties and while fuel remains in the facility, air ventilation i systems shall b cpcrab!c-to ensure the reactor room is maintained at a negative pretssure \
with respect to the surroundin areas % y w'gs ) ir c.-.trat.A c.,,,s ouW W. y r,4 -tk. < Qst p m&,, 4.0 REACTOR POOL 3[ 4.1 The stored reactor fuel-core shall be cooled by natural convective water flow.-except as provided for in Section-10.0 covering experiments. nwAre+r Qh(2.) 4.2 During4eactorsperation, Until such time as all fuel has been removed rom the pool and the poolis drained as a part of decommissioning, the minimum level I the pool water shall be ec !::: :.M12 inches atieast 46 feet.below the reference A the top of the pool. late, %. gefcwam< m above t.1 sui & a4helessi.top IT grid-p,Yz,,gQ bef.Q,,,,,g,k
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- R.wvf M pGh., Q . g k b cu w. M 4,3- The poolwater-outlet pipe sha!Lnotexter more 4han-8-feet below the top-of 4he reactor f( . ,4f.p-} wth r e d . ypoolwhen~fuelis h w it n. l .,
being stored in thetore e-Y b(o b bC'j' * ' tcouwA $,f el(34-
- 4. until such tinteallake fuel rhas Psc'id- dve b from been removed *f/'pthe pool and the poolis drained as a part of decommissioning, the pool water shall be sampled for conductivity at least weekly.
The conductivity of the coc! ant shall not exceed 5 micro-mhes per centimeter averaged over any one calendar month. a hvi be.h wNeM. ys T3 N'.9 Vs#d WO. +1me aa d.L f L h4 5 ---The reactor shall 41.s.-not be*'t
/**l, operated the bu
,,, y Q 5.0 STORED REACTOR FUEL DESCRIPTION CORE s.1 No reactor fuel Uoeldares3 38 %
l fr Q h Q ments or control elements with fuel followers shall be stored in the V> B reactor portion f the pool. The core shall be an assembly of uranium zirconium hydride w gg.a. fust-elements-placed-indightwater-except4or-adjacentar-non-adjacent positions-occupied f%, by-startup-sourcesr vertical-thimblesr voidsrcontrotsods rin-core-experimentsrand-rabbit v facilities, RMr Q dMg W Md dM wi% N kMJ ' su @ k stud in % 7.,JL.sy.7 se,4 J.L .n mu r"*" P l - Amendment No. 45 0 (1% pread Wpd O Ce T6[754 Mb< A r~ f b y N,g wJ d inesec %., nk-$u(. b t/~ rat (U0d sp uor Ne<-. c&'3 w e erWe4 wbjeg A#
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bs . p:3 (a) Standar4ccrec chc!! be ccccmb!!cc whereinell4uetelementsere standard 4ue! c!cmento. B lb) Speciatcores4ha44)eelLcareerwhichereeotstandard cores: A E- 5.2 Standard fuel elements shatthave the characteristics listed below: M kAL is" ass %s der .wr d'al 5
- Standard low-enrichment fuel bt oW
- *7in(ecm % .2.1 (a) Maximum uranium content 9.0 wt%
in unirradiated fuel (b) Maximum uranium enrichment <20% in unirradiated fuel (c) Hydrogen to zirconium ratio 0.9 to 1.54 H atoms to 1.0 Zr atom (in the ZrHn) (Iow hydride) 155 to 1.8H atoms to 1.0 Zr atom (high hyride) (d) Cladding material and akunnum 0.020 inch 304 or 304L stainless steel, b>E minimum thickness Incoloy 800, Hastelloy X, or 0.030 inch , aluminum or Zircaloy ! h,C 5.2.2 Standard Fuel Lifetime Improvement Program (FLIP) fuel l (a) Maximum uranium content 9.0 wt% in unirradiated fuel (b) Nominal uranium enrichment 70 %
- in unirradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in ZrHn)
(d) Natural erbium content 1.0 to 1.8 wt.% (homogeneous distribution) (e) Cladding materialand 0.020 inch 304 or 304L stainless steel, minimum thickness Incoloy 800, or Hastelloy-X 5.2.3 Standard low-er.richment fuel with high wt% uranium (a) Maximum uranium content 30 wt% in unirradiated fuel (b) Maximum uranium enrichment < 20% in unirradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHn) Amendment No. 45 39 4
T3aso (d) Natural erbium content 0.4 to 1.8 wt%' (homogeneous distribution) (e) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness Incoloy 800, or Hastelloy-X 5.3 Special fuel elements are shah 4)e uranium zirconium hydride fuel elements,
- 4) E which are not standard fuel elements, having the characteristics listed below.
