ML22124A252
| ML22124A252 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 10/17/1966 |
| From: | US Atomic Energy Commission (AEC) |
| To: | Nuclear Fuel Services |
| Doell M | |
| Shared Package | |
| ML22124A246 | List: |
| References | |
| Download: ML22124A252 (328) | |
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\ UNITED STATES A"rOMIC ENERGY COMMISSION WASHINGTON. D.c. IONS OCT .2 8 1966 Ul r.";'# .. '" 1"'. ~iR TC*
Doclt~t i;o. 50-201 Chenge No.1 L1eense Ro. CSF-l Nuclear Fuel Services,. Inc. Box 124 West Valley, Rev York 14171 Attention: Mr. W. H. Levis Viee President aDd General Manager Nev York State Atomic and Space
!le*... elo;:lIent Authorl ty 230 Perk h"enue Rev Yo:,lt, Nev York 10017 Attention: Mr. Oliver Tevcsend Chaiman Gentl~i'len:
This refers to your req'lest dated October 12, 1966, ~or !luthor! ";y to recel ve, possess end use up to f1 ve millicuries o~ stror.t1um-90 fer the prep'!rat1on and ul.le of calibration sources for dose Tate iLS tru-ments. Your reouest has been designated as Proposed Chenge llo, 1 end has been considered' pursWint to the provision. of Section 50.59 ot 10 CFR 50. We have reviewed the proposed change ana have tounc! that the pro~sed change ~oe8 not present a s1gni~cant haze~ co~s1dera~ion not dcscr1b~ or 1mpli~1 t '1n the :1FS "Find Safety Analysi. Report." end that the:'e 1& reasone';)le 8!surence that the health and .afety ot the public YiU not be endltnc:e~ by tbe chenge. Preparation ot the sources Yill be under edmS nistret1"e controls according to procedures fI~proved by tbe Plant S!lfety Cot-.aittee. Film badSeI, dosillleter. and other protective equipment rill be ut1lized a. nec****17.
Aet'ordingly, pursuant to Section 50.59 of 1(') ern Fart 50, tl~e rollo~nrt luthority is added to section 2.3 of the Tecbnieol Specifications of License no. CSF-l "Materiel, Stront1um-90 Fom Solution/Bealed sources , x 10-3 curies Sincerely yours, J. A. McBride, Director Division of Met~r1els Llcensipg cc: C. R. Ereun E. G. Eecllhoefer
CO~y UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 Oct 28. 1966 Docket No. 50-201 Change No. 1 License No. CSF-l Nuclear Fuel Services. Inc. Box 124 West Valley. New York 14171 Attention: Mr. W. H. Lewis Vice President and General Manager AND New York State Atomic and Space Development Authority 230 Park Avenue New York. New York 10017 Attention: Mr. Oliver Townsend Chainnan Gentlemen: This refers to your request dated October 12. 1966. for authority to receive. possess and use up to five mi11icuries of strontium-gO for the preparation and use of calibration sources for dose rate instru-ments. Your request has been designated as Proposed Change No. 1 and has been considered pursuant to the provisions of Section 50.59 of 10 CFR 50. We have reviewed the proposed change and have found that the proposed change does not present a significant hazard consideration not described or implicit in the NFS "Final Safety Analysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered by the change. Preparation of the sources will be under administrative controls according to procedures approved by the Plant Safety Committee. Film badges. dosimeters and other protective equipment will be utilized as necessar,y. COP.Y
COP..Y Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the following authority is added to Section 2.3 of the Technical Specifications of License No. CSF-l -Material FOrni Possessi on Limi til Strontium-90 Solution/sealed sources 5 x 10- 3 curies Sincerely yours. (signed) J. A. McBride) J. A. McBride, Director Division of Materials Licensing cc: C. R. Braun B. G. Bechhoefer COE..Y
CHANGE ~O. 2 Page withheld as containing Export Controlled Information 9
Page withheld as containing Export Controlled Information 10
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CHANGE NO. 3 Page withheld as containing Export Controlled Information 19
Page withheld as containing Export Controlled Information 20
Page withheld as containing Export Controlled Information 21
We havc taken into consideration the authorization in Technical Specifi-cation 4.8.1.5 to pacJ_ .. ge in spccificC: containers the solutions that r.1ay be stored in accordance 'dth Technic::.l Specification 4.8.1.4. Based on data in K-643 and CRXL-2143 \~e have ccnclucled that packaging and storage in accordance with Technical Specification 4.8.1.5 of solutions authorized for poisoned tank stora=e by this revision of Technical Specification 4.8.1.4 will be in keeping with normal safety requirements. On the basis of our revic,., of the nuclear safety aspects of the requested change we conclude that the proposed chan~e does not present a significant hazard consideration not described Ol" i::1plicit in the NFS "Final Safety Analysis Rcport" and that there is reasonable assurance that the health and safety of the public will not be endangered by the change.
