ML19308D823
| ML19308D823 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/04/1971 |
| From: | Grill R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003180769 | |
| Download: ML19308D823 (5) | |
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QkIESTIONS dN. CRYSTAL RIVER LETIT 3 GENERAIING FLANT FINAL' SAFEIY ANALYSIS r
REPORT - DOCKET NO. 302 i
Attached arc our questions on the Crystal 2ivo-nuclear generating plant 13 for the final safety.2nalycia rcrart. ' hese :uantiam are sumarJ 2M its follona 1._.
'Itc applicant han been raquented to ri. tuate the er ernal man unde Iweards t6 the plant sucit an or.losione or IT vet fr -' aarina teciden ts.
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They have beca recuanted to previde-better n ei:carolc~ical dat1.
L, preeent data recovery. for 25 montha is approxt:natcir 50%.
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Uc h..vc requu al thi nrelicant.to,-; -> :- detnilad infomti.on e the radi~-mive vaste trea trent rysten:..
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A detailed b:rir. tion of the offluet mitar has ben re u :Mmi.
R...P. Grill, Chiei c-Stte safety Branch i
Division of Reactor Licencing l
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SITE AND TdE Eh"!InciWNT It is indicated on page 2-2 that the Gulf of F2xico is used for barge traffic-to deliver coal to Units 1 and 2 adjacent to the nuclear site.
Assuc2 an oil barge releases oil to the Gulf of Mexico in the vicinity of the site. Provida a descriptica of the effects of the relenced oil on the operation of the main condenser circulating water systen. the engineered safety feature cooling unter systen, and other systems that might be affected.
Assu=e a munition barge or ship explodes in the closest normally used channel in the vicinity of the cito. Provide a description of the effect of the explosion on the operation of plant systems that night be affected.
Assucc a barge or ship becomes uncontrolled during a storn in the vicinity of the site.
Provide a description of the effect of the impact of the uncontrolled barge en the plant intche structure, the energency ecoling votar intake structure and any dikes and intake canals that night be affceted.
Assune a barge releasco chlorine gas in the-vicinity ef cha site. Provida a description of the affect of the released g s on the performance of the reactor control roon ventilation syst2= and o ther systens that might be affected.
Include a discussion of the protection that is provided for the reactor operators if chlorine can got inte :he control rec = and cther regions of the plant that cight be affected.
Pa;c 30 of the envircnnental report indicates that chierina is used to prevent marine organisns fron
' fouling condenser tubes.
Provida a description of the location, cuantity, chemical composition, and physical state of the chlorine stored on the site and the effcets of potantial chlorine gas relenscs fro = these sources on the safety of reactor operation.
Provide a description of existing airports and missile bases within 10 miles of the plant and of propesad airports '.ithin 5 miles of the plant.
For existing airports, provide a description of the aircraft using them including the weight of the aircraf t, the number of takeoffs and landings, and the flight paths.
Page 2-2 indicates a railroad track spur comes into the plant site.
Assume a railroad accident releases hazardous chemicals in the vicinity of the site.
Provide a description of the affects of the released chemicals on the operation of plant systems that night be affected.
Appendix 2a, the wind diffusion progran cenputer printout for Crystal River Unit Number 3 tabulates approxi=ately 60% of the data that could be obtained if the meteorological instru=ents and the NUS vind variance
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co=put:r had functioned continucualy.
"a enpect at least 90% dern recovery. -Provide t. tabulation of time perioda when no data were recorded and.ctate the rencons for not recording these data.
Provide a tabulation of the estoorologicci parameters calculated by the vind vane computer code using =cteorclegical dcta for a 12 =enth period (the tcble cttached in cppendin 2a uses cateorological dcca for a 25 n: nth period) and provida a tabulation of the joint frequancy distribut;'en of vind speed and directica from the 30-foot level by wind directional variance (sissa theta) claases from the ISO-foot level for data obtained during the -365 consecutive day period that has the best data recevery. If the range of wind direction obtained from strip chart record 2rc and conputer data ic used to inprove data recovery, cc pare the results ebenined by each cathed for a tice period when both the computer and the strip chart recordere vere operating.
If a reanalysis of the noterological data indicates any significant change in the accident or annuni average v/Q valuun used in those analyses, these revised 4/Q values should be supplied in an nnendment to the PSAR.
State your plcns as to whether you uill inctnll a vertieni te:oeratura difference systcc to estimate atmospheric ctability for accidental and/or annual averaaa relecccc of scaecus effluents.
Page 18 of the Cryctal River Unit 3 Envirorncatal Report indicates thnt a second set of meteorological instrumentntice uns installed on the 150-foot meteorologicci ccuar in July 1970. The TSAR docc nu ; include infor-natier en this instru:1nt.
Plecse include the data from thin elevation in your analycic of both routine r:lcase and accidental relcasa ec:ccrclogy used for tha Crystal niver facility.
The population statist 1cs appear, from page 2-1, to be based on the 1960 census.
Please provide revised population values based en the 1970 census, and ~1nclude a revised draving sinilar to figure 2-6 uhich shous the popula-tion distribution within a 5 and a 50 mile radius fron the reactor site.
WASTE DISPOSAL AND PADIATION PROTECTION SYSTEM s
Provide a discussion of how the radwaste system vill be designed and operated so as to cocply with the amendnents of 10 CFR Parts 20 and 50 of the AEC's regulations that require releases of radioactivity to be reduced to their lovost practicable levels.