5.3.1 Special fuel elements with high-enrichment uranium. (a) Maximum uranium content 12.0 wt% in unirradiated fuel (b) Maximum uranium enrichment 95% in unirradiated fuel (c) Cladding materie! and 0.020 inch 304 or 304L stainless steel, minimum thickness Incoloy 800, or Hastelloy-X or 0.030 inch Zircaloy (d) Construction shall be such that calculated clad temperature shall not exceed 500 C at the planned operating level 5.3.2 Special fuel elements with high wt% uranium (a) Maximum uranium content >30.0 to 45.0 wt% in unirradiated fuel (b) Maximum uranium enrichment <20% in unirradiated fuel (c) Cladding material and 0.020 inch 304 or 304L stainless steel, i minimum thickness Incoloy 800 or Hastelloy-X or 0.030 inch Zircaloy for 1.5 inch nominal diameter, or 0.015 inch to 0.020 inch stainless steel, Incoloy 800 or Hastelloy-X for 0.5 inch nominal diameter A
' Scaled according to maximum U-235 content such that a core containing only these elements would require a criticalloading of 2 50 fuel elements.
4(a) Amendment No. 4539
ha6t3 g9 g ' (d) Construc' , is chc!! be such that the calculated clad temperature does shair not exceed 500'C at planned operating level. (e) Special fuel elements with 0.5 inch nominal diameter are cha!! be enclosed in a 0.020 inch metal shroud. The shroud, constructed from one of the above listed cladding materials, has sha!! have a nominal diameter of 1.5 inches. 5.3.4 Any burnable poison used is cha!! be an integral part of the as-manufactured 4)g fuel element. A burnable poison is defined as a material used for the specific purpose of compensating for fuel burn-up and/or other long-term reactivity adjustments. 1 l l i 4(b) Amendment No. 4539 I 1 l
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tedhits-entirety ( Se <- 9 4 Gr W.j u wrWs,ej) i l l l 4 1 Amendment No. 43 5 l l
b~ sis 6.0 CONTROL AND SAFETY SYSTEMS 6.1 Control Systems d- 6M The poison section of the control rods which may remain in the facility shall 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 equi,nped with fuel or non-fuel followers. (3 6.1.2 The number and ocn'iguration of fuc! O!cmonte and controkeds4n-the reactor chc!! be cuches40-maintain the reacter chut down by at !0cct one4c!!ar Of reactivity at a!! timec, cvon if c!! controkods-were removed-C v . 4. .#2 v fh ta 6.aM ww.v g 644-Oeleted s w oe m 6.2 Safety Systems g 6.2.4 The reactor cafety cyct^me and4hc ccccciated instruments necccccrj to provido the cerame !!ctcdan-Tab!c ! ch0!! beeperable dur!ng reactor Operation-Q 6.2.2 During reactor Operat!On, th0 Opp!!Oab!O interlockc chown in Tab!O !! shc!! bc Operab!c. Amendment No. 454 6
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.,a-D 6-22 Until such time as%:ll f; .. :!:mW cc."a;,u
*ro! rede, ~ e-.,m and mejor ec!!t':!cd mm,nnnon!? c!*e reec!c@et'c bccn rc~ct'cd from the facility, radiation monitoring systems shall be operab',e as follows:
o p.c# g (a) An area radiation monitoring system capable of activating the evacuation alarm. [ (b) When the facility reastor is not secured, a continuous monitoring system for airborne activity having a readout and i audible alarm which can be heard in both the facility 4eastor / and control rooms These systems shall be calibrated annually and their set points 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 specincation shall be satisfied if the installed system (s)is replaced with appropriate alternative or portable radiation monitors.
@ 62r4-The4eactoreafetyeystems-ehall4m-verifd4o-beeperableet4 east oncesachday4he4eactoFis-operatedrunless4he-operation-extends continuously-beyondene4ayrin-which-case 4hMperability-of4he reactoreafetyeystemeeedenly4merifiedprior-to4he extended operation-S 6;2E>-Deleted 612,6-Deleted Q
g Whenenectivated charcoabfilter4s-required-for-the4estingef thermionic4evices rits-blower-ehalkbe-verified 4o4)eeperableet4 east once-eachwee4(intervabnot4oexceed4en-days). A compleef4he activatedcharcoatehafLbe4ested-senwannually-{atintervals-not4o exceed-7-#2-months)4o-confirrnecceptable4ew4evels-of water / humidity-content-The4ilter-flowfateshalbbe-verified annually i tote at !cact460-ofm-{ interval not4oexceed46-monthsh i CC# 3-~ Following maintenance or modification of the radiation monitoring controier reactor-safety systems, the affected system shall be verified to be operable before retuming it to routine commencing 1eactor operation. l 1 7.0 FUEL STORAGE 7.1 All fuel elements or fueled devices shall be stored in a safe geometry (kg less than 0.8 under all conditions of moderation). E., ' S 7.2 Q lwh wfS Irradiated fuel elements [E. _f...<cxperiments shfa 6 81 i e sEoY$8 in an array which will permit sufficient natural convection cooling by water or air such that the temperature of the fuel element or fuc!cd device will not exceed design values. Amendment No. 453 7
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O.0 ADMINISTRATIVE REQUIREMENYS g p
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chnllannly 8.1 Organization E.? F - The facility shall be under the supervision of the Physicist-in-Charge or his designated attemate, both of whom shall be a licensed senior operators of the facility. The minimum qualification for the Physicist-in-Charge shallinclude a Bachelor's degree or equivalent academic education and three years experience !n activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated alternate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive maiorial. The reactor shall be related to the Corporate structure as shown in j i the followit,g chart: 7 Vice President hg b _ vira preciaant _ - mgnateo or Cognizant sf; c Alternate President I 1 l l Director Licensing, Safety _
^ Nuvear Compliance
. Criticality mm
- --HesWPEysics Physicist-in-Charge- - -
" Sa"f[
Committee normey mi< Direct Reporting Se'C, t'qbr....,}
--- Functional Support / Oversight fyrb+ sos L
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- 8.2 Criticality and Radiation Safety Committee g p$ {
9
- a. There shall be a Criticality and Radiation Safety 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. l l
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I l C 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 l called by subcommittees of the CRSC or by the Chairman of the CRSC at times when such meetings are deemed appropriate. h 2. Having a quorum when a majority of the membe,6; attend. g 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or his designee. Evidence of approval of the ped.icipating members of the CRSC shall be obtained before distribution.