CHANGE NO. 4 UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 IN Ri:P1. Y PtEFEr::t TQ: Docket Fo. 50-201 JUN 8 iSst Nucl~ar ru~l Services. Inc. Change No.4 Box 124 Licecse No. CSF-l WEft Vdley, N~w York 14171 Atte~t~~n: tr. R. P. Wischow AsaiaU:lt General Manager AND New Yo~k St~te Atomi~ and Sp6ce Developt:;~nt Author1t:y 230 P.!'k A-.. e~ue New Yo~k, N~w York 10017 Att~nti~n: Mr. Oliver Townsend Chairman Gentlem~n: This reie=s t~ (1) Nuclear Fuel Service,' requeat dated DeeeCbe~ 15, 1966, a~d ~upple~~ted F£~r~s=y 10, 19&7, ?ebr~a=y 15. 1957, a~d ~r~h 20, 1967, for appro'nll of a p=oposd to install a heat e.xchi1r.;g~r. in ""sse!'.. ';'"!.::.k 8D-2, and to u.ee the hue exct~r.ger co boil-off ex:esa lic;uid from ehe w:.ne tsuk, ac~ (2) S~:le4r lael Ssrvi~e31 re~uest& Q~ted'MArch 24, 1957, for c~~ng£5 in the t.ecrci.:a1 speeificaUorui dul1ng with ra.tio~-:"dv1ty in effh.e:.<:s, IIk)n1t:.r1:!!.g of eff1'lenes, tlnd aC::Iin1atrative r£q*.1ire~;r.:s goven1~!g operation of thl: ft:lli~y. Ih~se rf.C;Ue3U have been desi.gti.~1:e:i u Prop')s~Q (t"!.9.nge No .... sr:ul of .t!:~::1 cQr:.ci~t.as:e, the 1D!tal1~ti':>:l aLe u~e of the subject heat ext-hanger 1~ W.s~~ I~~k 80.2 does n:tt pres6~t &1gntfi.:s:lt hazards co~ideration. cot deacrioad ori.mp1iclt in the
Nuclear Fuel Services, Inc. AND New York State Atomic and Space Development Authority NFS "Final Safety Analysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered by its installation and use. Accordingly, the proposed installation and use of the beat ~~chan~er is authorized. A copy of the Waste Tank Heat Excban~er Safety Analysis prepared by tbe Divi.ion of Material. Licensing 1. attached. lD addition, we have reviewed the proposed change in Technical Specifications and bave found that it does not present significant ha%srds considerations Dot described or icpl1cit in the NP'S "Final Safety Analysis Report" and that there is reasonable assurance that the health aDd safety of the public will Dot be endangered by the change. A copy of the Evaluation of Technical Specification ChAnge Nueber Four by the DiVision of ~mterials Licensing is attached. Accordingly, pursuant to Section 50.59 of 10 CFR fart SO, changes in Technical Spec1.ficotions 4.0, 4.1, 4.2, S.O. 5.1:* and 7: 1 of !.:!.:c:;s ::". CSF-l as set forth on attached pages 11, 12. 14. 15, l6a. l6b, 16c. 43. 44. 45. 70, 71. and 72 are authorized. Sincerely yours, Oriain.1 Signed by
.&. I. Mc:£IriISe J. A. MCBride, Director Division of Materials Licensing Attachments:
Change 4 Revision pages 11, 12,
- 14. 15, 16a, l6b, l6c, 43, 44, 4S. 70, 71, and 72.
Evaluation of Technical Specification Change Number Four Waste Tank Heat Exchanger
" Safety Ana ly81.