Provide a tabulation of the total anticipated maximum yearly discharge of each isotope (including tritium) enpected to be released from all sources (provide separate tabulation fer the releaces that vill result f ron containment purging) to the environ =ent for both liquid and gascous effluents and compare thc= with the limits of 10 CFR Part 20.
Assume water leakage -
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' frco the reactor coolant systcc and f tc9 fen product leakage from the fuel rods con:ictent with your preponed technical specificctions and with data fren opnrating plants, et:ch as Ginna.
In addition, provide the fc11 cuing:
Deveriba tha bcmia fer these estientes. 2n:Ind_m the catn::tiono 2ada uith r n;ard to decontaxin clar f acto r, u cd f er holdep, filtretion, evarnratica nnd decincr411:ata n.
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t.cm. or garacional una from cinilar radweste treat = cat conpenants in coeracia;; plants.
Include a deceription using numerical values to show the anticipated use of the contcin=nnt vent and purge system to relieve pressure buildup in the containnant, and to permit accecs to the containnent by plant personnel for routinc inspection and maintanence.
Provide cdditioncl information in the forn of process data on process load diagrana for bota liquid and gaseous unstes.
On the liquid unsta process load diagrca, uhou the microcurie content and flow rate in cach flow path.
On the 32:couc wert2 process lend diagran, chou the flow rates, tecperaturas, pressures, speci fic isotore radioac;i/ity for the 90 day nininun heldup time in die decav tanks, ac appecpriate :ters of the process.
Provide a description of your procedures to deternine and record the activity of crecific icatores that vill 'ca la the lic.uid ucate diccharned to thu Colf of 'i2niao.
Inci s in the dcacrir~', =c frequencv cf pariadic deter.inaticna cf iretoric com rition and c6m in condition t:.it tauld requira there det:rninsticr
'unm chav ec in = > rn 5nste prococs or unenrected changec in grece nettvity naccurenantc). " c"ide the fellowing infermation rencrding tritium:
A cerparican of the anticipatel nanicum trittua concentration in Cr: discharpc canal and in the Gulf of "anico, uith current tritium conc. cat.ratienc in the Calf of "=1co na datar-min d by your preoperational conitoring progrns.
Provide cico, your analysis of the fraction of tritiun in the primary c ;1 cat that uill be relesaca to the circulating uater discharge canal.
A dincussion of the uncertainties in your estL:ste of the arount of tritium that vill be generated.
A dascription of the methods to be used to conitor tritium concentrctions prior to discharge from the plant.
Provide the following information with respect to the instru-nantation, sacpling techniques, and 1chorntory analytical procedures to be uced for evaluation of gaceous and liquid efflu2nts and other in-plant and environmental radiation and radioactivity levels: A description of the instrucent types, sensitivitics, ranges, set points and calibration methodo and frequencies. A discussion to demonstrate the capabilities of the instrumentation and procedures to detect, measure, and control effluent releases, by appropriate radionuclide, within design objectives and expected for routine operation and for expected operational occurrences. An identi-fication of each path by which liquid and geaccus effluents can be released from the plant, and of the instrunnntation to be used for monitoring each path. An evaluation of the possible annual releases of radioactive materials if effluents having radioactivity levels equivalent to the monitor setpoint are continuously released.
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_y Page 11-16 bricfly deceribes the reactor building purge exhaust duct monitor RN-A-1.
Provide a deceription of the enpability of thic instru-ment to deccet erecific isotopes, including the capability to detect gcccouc iodine 111 in the presence of noble gases.
Provide e descrip-tien of the mathod of ins trun2n: cc115rstien fer ic:csurina the queatity of radiocc ive ncbla 3:ccs, icdiaca and particulate unctar.
If a filter tape is used in this system, state the filter officiency of the paper for radioactive iodine.
Page 11-18 describes the monitor in dio plant discharge line.
Provide an analysis of the menimum concentrhtions of radioactivity thct could exist in the diccharge canc1' du2 to activity, the secom generator bicudoun system bcsed on a radioactivity Icv 21 equal to the satroint of the liquid radiathn uenitor end in tha credensar vievaa pt=p enh:ust due to the continuou relense of :. teem and gescs fron ene ficah tanh havin3 a radioac:ivity icvel equal to tha actpaint of enhcus: =cnitor RM-A-12.
Assume fer the caslysis that the maximum ecolant activity and maninum cecicut 1cakage to the craca genarnter are es specified in the Technicc1 Spccifica: ions.
It is noted on page 14-21 that the fuel hcndling :.ccidant analysin is haced on the failure of 56 out of th 203 tuel r:ds in a fuel cacerbly.
It is further netad thac a uatar dacant:rinction fccter of 1000 ic tchen for iodina.
Uur currcat craff model cacarua a unt2r decon:aninction fact:r of 100 for olta:ntal icdinc. Your refueling cc ident desc should be reunalyzed bcacd on theac ravised nacunptions.
' Indicate tho radiation source term used in the design of the control compicx ccergency ch:rcoal filter chcun in figuro 9-12.
Provida data on the charcoal filter system an to ' type and uelght of charcoal used, flow rate, face velocity of the filters and the onpec:cd officiency for both elemental and orgcnic forms of iodinc.
Indicate the calculated thyroid dose to the reactor operatorn in the control room following the dcJign bcsis cccidents.
Table 14-52 includes the results of engineered safeguards system leakane doses resulting from the M!!A.
Provide the details of your analysis includ-ing the fission product source term contained in the Icakage, the partition factor assumed as the liquid flashes to steam (figure 14-61 shows the temperature of the surp water is above 212*F for the first' two hours following the LOCA), and the flow path to the point of release to the environ =cn t.
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