- c. The Criticality and Radiation Safety Comrnitte;, 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:
- 1. Deleted Review-and approvaLof experiments utilizing the reactor facilf asu4ccordance-with-Section-104; h 1-2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications; 1
l l i l I l 1 I 7(a) i Amendment No. 454 9
b B5h p> g 24. Determination of whether a proposed change,--testrer.Ar p.,4- experiment would constitute an unreviewed safety question or a change in the Technical Specifications, b 34. Review of Facility records;
- 44. Review of abnormal performance of plant equipment and other anomalies; and
{/ h 54. Review of unuouc! Or rmal occurrences end incidents %t which are Reportable Occurrences under 10 CFR Part 20 and 10 CFR Part 50. { i 8.3 Written Procedures j i 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 i preclude the use of independent judgment and action should the situation require such: Oh a. Testing and calibration of instrumentation, controls, end 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.
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- c. Fuel element aDing. end-expen'menF-loadmgtw, < loading:
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- d. Maintenance of systems necessary for assuring the integrity of the fuel or otherwise maintaining the reactor in PO! ::ctu .
acuc Am w;1f4 L li%t ,
- e. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal reactivity changes.
D 1. Decommissioning activities (consistent with an approved Decommissioning Plan). I Changes which alter the original intent of the above procedures shall 4 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 10 CFR 50.59) may be made by the Physicist-in- 4
% Charge. All such temporary changes shall be documented and I subsequently reviewed by the CRSC. !
'and appe,vej j h H::n: c! 9.' Waugh S.S cn lh: !c!!cwing p2gn 8(n) nM Rth) l
( 9.0 FACit/TY REACTOR OPERATIONS I
~D ., F The fo!!owing activities shait be conducted in the ***raciitty:d"I, f rah *J M (
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C)% 7 ^ u asintenanw. monitoring, defined in approved wntro; procedures see pp(tection Section 8.3). orpersonnet and security activitie l l 1 8 i I i
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- I h? 3 b) Decommissioning 460nsistent with an approved Decommissioning Plany
' 0, Y c) Fuel storage, handling, packaging and removalin accordance with approved procedures. g 0.* Maximum Operatin;; Pcwer_teve4 g 0.1 1 The-opetal+ng-powef-levc! cf the reactof-shelf-not-be-intentionally reiced above 1500 'i!;watic cxcept for pulcin;; cperations (300 Specificction 0.2). l I 1 9
(Ja TU hM h/ch.! N a q j u in*d 7J in % l-Jt ers,[ce 6 wMin pyhdM h 8A Action to be Taken in the Event of an Abnormal Occurrence in the event of an abnormal occurrence, as defined in Section 1. ofthe h)V Specifications, the following action shall be taken: p2 f a. The Physicist in-Charge or designated attemate shall be notified and corrective action taken with respect to the operation involved. g' G b. The Physicist-in-Charge or other person notified under Section 8 shallnotify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 8.1. ! F, F c. A repor1 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. < h>V d. A report shall be made to the NRC in accordance with Section 8.6 of these Specifications.
$ 8.5 Facility Opcra!!ng Records 7 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: \
l C,E a. Normal reactor operation andhhtatus; h,F b. Principal mu ',tenance activities;
.c c rtibl E c. Abnormal,occu9r e*nces;e.
- d. Equipment and component surveillance activities required by the h)V Technical Specifications; f e. Gaseous and liquid radioactive effluents released to the environs; F* f. Off site enviromental monitoring surveys; p g. Fuelinventories and transfers; l
%V h. Facility radiation and contamination surveys, i Cv ',a upqt .(pΜd
\
.) h adiation expo [sures for allpersonnel;\m% =? JK Lqc&.e sv kf k }<- Updated, corrected, and as-built drawings of the facility (these shall h)V -- be retained for the lifetime of the facility);
& Jk Decommissioning / dismantlement activities.
8(a) Amendment No. 45
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- 8. 6 O%f Reporting Requirements l
In addition to the requirements of applicable regulations, and in no way substituting therefore, 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
- 1. Any accidental release of radioactivity above permissible limits in i unrestricted areas, whether or not the release resulted in property l damage, personalinjury, or exposure; l
h 2. Any abnormal occurrences as defined in Section 1. of these Specifications. l
- b. A report within 10 days in writing to the Document Control Desk, USNRC, Washington, DC 20555:
)
l f 1. Any acc&tL Tl ec! ease of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property i l damage, personalinjury, or exposure; the written report (and, to the { extent possible, the preliminary telephone or facsimile report) shall l describe, analyze and evaluate safety implications, and outline the 1 corrective measures taken or planned to prevent reoccurrence of the i event.