cc: Hr. T. C. Runion Hr. B. G. Bechhoefer
EVA1.U..l..TION OF 'IE~F~lICA1. SPECIFlCATIOU GE:~!;Gl:': m:.3ER ;:'OUR "V
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DlV!~!m7 OF }~\~RIID UCE~!sING ti"UCu;.*..:1. n..r:L SE~";~:":S, I~:C. DVCK.S! 1"0. 50-LOl Pollowing several discussions with regulatory personnel, Nuclear Puel. Services, Inc., (!TZ'S) submitted two'letters.each dated lUrch 24.1967, wbich pr~posed modifications to the Technical Speeific"tion of 1.icen.e CSF-l. The propo~ed revisions dealt with licit. on the ~uantity of radio- ,activity in effl~~nt3, monitoring of effluents, and administrative re~uire
~ents R~~erniDg the operation of the facility. During our revi~~ of the pro?oaed ~difica~ions we h3d several telephone conversations with NFS which reGult~d in additional modifications that were agreed upon by NrS. None of the propos~d reviS1~ns pre3ented a hazareia consideration not described or lz::;!licit in the UPS "Final Snfety Andysis Report". With the exception of the ~d1fi~3tion to Specificction 4.1.1, described belo~ the reviSions pro-vided for greater in-depth control of the operation. Accordingly, the reVisions rusonably assurec1 that tile hUith and safety of the public ~oulci not be e'!1dara,;ered and they were incorporated into Licen,e CSF-l by our tele-type of ~~rch 30, 1907. the revisions are discussed below:
Spee1fi~~tion 4.0 has been modified to correct the numbering of the technical spe~ii1cat1ons referenced therein. Sn!~ifi~lti~n 4.1.1(c) h3s been added to allow some credit for the dilution c8pab11i~y prOV1G2d oy the meteorology of th~ site as ia cocmonly authorized in the esse of reactor facili~ies. Based on.~he cnnual average dilution data pre ....nted 14 the "FiMl Safety AnalysiS Report", a monthly average reluse rate of 0.1 mi~roeuries per second of particulate activity h3. been authorized. This rate will result in concentrations at ground level off-site below the values specified in 10 erR 20. Appendix B, Table II. Column 1 and will b~ con-sistent with Federal Radiation Council dietsry intake luid4nce. For example,
if all of the particulate rQdioactivity released were the highiy radiotoxic isotope Sr* 90, the concentrations oif~aite would be 1/1000 of the allowable 10 CFR 20 concentration limit (inhalation) in unrestricted areas. In terms of soluble strontium nitrate the quantity released per year via the stack vil1 have to be limited to 0.037 crems in order to meet the requirements of this specific~tlon. S~ecifieation 4.1.2 has been revised to incorporate minimum values of wind velocity vn1ch shall exiot before initiation of a dissolution operation. These agreed upon values vi1l prevent dissolutions except during periods when there is reasonable assurance that gaseous radioactivity releases will DOt result in off-site exposure in excess of 10 CPR 20 atandards *. Speclficp.tion 4.2.1 has been added to provide more i~depth control of liquid effluents. 'ine specificatien includes the oper&.ting technique which must be used with the single interceptor (tvo interceptors are to be installed in the near future), e9~~blishes a limit on the quantity of radioactivity which ~~y be released from the interceptor to the lagoons in any qu~rtEr. and permits byp~s8ing of the interceptor and 18800ns if a liquid effluent is batchwise collected and ~naly8e8 sho.a it to be below the concentracion limits for effluent released to unrestricted areas. Liquid effluents entering the interceptor shall be monitored by an i~line monitor which vi1l indicate a release of radioactivity at a concentration in excess of 5 x 10J ~c/ml to the interceptor. The interceptor sh~ll be sacpled and the sa~le analyzed to determine that it is below the specifi~d licit befere the interceptor is diichar~ed. Any alarm of the in-line monitor during disch~r~e of the interceptor requires that the discharge operation be stopped. Th~se operatior.a1 steps should prevent an inadvertent release of radioactivity to the lagoons. The 4.9 million gallon lagoon system provides holdup equivalent to the volume of plant waste water released during 120 days'of Dormal operation. This holdup capability pcrcits
- period for rad1eactivity decay. sedimentation and ion exchange and allows release to Cattaraugus Creek during periods of high flow thus assuring th~t
- mini~um concentration vill result in unrestricted areas.
The maximum quantity of radioactivity that may be transferred to the storage lagoons in any quarter is ~qua1 to the quantity vhich could be diluted to the limits specified by 10 CrR 20 for unrestricted aress if the annual average flow rate indicated in the "Final Safety Ana 1y81s Report" haa existed durir.g the quarter.
Specific!ti~n 4.2.2 i. the **me .s the former Specificatio~ 4.2.1 Soeeifie~tiop~ h91 been modified to r~1uire ahut-down ofop ..ra~ion! relea5ing ~~Qi~ac~lvity to the environment if monitor1~ requirements cannot be fa1fi11~d. Sped fication 5.1.1 has been added to require analyU:al de!::erm1~t1on; of ra~1~a~~1v1~y in ~11 batches of effluent 1iq~ids prio: co rel~age, either to the lagoon sy$~em or dir~ctly to the e~~iro~~n~. This guards against 4n in!dvertent release of ,ontamina:ed liquids from s~urces n~t expected to be radi~act1ve. So.:.d.ft:'1tbl'!. 5.1. 2 wu f.;)t'mer1y cumbered 5.1.1. In ~ddit1"m t., :he ch.:-.pge 1~cr1Lg, this s~eeliic!tior. hAS been made ~re r~~trict1ve in respect to operso111tyof th~ Cattaraugus Cr~ek concinuous esmpler. N~ more ch~n two ~llion ~~11on3 can be re1essed !Tom the ls~oons in one yesr u:ili=1~2 manual sacp1i~;in lieu or contl~aous s~mpliLg of Cattarau;us C~£ek. A minil:l.lll! £tequerocy of manual 6.a:l:pli:~ hAs :>een spE;.ifled. t~ af.$ur~ ~tAt k the ana lytic .. 1 dAta 18 repr£sE:n~at1ve. Sp~e1i1(;.~~~ tak-es the p1a.!e of former 5.1.2. It hilS bee!'.! revlud to rec;*... 1re ':::lr.::1;'\:OUS. collectio"!1 of :;-131 and plTticulate !Amples of sta.:k eff1u~.:lt ar.:i w!>.!kly anslyses of these I14mplu for both al~r a ar.:d b.;!:a activity ~i the p~rtlcul~tes. Continuous ~ni~ori~g of Kr-85, 1-131 a~d puticubte beta a.:;t1v1ty of the stack effllAU1; is 6.160 rt'\I.1ired. If the contlnu~us Kr-S5 ~~ni~~r fails, pr~ces31n~ mey con;!~~2 bv ~alcu13:ing the quantity of r!luscd Kr-85 fr*jm irrsdtati,n e:.t!l 0)£ t.he fuel he1n~ pl':.c"=ssed, If the 1~131 ~r p2~ticu1ace beta activ1ty ~~it~l~ b~eo~ 1n~per&tiv~ a sample ~oll:cted throughout each enif! will be .na1y~Gd.