}
h 2. Any abnormal occurrence as defined in Section 1. of these Specifications. \
- c. A report within 30 days in writing to the Document Control Desk, USNRC, l Washington, DC 20555:
{ 1. Any significant variation of measured values from a corresponding predicted or previously measued value of safety-connected operating i characteristics occurring &&; p :::::!:n ! ?: r;::::r; for {k,cea. dor' or W
- 2. Any significant changes in the transient or accident anb' lyses as described in all Safety Analysis Reports; and
- 3. Any significant changes in facility organization or personnel for which ;
ininimum qualifications are specified in these specifications. l
- 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) h E : N h.)) $ ~ ~ :., w u,- ~ w WC$rred sk& h&5 & Nsh HY dowfV he $ Y'stEs* h
- 2. Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe possession of the Q
reactor, and the reasons for any corrective maintenance required. }4.,gm rd;.g h TMateri.1 3. 3 [ A summary of each change, if such changes have been made, to the Wpf facility, or procedures, tests, and experiments carried out under the y) ~ conditions of Section 50.59 of CFR Part 50. [ _4. f A summary of the nature and amount of radioacdve effluents released or discharged to the environs beyond it.a effective 6(b) control of the licensee as measured at or prior to the point of such release or discharge-Amendment No. 45
- 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 signiacent exposure, and a twief summary of the resuns of redishon and contammahon surveys performed within the fedlity.
h2 Si s., - g' O.1.2 The maximum-availathxeess4eastivity-{ cold-with-experimentsr4f anyr4n-p!ccc) chaltbe-
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@ (c) 920*G4orspecialfuebelementsr (b (d) Valucc cc! coted 4or-the-applicable 4ong4ived4uetelements-are as-follows+ )
FueLElement b Location LEU (20-20) FLIP LEU (30-20) incompact 780'G 780 G 690*G Segment Adi acent46 9ne 670 G 676*G 490*G b Water F!!!cc Hole Adjacent tcTwo or 645'G 500 G 405 C b More-Ad}asent Water R!!cd-Holes
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. thermoocuplc c!cment chc!! be-placed in the hottoct4uel h c!cment !ccation next to occh flux trap-A4hermoccuplo c!cment chc!! c!cc be p!cced in the anticipated hottect fuel c!cmont !ccation within4he<ompact-segment 4the-scwe unless4hc flux trap 4s40cated in the hottect coction of the cero. With nc '!ux trap, the thermccoup!c fuc! c!cment-shalLbe located in the anticipated hottoct core-pos4x>n-9 Amendment No. 39
- b. 3. d S 9.2.3-The+naximum+eastwity-worth cf any-transient-esntrol4od+haltbe
$6fA
($ 9.3 Low Pcwcr and4uboriticaLReactivity-Worthef4xperimente Q 9.3.1 Individual experiments havnya-reactivityworth-greater 4han $3.00r-or asombination-of-expenments-hawngs40talworth-greatcr than-$4-00r shalbbe subject to the following-restrictione durimj+eastivityworth measurements (thecc rectrictionedonotepply during theralibration of-contrc'. . ^.d
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Amendment No. 39 . I
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h 9:44-Prior-to-pulsinge-specefcorewhich-has-generated 4nore4han40 MW-hrs-ofenergy-since4hc 'act inspectionof4heepeciaMuel elements-com.ained4hereitirthecc specialfuelelements-havingeo instrumentation +haltbe4neaswd-for4engthend bend--Speciabfuel elements-found40-be-damaged cc de'ined4n-Section-6 6A(d)r6:5-2(b) or-6:6:3(c)-shalkiet be used4n-any further-reactoroperation: h) 9.' A Up4044 geciaMuetelemen+.c, cc cet forthin4ection-6:3:24nay-be added4oe-core rstandard-or-speciatrif4he4emperature-shutdowneo-efficient 4s-demonstrated 4yt I6 (a) The-core-shatthave-previouslyrwithout4helnsertedelementst been41emonstrated4o-satisfy 4he-requirementsof4ection 9;4:2--and I -(b) The core-shalfrwith4he-speciatelementsinsertedrbe demonstrated 4ohavee-power-coefficient-(reactivity 40ss-with increasing power)4 hat 4s4arge-enough4e-reasonably-assure that4he-shutdown-coefficient 4s-at4eastes4argaesthat cpeci' icd 4n-Section-9:4:2: Amendment No. 29 10
h e. 3Ls '
\
P- ) 0.4.5-More than 10 cndep to e fu!! foadegefepecial-fuetelementsresset l forth in Section 5.3.2, may-be-usedineere-providedt 4 l
@ (e) Ecch4ypeofepecial4uel-eced in the above-coreehalf-have been cuccessfully4ested-under-conditions-established 4n Section 9.4.4. l l
l i3 (b) ,^ t ! cast-six-special4ue! c!cments ofeach4ype40-bessed4n the above core-shalf-successfully-undergo 400-poweFeyeles , 00 cet forth4neestions-64-2(a)-or . 5:a(a): l f3 (c) ,^ t !ccct cix cpecial c!cmentsefeach4ypeef49eMo-bessed4n theebove-core-shalf-successfully-undergo 400-poweFpulses l thattroduce4ueHemperatures4n4heseepeciaf46 Jelements l ofet4 east 400*G: l g - (d) Succcccfu! completionef the tectc decaribed494ect+ons , 04-6(a)r{b) rand-(o)+equires-completion of catisfactory4uel ! inspections <cnductc4under Sections-E62-an45&ar
@ (c) The core cha!! meet the requirements onshutdown-ocefficient set 4 orth in Section 9.4.24egardlessef-the-urantumenrichment of the indiv;duaf4cc! c!cments.