ADMINISTRATIVE REOUI~!ENTS The scope of the administrative requirements bas been increased. In Specification 7.1.1 an Assistant General Manager position has been added with cirect respc~3ibility for radiological and nuclear safety. The Director of Health and S3£ety and the Technical Services ~~nager report to the new Assistant General l1aneger. and their responsibilities have been defined in terms of their radiological and nuclear safety ;functions. An additional cbange in Specification 7.1.1 adds to the Plant Safety Committee's respo~si bilities the investigation of abnormal occurrences and tbe recommendatio~ of measures to prevent repetition of such occurrences. Specific~tion 7.1.3 bas been revised to indicate an acceptable degree of knowledge on the part of the production operating staff. Specif5cstiC'Tl 7.1.5 h:ls been revised to require that records be kept of Plant Safety Cor~ittee meetings as well as details of their investigations and reco~endations. Soecific!:tion 7.1.6 is a new specification requiring periodic audita of radiological <In:i nu=lear safety throughout the facility by competeut per-aonnel other than those responsible for the execution of the audited operations. Specification 7.1.7 is the former 7.1.6. JIJN 7 19S7
WASTE TAm< H~AT EXCP.ANGER SAFETY .~iiALYSIS BY THE DIVISION OF nTERIALS LIC!NSmC
!l1.l'CLEA~ FUEL f:::tVICES, I:;C.
DOCKET ::0. 50-201 AUTHORIZATION REOUESTED By a letter dated December 16, 1966 and supplemented by letters dated* February 10, 1967, February 15, 1967. February 20, 1967, and March 20, 1967, Nuclear Fuel Services, Inc. (:~S) submitted design information and operating procedures for a heater to be placed in high level Waste Tank 8D-2 and requested approval of the installation and use of such a heater to boil off excess water accumulated in the tank because the radioactivity content is thus far insufficient to cause self boiling of tbe waste liquid. Subsequently the beater may be transferred to the spare Waste Tank 8D-l, which has been half filled with water, but to which radioactive waste has not yet been directed. Waste Tanks 8D-l and 80-2 are 750,000 gallon tanks of mild steel, located underground in concrete vaults. They are designed to contain neutralized self boiling radioactive wastes from plant operations. The tanks are pro-vided with vent systems that include. condensers, a knock-out drum, reheater, filters. and exhausters. Uncondensed gases are discharged to the plant ventilation system. Condensate may be returned by gravity to the waste tanks or, if Teduction of tank contents is desired, it may be pumped to the plant for processing and discharge to the environment. Prior to the introduction of neutralized radioactive waste to Tank 8D-2, 100,000 gallons of caustic solution was added to the tank to assure neutralization and an additional 300,000 gallons of water was added to assure proper operation of built-in air lift circulators. Because of these water additions and the low heat generation rate of the radioactive waste being transferred to Tank 8D-2, tbe tank will not boil by itself before it becomes filled. Hence, the need to install a heat exchanger to boil off tbe excess water.
The proposEd installation will consist of a steam heated tube bundle vertically &uspendcd in the tank from a concrete filled pl~g mounted in the l2-inch corrosion coupon access hatch of the tack. Corrosion specimens in 8D-l and 8D-2 now attached to the 12-in~h ~~tch covers will be ~ved at t~e title of the heat excn3nger installation to the 6-in:h U::l?11ng hstch covers. Future sampling of the tnnks will be effected through a 2-inch hole in the beat exchanger installstion plug and a hole in a new .12-incb plug to be used after the ~eat e~c~nger is removed. Thus. the proposed installation will not interfere with noreal corrosion monitoring and sacpling programs of the waste tanks. A 2-inch steam line and a l-inch condensate line. cast in the hatch plug. will feed and droin the he~t ex=hanger. Steam will he 8up~lied via a temporary 2-1nch line ~unced a~cv6 ground. Steam flow w1ll be regulated by using a globe valve snd pressure gauge. A bleed valve on the steam line will p~roit venti~~ the exctsnger system up~n t~=~~tion of s:e%m flow to relieve the vnc~~m ,aused by conder.3i~ st£~. Co~j£~ss~~ from the heat exchanger will pass t~ou~h a stea~ trsp for batchwise collection in a portable 3500 gallon tank. w~ere it will be sau:plcd ar.d cOn'ol'eyed to _______ .l ........ ..a .. _____ , -,rr."'r."s.a .. ,,* -.. . . ~t'~.... t,ap at the ste!lm tnp snd wit!l pipir..g
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con:i~nsate directly to Tank 8D-2 ra:her than to the portable collection tsnk. SAFETY C'.o~7S!I'EPA,!,~I)NS
- 1. Control of A.ctivity ~rir.2 Instdht1:m ani Rel!'..,val of t;h~ Ex:b!l!!.2I;r The NFS procedures for insta11ing tha h!a!lt exchanger cdl for removing the present corrosion cot:pon accesa hatch cover with a =:ans ani thoan encap!~l~ting the cover f~r rtorsge. lbe new plag and hast exch3~ser will be inser~ed into t~e hatch i~ediately. If any ~e19y is encoun-tered. th~ hatch will be recovered with the or1gin~1 pl~g or. if the delay is only a few minutes. a tempo=ary plastic covsr will ba ussd.
Once the heat exch3nger is in place the tank will be in a sealed co~ dition. When trsnsferring the best exchanger to lank 8D-l. the beat exchsnger will be slowly withdrawn from T.nk 8D-2 1n:o s plastic bag
** it is being .prayed down and rinsed ~~tb the rinse going back into rank 8D-2. The hatch will be capped at once with the pl~g from the corrosion coup~n ac::=ess hstch on 8D-l and the hest ex:~sng5r and plug will be transported by crane to th& 8D-1 corros~n coup~n access hatch where it will be inserted into lank SD-l. In addition to these pr~cEcures, NFS notes that the off-gss .ystem exhauster will pr~vide a draft to insure
~hat the flow of air will be into t~e hatch and not out. NTS further notes that they have experienced no venting of tank vapors to the atcosphere when sampling the tanks through the 6-in=h hatch.
- 2. Venting Callacity ~n':i Entr,'lir.~ent Approximately 3000 pounds per hou& of condensate will be disch~rged from the heat exchan3er (2.7 x 10 BTO/hr) when the tank is boiling.
About ten percent oi tne he4t will be lost to the ground around the tank. thus th~ m3Xicum net boil-oif rate from the tank will be 2700 pounds per hour. Ihis quantity is within the design rating of the condensers in the tank vent system. HFS estimates thst the vapor velocity at the vapor exit line from the tank will b~ only 21s the design value. Also. the fission product concentration is only ab~ut 1/10 of the concer.tr4tion that will be present when tte t~~~ i3 ulticately filled to the design level with high Activity waste. Under these conditions NFS sees no problem with entrainment of activity into the v~~t syste~ Since th3se tanks wgre designed for higher boiling rates. we believe that the proposed operation will present no venting or entrai~~nt hazards not previously analyzed.
- 3. Leay~ge of Radioactivitv In:o p.~!ter Sys~em During routine operation. the heat ex:hanger will be at a minicum pressure of 15 psi and no activity w~uld be expected to leak ir.t~ the heat exchanger should it dave lop a leak d~ring use. The condensate from the heat exchanger will be colle:ted in a portable 3500 gallon tank. sacpled. and than. if the activity con:entra:ion is within specified limit, it may be released to tha environm~nt. If the conden-sate becomes contaminated aaove the release limit. it will be transferred to either Tank 8D-2 or the G~neral ~~~p~se Evaporator, 7C-S.
To assure that this ~e~hod of condensate ~is~sal is adaquate. Te~hnical Specifi:ation 4.2.1 incorporates re~uir~~ots for b3tch c~llec~ion and sampling of condensates and specifies t~at .~~ conde~aa:e may no~ be released directly to the envir~cment 1f
- co~entration of 0.3 picocuries per milliliter is exce~ded.
( Whenever ste~m flow to the heat exchanger is terminated. the steam trap will be hypassed to relieve the steam pressure. then the bleed valve will be opened to relieve the vacuum caused by condensation of steam in the system. When the system is restarted. the valving will be adjusted to close the vents to atmosphere. A steam pressure of 20 psig will be built u~ with the heater condensate routed to the high level ~~~te tank. After a sa~le of the flowing condensate has yielded a satisfactory activity analysis. the heater condensate will be routed to the portable collection tank. These precautions. along with the sampling of the condensate coll£cted
'in the portable tank provide ample surveillance to warn of leaks which might develop.