g (f) The-spectaf4uc! c!cments in the cere-shalkindergo cureci!!cnce meccuremento deccribed in Section 5.5.2 or 5.5.3. !! w"! be-permiccib!c to count in the 1000Scwcr cyc!cc thoscoperationssonoustedender-Section 9.440r4.46 e --,mn r vne ,-m , um 0V.V b/W h s VIVIL.I 13 %J
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@ 10.1 Experimental-ApprovalProcedures
@ 10.1.1 Routinc experiments 4nay4)eperformed at the discretione4he Physiciet-in Charge-or-his-designatedeltemater without4hc neccccity ,
of-any-further-rev+ew- l
@ 10.1.2 Prior 4operformmg-any4eactorexperiment-whiciusnote+outine experiment, the propeced experiment chc!! be-evaluate 4by-aperson or-personc appointed by the Phycicict in Charge 40 be-respons+ble-for reactor cafety. H0 chat! consider 4he-experiment in terms-of4ts-effect on reactoroperat+onend4hepeccibility andoonsequences-of4ts failure 4ncludir grwhereeigniftsantr onsiderationof-chem o + sal 4
Amendment No. 29 10(a)
l I h_a $i5 S rocctienc, physical integrity, decign life, proper coc!!ng, interactx>n wdh-cero componente, and reactivity c'fectc. Fo!!cwing-a4avorable evaluation and prior to conducting an experiment which is not-a routinc cxperiment, he must sign on authorization form containing4he bacic for the favorable Ovaluation: 3 10.1.3 No cpecial experiment cha!! be performed until4heproposed experimental-procedure for that experiment or type Of experiment has been revicwc1-by4he-Griticality and Radiation-Safety-Committec. O 10.1 A Favorable eva!uction of4hepretective meccurec provided-for-en experiment cha!! conclude 4 hat failure of the experiment wi!! not ! cad to a direct failure of a fuc! c!cment-cr of other-experiments or intedere with mcvement of a control red: h 10.2 Experimenta!Limibtienc l
@ 10.2.1 The fc!!cwing limitationc enfeactivity cha!! apply 40-altexperiments, except-for-low-power-reactivity-worth-experiments-(Sectx>n4G)>
@ (a) The4eactivity-worthof-any4ndividualexperiment-shalLnot exceed 4340r b (b}----Experiments-having4eactivity-worthsgreater-4han4h00-shall be-securely 4ocateder-fastened 40-prevent 4nadvertent reactivity-changes-during-reactor-operation--Howeverr deliberatesmailmovement-of4uchenexperiment-shall-be permitted-provided4tsfiesxJn4s-such4hatt O 1. 'ixed4nechanicalstopsere4nstalled4o4tmit-potential reactivity-changes 4oless4han-$h00ror 6 2. the-rateof4novement4slimited4>y-mechanical 4neans such4 hat-the-rateef-reactivity <hange ic !ccs-than l
$0AGper-minute- l
$ 1042-Explosivematerials+uchessunpowder dynamite;-TNTr r
or-PETM-may4)e4rradiated4.+4hefeactor4x>reer4eactorpootsub}ect nitroglycerin-i to4he4ollowingu>nditionst h (a)----Explosive 4naterials4ruguantitics of-254nilligramsorless+ h -1. the-pressure-produced-in4heexperimentc>ntainer upon4felonationof4he+xplosiveshallbeless4han the desigrFpressure-of4he-containerr or l l i l l l
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Amendment No. 33 11
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Amendment No. 37
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3 (d) The irradiction time for-antonc device chall-notexceed40A00 hours 6 -{e,s T, s, ,,., ,~'otc', ^ "~"", ,ot-be-plac^,~d ~..' r^osith-peMeHc. o -'."~",
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l I e i 14 4
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l Amendment No. 40 14(a)
-baEs . M 10.2.8 Forced water '!cw experimente may be carriedeut in the reactor follewmg c favorab!c cvc!uction-which cha!! include, in addd+on4o those4temerspec6fied4n-Sect +on40.4-27 4heu>nsiderationof4) locked water 44ow-and-approval-in-accordance-with-Se@>n4041 b 1049-Anyeddit+ons rmodificattons ror4naintenance4othe-ventilation-systemt the ccre and itc acccc!cted cuppc-t ctructure, the poc! cr itn penetratienc, the poc! coc!cnt cyctcm, the red drive mechanicmc or I the reactor cafety cyctcm cha!! be made and tected in accordance I with the cpecificatienc to which the cyctemc were cri;;inally dec!gned and fabricated or to specificatienc approved by the Gnicalityend Radiation Sctety Committec. A cyctem sha!! not be ^hed Operabic unt!! c'tcr it !c cucccccfe!!y tec cd. b 10.2.10 Exp!ccive motoria!c may be radiographed ucing neutron-beams 4 rom the reacter cubject to the fc!!cw!ng conditions +
- c. For exp!ccive deviccc containing only Clacc B and-G l explosives +
6 1. The-radiography +fexplosives-present4n4he4>eam(s) ateny-one4imeshalibe4imited4oequentity-oft