- 4. Pioing Failure NFS presented final design details which included a description of features to reduce piping stresses. The staff reviel~ed the design and concurs th~t the design provides adequate strength to make mechanicnl stress failures unlikely.
If ii "G=Pl~tc b:e:!~ chculd c==ur in the 2- int'h ~t~Am 1ine: NrS .. esti~~tes that approxi~tely 4000 lbs/hr of steam or about 4.9x10 b BTU/hr, could be released into the waste tank. We have independently verified that the flow would be so constrained by the chara~teristics of the Piping] Since the tank vent system condenser is deSigned to handle 1 x 10 BTU/hr, the maxi~m steam leak rate would be accommodated, and hence this does not present a hazard not previously analyzed. CONCLUSION Based on our review of the proposed installation, we con:,lude that it does not present significant hazards consieerations not described or impliCit in NFS "Final Safety Analysis Report" ~nd that there is reasotl.3ble assurance that the health and sarety of the public will not be endangered by the installation and use of the proposed heat exchanger in the high level waste tanks. We recommend that the heater steam condensate discharged to the environment be limited to a radioactivity concentration that does not exceed the unrestricted area concentrations specified in 10 CFR 20.
Page withheld as unreviewed potentially containing Export Controlled Information 34
Page withheld as unreviewed potentially containing Export Controlled Information 35
This is about oue-fifth of the nor~.l aeolian dilution of Sxl06 cubic meters per second expected in this area. Milk produced at the oD-site farm and in neighboring pastures is to be tested routinely for Iodine-Ill content to provide asaurance th~t adequate dilution is afforded by the meteor-ological conditions th~t actually prevail. If the collected data show the calculation to be in error, the 3.l curies per year Iodine-Ill atack diacharge limit will be subject to raviaion. There are two aafety factora not taken account of in the above calculation. cattle \li11 be on pasture approxiately one-half of each year, and losses to the soil have been oeserved to reduce the effective h41£-life to Iodine-Ilion grass to approxi-mately 5 d3Ys. These factors woul4 reduce the average dilution needed to 6.7 per cent of the 5x10~ cubic metera per second normally expected value. 0.067 _ 5 x 1.0 x 106 2 x 6 x 5 x ~"5'5 Abrupt complete failure of the iodine removal equipment is unlikely. But if this should happen coincident with stack monitoring failure and release all the Iodine-l3l in a pre-ceSSing lot of fuel under inverSion meteorological conditions, the maxi~m concentration in milk expected to result may be computed to be 1.8 x IO~u curie per liter, and the projected do.e to the thyroid of a child drinking 1 liter per day of milk following such an incident would be 2 rad. which compares to the Federal Radiation Council Protective Action Guide of 30 rad. to an individual. The limit for particulate release is based on the normal dilution reducing the average concentration to 2.xlo- l4 microcuries per milliliter or less at ground level beyond the exclusion area. (Chanae No. 4 Revision)
4.2 RADIOACTIVITY CO!ITENT OF REI.EASED LlQ1JID EFFLUENTS APPLICABILITY This specification establishes limits for the discharge of radio-activity contained in liq~id effluents from the site. OBJECTIVE To provide reasonable assuraace that coacentrations of radioactivity in Cattaraugus Creek will meet the requirement. of Title 10 Code of Federal Regulations Part 20. SPECIFICATION 4.2.1 ALL PROCESS STEAM CONDENSATE SHALL BE COL1.ECTED BATCmnSE AND SAMPLED FOR *GROSS ALPH::\ AND BETA ACTIVITY. THE CONDENSATE K\Y BE DISCP.ARGED l'lITI:OUT PASSn;G THROUGH THE STORAGE lACOONS AFIER IT IS DETER.'1U:ED THAT ITS CO:;CE.illRATION IS 0.3 P!CCCU3.IES PER MILLILITER OR LESS. ALL Ol',::R LIQUID p1J\!a EFFLUID;TS CONTAnm:G RADIOACTlnlY FRO:1 PLANT OPEP.AT!ON OR l-lHICH HAVE BEEN IN CmmeT WITH EQUIPMEh"T CONIAL~ ING RADICL\CTIVITY :S!iALJ., DE rAiNIIOiU!i i'i' N; nU.n~ ~-:O~:l'rcR SET 'I*O ."