% (e) 'ive-pounds-of+xplosive-(equivalent-TNT}4f4he individuabdevices-containnomore4han4h2o i pounde (114 grams)For I 1
O (b) up4o4wo-pounds +f-explosive-{ equivalent-TNT) provided4hatenly-asingle-device 4s rad +ographedetene4ime: (3 - 2. Explosive-devicerrrnay-oePostt+oned4or44 Ret eslear the-endef4he-beam-port: b 3. Samples-whose-discharge-couldproduce+4hrust-ine ! definite-direction-shalf4>eeriented-soes4o4>eeimed away-from4he-reactor-and4ts-components: h A
/\tenyone4!me4hereehalbt>e4)o-more4han45 pounds ofexplosive-in4he reactor-roomin<lesignated-storage areas-This-25poundc cha!! be-composedeflots-none of-which-shaltexceed4£sofexplosive-During temporary 4nterruptionsof44Reperationrthe-storage shalknotexceed44)ours:
b 5. Up4o400poundsefexplosivemay-bestored up40 eight-hoursoutside4he-reactor-building 4n-a4emporary holdingsrea4or-the-purpose-ofpreparation4or44R: Amendment No. 30 15 i I
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l Amenament No. 30 15(c)
1 h& SD TABLE 4 b MINIMUM-REACTOR 4AFETV-SYSTEM 4 GRAMS Originating Modem-Which Ghannel SetPoint Effective SS Pulse 4-Power-Level 1.65 MWt or lower X
-(24ndependentshannels) j
- 2. Fuel Element-Temperature As+pecifKxMneec4 ion 4-24 X
--(24ndependentehannels) er lower 3-Gonsc!c Scrcm Manual X X 4-Gencole Power Supply-Failure X X 6-Mcgnet Current-Key 4 witch Manual X X @ TABL444 MINIMUM 4MTERLOCKS a Action-Prevented ModeanNVhich D Effective SS Pulse 1 4-Withdrawafef-more4han-one-standard-fed X l
2-Withdtcwc! cf cny standard-red X 1 3-Applicction of air to4ransient-rod 43n!ccc thosewith -X rnevab!c cylindersond-thestandard-reds-are4ully-inserted , l I l l Amendment No. i f 16 1
}
TRIGA Reactors Facility TECHNICAL SPEC FICATIONS TRIGA NARK : REACTOR Facility License No. R 67 ; June 1999 l l l
e
- e TABLE OF CONTENTS Page No.
1.0 Definitions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 Site . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 2 3.0 Rea ctor B uilding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 Rea cto r P ool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3. 5.0 Stored Fuel Description ... ...... . .. . . . .... .. ...... ...... . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.0 Control and Safety Systems... ....... . .... .... . ..... . . . . . . . . . . . . . . . . . . . . . . . . . 5 6.1 Control Systems.. . . .... ...... ........ . .. . . . . . . . . . . . . . . . . . . . . . . . . . 5 6.2 S afety S y ste m s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7.0 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8.0 Administrative Requirements. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 6 8.1 Organization.... ... . .... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8.2 Criticality and Radiation Safety Committee.. . . .... ....... . . .. . . . . . . . . . . . 7 8.3 Written Procedures.. . . . . . . . .. .. . .. .. . . . . . . . . . . . . . . . . ... . . . . . .. . .. . . . . . . . 8 i 8.4 Action to be Taken in the Event of an Abnormal Occurrence. . .... .. ... ..... 8 8.5 Fa cility Re co rds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 8.6 Reporting Requirements... ....... ...... . ... . . . .. ........ . .. . . ... .... . . .. 9 9.0 Facility Operations... ... ... ... . . . ..... ... ... .. . ... ... .. . . . . .. . .. ... . . . . . . . . . . . . 11 l AMENDMENT NO.45
Appendix A License No. R-67 ! TECHNICAL SPECIFICATIONS ! for THE TORREY PINES TRIGA MARK F REACTOR Date: September 27,1968 1.0 DEFINmONS l 1.1 Facility Facility means the building housing the disassembled reactor plus systems, components, etc. associated with possession and decommissioning of the reactor, including fuel storage. I 1.2 Facility Secured Facility secured shall mean that condition where no decornmissioning activities or handling of fuel are in progress at the facility. 1.3 Facility Operation Facility operation shall mean any condition wherein the facility is not secured. 1.4 Decommissioning Activities ; Decommissioning activities shall mean those activities required to remove the facility 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 willinvolve 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 in the 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. AMENDMENT NO.45 1 /