..!..A'p.M AT 5 11:\NOCL'RIES PER. llIL!.ILI'l'ER AND SHALL BE COLLECTED IN Tl'..E IN'!ERCEPIOR. THE It.'IEF.CEFroR DISCHARGE VALVE SHALL BE FULLY OPENED AFTER ']"aE m:~ERCEP TOR HAS BEE:I SAl-!PLED Alm tHE ANALYSIS vtRIF!ED TO BE LESS TIt-\,'1 5 Rl\l;OCUitIES PER l-lIL1.ILI'!ER. THE COltrEllTS SP.ALL BE DISCHA.l:tGED AS P...\.PIDLY AS POSSIBLE. WHEN THE nrrERCEPIOR IS E>-1P"IY, TUE DISCP.ARGE VALVE SHALL BE CLOSED A~1) '!HE CYCLE REPE.\I!D. IF TIlE I~;tIl:E l'DNITCR AL.WlS DURING DISCHARGE OF 'IHE n'TERCEPTOR, THE DISCH.'lRGE VALVE SF..!1LL U CLOStI) n!::EDIAIEtY AND 'IF";;: CAUSE OF 'niE DIFFICULTY DE1'ER1mlED Alm CORRECTED. £'JRING AllY CALt..'ID.\R QUARTER NO MJRE TP~~ 48 CURIES CC:mTh"ED EQUIVALENt UNIDENtIFIED ALPP_\ Alm BETA ACTIVIty OTHER THAN TRIrIUM OR 1-131 SHALL BE 'IRANSFER.'U:D TO THE LAGOONS. 4.2.2 ACTIVITY RELEASED TO CATTARAUGUS CREEK FROM ALL SOURCES ON THE SITE SHt\.LL 1.;01' AT ANY Tn!! RESULT IN A CONCEh'"l'RATION, AS MEASURED AT THE MONITOR!NG STA'IION IN CArrARAUG'JS CREEK, WICH EXCEEDS 'l'!UCE THE CONCE~"IRATIOU SPECIFIED IN T1TL! 10 CODE or FEDEaAL ltEGlJLUIO!IS PART 20; PROVIDED l!:l~n:VER. THAT IN ANY 365 CONSEClJTIVE DAY PERIO!:. THE AVEP.AGE CONCENrRA~ION OF MDIQ.\c.uvm IN C--\T'IJ..!t.'UGUS CREEK SH.u.L NOT EXCEED THAT SPECIFIED IN TI'l'LE 10 C::>~E OF FEDERAL llEcrJIATIO!;S PART 20. SUfFICIENT DATA ON n'REAM FLO~~S AND MDIOISOTOPE CONCIDn'p.&'TIONS ~1!JST BE RETA:C;.ED TO DEMJNSIRATE COMPLIANCE WITH TlTLE 10 CODE or FEDERAL RECULAU:lNS PARI 20. (Change No. 4 Revision)
- 16a -
BASES these specifications limit the radioactivity in the storage lagoons and the radioactivity concentration in Cattaraugus*Creek. The discharge of Uq'Jids from the site has been discussed in paragraph 7.11 through 7.13 of the Pinal Safety Analysis Report. The dominant isotope in the liquid effluent is expected to be tritium for which a separate analysis "'ill be made. {See Specification 5.1.2). In addition, the quality of liquid effluents may I:.e such that the quantity of other isotopes such as 5r-89, Sr-90, C6-l37, Ce-l44, Ru-106, 1-129, 1-131, and Zr-Nb-95 may also have to be specifically measured. The alarm setti~g of the inline monitor will be established in terms of beta activity o!:Ger' than tritium as dete:cmined by analyses of the liquid flowi~g through the*neutralization tank As shown below, the limited plant throughput of tritium makes it unnecessary to detect tritium in analyses of liquid samples from the interceptor.
"Combined equivdent unidentified curies" will be calculated as follows.
Wh~n Rop~ifi~ ~na'vReR arp m3de fnr Anv iAn~nOF.. thp r.uriPA ~f thAt iA~t~pP found ~ill 'be multiplied by the ratio ~f 3xlO: 7 *.* wei the "equivale:!.t curies" so determined will be summed as illustratad in the follov!ng example to determine the total amount rele£sed to the lagoons * .1-131 13 a special case. For 1-131 a minimum holdup time of 48 days (6 half liVES) is assumed in the lagoon system, and credit is taken for this decay. EXAMPLE: Assume that an interceptor batch is found to contain 10 curies of r&dioactivi:y other than tritium, plus 600 curie, of triti~m (from 2 tonnes of fuel). Specific analyses are made which show teat the isotopic composition. except for' tritium. 1s as follows:
.&u-l06 4~
Zr-95 3~ 1-131 251 Other (unidentified) 51 total lOOi
- 3xlO- 1mi.::oc;uries per milliliter is'the mixiQUm p'!rmissicle concentration in unrestricted are~s for Sr-90 which is one of the mos~ radiotoxic isotope expe~ted ~o b~ released in the liquid effluent from an irradiated nuclear fuel pro~essir.g plant. MPCi is the maximum permiSSible concentration for each port!:~lir iSotOpe as indicated in Appendix B,table II. Columr. 2 of 10 (.lR 20. .