1.8 Abnormal Occurrence An abnormal occurrence is: (a) Any unanticipated or uncontrolled change in subcritical multiplication during fuel storage or handling, (b) An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy caused or could have caused the existence or the development of a condition which resulted or could have resulted in a facility condition outside the requirements of the Technical Specifications; and (c) Release of fission products from a fuel element or fuel follower control rod during fuel storage or handling. 1.9 Measured Value The measured value is the magnitude of that sariable as it appears on the output of a meacuring channel. 1.10 Measurina Channel
)
A measuring channel ' the combination of sensor, interconnecting cables or lines, amplifiers, ani output device which is connected for the purpose of ' measuring the value of a variable. 1.11 Channel Calibration A channel calibration consists of comparing a measured value from the measuring 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 appropriate center of tne TRIGA Reactor Facility building shall define the exclusion area. 3.0 REACTOR BUILDING Until such time as all fuel is removed from the facility and all decom.,issioning activities have been completed, the following ventilation requiremen.4 shall apply. ) I 3.1 The reactor shall be housed in a closed room built to restrict leakage. The ! minimum free volume in the reactor room shall be 11,700 cubic feet. 3.2 Controls for the ventilating system shall be located in the facility. 3.3 - All air or other gas exhausted from the reactor room shall be released to the environment at a minimum of 20 feet above ground level. I AMENDMENTNO.45 2 l
3.4 The reactor room ventilation system shall be separate from the rest of the building ventilation. 3.5 During decommissioning activities and while fuel remains in the facility, air ventilation systems shall be operating to ensure the reactor room 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 REACTOR POOL 4.1 The stored reactor fuel shall be cooled by natural convective water flow. 4.2 Until such time as all fuel has been removed from the pool and the pool is l drained as a part of decommissioning, the minimum level of the pool water i shall be 12 inches below the reference mark near the top of the pool. The l reference mark is located on the west wall of the north-south canal at a level 181/2 inches below floor grade level. 4.3 Until such time as all fuel has been removed from the pool and the pool 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 centimeter averaged over any one calendar month. 4.4 Until such time as all fuel has been removed from the pool, on a quarterly basis the pool water shall be sampled and analyzed for the presence of fission prcducts at a level indicating potential fuel leakage. 5.0 STORED FUELDESCRIPTION 5.1 No reactor fuel elements or control elements with fuel followers shall be stored in the reactor portion (round area) of the pool. Reactor fuel elements and control elements with fuel followers shall only be stored in the Fuel Storage Area of the Mark F reactor pool. 5.2 Standard fuel elements have the characteristics listed below: 5.2.1 Standard low-enrichment tuel (a) Maximum uranium content 9.0 wt% in unitradiated fuel (b) Maximum uranium enrichment <20% in unirradiated fuel (c) Hydrogen to zirconium ratio 0.9 to 1.54 H atoms to 1.0 Zr atom (in the ZrHn) (Iow hydrida) 1.55 to 1.8 H atoms to 1.0 Zr atom (high hydride) (d) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, Hastelloy X, or 0.030 inch aluminum or Zircaloy AMENDMENT NO.45 3
5.2.2 Standard Fuel Lifetime improvement Program (FLIP) fuel (a) Maximum uranium content 9.0 wt% in unirradiated fuel (b) Nominal uranium enrichment 70% in unirradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHn) (d) Natural erbium content 1.0 to 1.8 wt.% (homogeneous distribution) (e) Cladding material and 0.020 inch 304 or 304L stainless steel, ! minimum thickness incoloy 800, or Hastelloy-X l l 5.2.3 Standard low-enrichment fuel with high wt% uranium (a) Maximum uranium content 30 wt% in unirradiated fuel (b) Maximum uranium enrichment < 20% 1 in unirradiated fuel (c) Hydrogen-to-zirconium ratio 1.5 to 1.65 H atoms to 1.0 Zr atoms (in the ZrHn) ; (d) Natural erbium content CA to 1.8 wt%' (homogeneous distribution) (e) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800, or Hastelloy-X
' Scaled according to maximum U-235 content such that a core ccntaining only these elements would require a criticalloading of 2 50 fuel elements.
5.3 Special fuel elements are uranium zirconium hydride fuel elements, which are not standard fuel elements, have the characteristics listed below. 5.3.1 Special fuel elements with high-enrichment uranium. (u) Maximum uranium content 12.0 wt% in unitradiated fuel (b) Maximum uranium enrichment 95% in unirradiated fuel (c) Cicdding material and 0.020 inch 304 or 304L stainless steel, minimum thickness Incoloy 800, or Hastelloy-X or 0.030 inch Zircaloy (d) Construction shall be such that calculated c:ad temperature shall not exceed 500 C at the planned operating level I AMENDMENT NO.45 4
1 5.3.2 Special fuel elements with high wt% uranium (a) Maximum uranium content >30.0 to 45.0 wt% in unirradiated fuel (b) Maximum uranium enrichment <20% in unirradiated fuel (c) Cladding material and 0.020 inch 304 or 304L stainless steel, minimum thickness incoloy 800 or Hastelloy-X or 0.030 inch Zircaloy for 1.5 inch nominal diameter, or 0.015 inch to 0.020 inch stainless steel, incoloy 800 or Hastelloy-X for 0.5 inch nominal diameter (d) Construction is such that the calculated clad temperature does not exceed 500 C at planned operating level. (e) Special fuel elements with 0.5 inch nominal diameter are enclosed in a 0.020 inch metal shroud. The shroud, constructed from one of the Ecove listed cladding materials, has a nominal diameter of 1.5 inches. 5.3 4 Any burnable poison used is an integral part of the as-manufactured fuel element. A bumable poison is defined as a material used f?r the specific purpose of compensating for fuel burn-up and/or other long-term reactivity adjustments. 6.0 CONTROL AND SAFETY SYSTEMS
)
6.1 Control Systems 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, l clad with the materials authorized for fuel element cladding. The contriai i rods may contain flux traps and may be equipped with fuel or 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: 1 (a) An area radiaticn monitoring system capable of activating the i evacuation alarm. (b) When the facility is not secured, a continuous monitoring system for airbome activity having a readout and audible alarm which can be heard in the facility. AMENDMENT NO.45 5
l These systems shall be calibrated annually and their set points verified l 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 alternative or portable radiation monitors. Following maintenance or modification of the radiation monitoring systems, the affected system shall be verified to be operable before returning it to routine operation. i 7.0 FUEL STORAGE 7.1 All fuel elements or control elements with fuel followers shall be stored in a , safe geometry (ka less than 0.8 under all conditions of moderation). I i 7.2 Irradiated fuel elements and control elements with fuel followers shall be
~
stored in an array which will permit sufficient natural convection cooling by water or air such that the temperature of the fuel element will not exceed design values. l l 8.0 ADMINISTRATIVE REQUIREMENTS 8.1 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 alternate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive materiai. The reactor shall be related to the Corporate l structure as shown in the following chart:
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_____________b__________ CC l l l I I I I I I __________.______________ C .*"", ___j______I _ _ _ _ e- w 17 AMENDMENT NO.45
l l 8.2 Criticality and Radiation Safety Committee i 1
- 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 l be composed of at least four members selected by the Cognizant : Vice President, or a designee, considering their experience and l education with regard to the various aspects of nuclear physics, j chemistry, radiological health and statistics, as well as appropriate l experience in other disciplines such as metallurgy and engineering. l Subcommittees shall be appointed by the Chairman of the CRSC. The j subcommittee assigned the responsibility for reviewing facility i operations shall not have thereon person (s) who are directly involved with the facility.
- b. The Criticality and Radiation Safety Committee shall be in accordance with a written charter including provisions for:
- 1. Holding meetings or audits at least annually; special meetings I 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 members attend.
- 3. Preparing minutes or audit findings of the CRSC meetings by the Chairman or his designee. Evident of approval of the participating members of the CRSC shall be obtained before distribution.
- c. The Criticality and Radiation Safety Committee, or subcommittee, shall i review and approve safety standards associated with possession of j 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:
- 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; I
- 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 Part 20 and '
10 CFR Part 50. AMENDMENT NO.45 7 u
8.3 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 I 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. Fuel element or control element with fuel follower handling.
- d. Maintenance of systems necessary for assuring the integrity of the fuel and for maintaining the reactor in accordance with the license.
- e. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal changes.
- f. 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 original intent and do not constitute an unreviewed safety question (as defined in 10 CFR 50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed and approved by the CRSC. 8.4 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 attemate shall be notified and corrective action taken with respect to the operation involved.
- b. The Physicist-in-Charge or other person notified under Section 8 shall notify the Chairman of the CRSC and the Vice President, or his designated attemate, identified in Section 8.1.
- c. A report shall be made to the CRSC which shall include 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 8.6 of these Specifications.
AMENDMENT NO.45 8
8.5 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 statue;
- 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; l
- f. Off-site environmental monitoring surveys; !
- g. Fuelinventories and transfers;
- h. Facility radiation and contamination surveys;
- i. 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.
)
i 8.6 Reporting Requirements ' in addition to the requirements of applicable regulations, and in no way substituting therefore, 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, personal injury, or exposure; r
- 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, Washington, DC 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 possible, the preliminary telephone or AMENDMENT NO.45 9
I
I ]1 a , i- facsimile report) shall describe, analyze and evaluate safety i implications, and outline the corrective measures taken or ] ! planned to prevent reoccurrence of the event. l l l
- 2. Any abnormal occurrence as defined in Section 1.8 of these Specifications.
I ! l c. A report within 30 days in writing to the Document Control Desk, USNRC, Washington, DC 20555: q l
- 1. Any significant variation of measured values from a l l.
corresponding predicted or previously measured value of I safety-connected operating characteristics occurring for the ! reactor or fuel; !
- 2. Any significant changes in the transient or accident analyses l
as described in all Safety Analysis Reports; and
- 3. 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 status of the facility and fuel, (3) any changes to the decommissioning i schedule, and (4) a summary of radioactive material l shipments. l
- 2. Discussion of the major maintenance operations performed )
during the period, including the effects, if any, on the safe
~
l possession of the reactor, and the reasons for any corrective maintenance required. l
- 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 performed within the facility.
AMENDMENT NO.45 10
9.0 FACILITY OPERATIONS 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 8.3). b) Decommissioning in accordance with the facility license and consistent with an approved Decommissioning Plan. c) Fuel storage, handling, packaging and removal in accordance with approved procedures. I i l l l 1 AMENDMENT NO.45 11
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