(Change No. 4 Revisi~n)
\
l6b - Then the "equi\o",len: unidentified curies" are: Equivalent 3xlO- 7 Iodine Unider:.;ified hot ope MPCi Factor Curies Ru-106 4 lxlO 5 D 0.03 0.12 Zr u 95 3 6x10- 5 0.0048 0.015 1-131 2.5 3x10- 7 1 0.0155 0.04 Other 0.5 3xlO- 7 1 0.5 (unident if ied) Combined Equivalent Unidentified Curies 0.675
!he contribution of the tritium would be calculated as follows:
Equ1vale:l.t 3xlO- 7 :odine Unidentified Isoto~ Mea!u!'ed Curies MPCi M?C1 Fa::tor Curi .. ! H-3 600 ',r10-3 lxlO* 4 - 0,06 It is app:arenc from these calculations that tritium need n;,t be specifically analyzed to determine its contribation to the "combined equiv3lent unide::l:ified curies. " It is r.ot the i:ltent of NFS to discharge from the ph:.:: the maxicum quantity of r2dioactivi~y which could be acco~aated within permissibl~ c~r.~entrations by the flow of Cattaraugus C~eek. Pruden: plant operation dictates that the quantity of radioactivity released to Cattaraugus Creek be k~pt at the lOI:eat pract'ical amount. 'Io assure an in-depth cor.trol of l!qu1c effl~E.nts rdec!ied to Cattaraugus Creek, a quarterly limit of 48 curie eq~1v~1~d~a of l1qaid discharg~d to the lagoons he, be~n set, and tKe ,on~e~tratlo~ ~! liqUid fed to the lago~ns is limited ~o S.xlO-~pc/ml. TheBe limits are ,onsis:~r.t with meeting the requirements of Specification 4.2.2 in CAtta=Augus CrEek. Activity released into the liquid effluent system goes throug~ 4 S~p6r4te holdup units, via ac interceptor. a 300,000 ga1lo~ lagean. ar.d two !u~cessive 2.300,000 gallon lagoons. Thus. there are f~ur separate ch~n;e5 to 6ppreh~nd errant activity and the total possible holdup time is about fo~~ ~~ths * .Plant operations. therefore, has a high degree of*,on:ro1 over the discharge of rsdioactivity in the liquid effluent and there is plenty ~f tice to shut the plant down in an orderly fashion if thiS Techni,al Specif~ca~ion cannot be met. (Change N~. 4 Revision)
\
- 16c -
Continuous 8ampling will be conducted at the monitoring atation near the aite boundary on Cattaraugus Creek. At least on". weekly basis. the cOmDosite aample from this station (see Specification 5.1.2) will be analyzed for gross " alpha and gross beta activity and for tritium. Discharge from the atorage lagoons will be rceulated to conform to the flow in cattaraugus Creek. Stream flow is measured with an instrument which records the level of the strezw. "!he flow i8 calcul~ted uSinz tne cross Dcction of the stream bed and a series of ~eloeity measurement8 at various water heights. An auxiliary monitoring 8tation baa been provided near the plant 8ite at the confluence of Frank's and Quarry Creeks. This station aerves a8 a sensitive monitor of any un=uspected or unregulated discharges. Measurement of flow at this point and ~inte~ance of the system is quite difficult"due to the "rugged terrain. Consequently data taken here cannot be expected to have the consistency neceosary to r~ke use of tbi3 st3tion as a part of the discharge inventory. It will. however. be maintained in operation to the greatest extent possible as an added ~rgin of safety. "
"(Change No. 4 levil1on)
5.0 HINnruH C01IDITIOUS FOR OPERATION The specificationa included in this sectioD set forth minimum cODditione for safe plant operation. If Specificationa 5.1.1 through 5.1.3 cannot be fulfilled the operations which could cause a release of radioActive effluents ~st be shutdown with the £:ception of the ventilation 8y~cem which normally is kept OD, until the probl~ are corrected. The other
.pecifications in this section provide *prtmary and alternate conditions which may be fulfilled. If the alternete cOn4ition 18 in use the opera-tiODs shall be ccnsiciereci to be continuing in * "ready condition." Ii neither pr~ry nor alternate conditions for a particular operation csn be fulfilled the operations shall be shutdown with the exceptio~ of the waste tank off-gas system which bas to remain OD stream while appropriate ~epair. are made.
(Change No. 4 Revision)
5.1 E:1'Ll'ENT }-lONIICR!NG APPLICABILITY This spEcificstion applies to the equip~nt necessary, tbe frequency of Ba~p1i~g, and t~~ ?nglyses required for radioactive g~seous and liquid plant effluents. OBJECTIVE To assure th9t monitori~g equipment will be in operation and sampling and ar.dyaEE will be perfon:ed to permit appraisal of liquid and saseous radioactive effluents. SPECIFI:AT!ON 5.1.1 ALL BATCHES 07 L!QUm PLANT EFFLUENTS "LLECIED IN ACCORDANCE WIl'R SPECIFICATION 4.2.1 SHALL BE ANALYZED FOR RAD!!)ACIIVIIY CONI'E};"'X. 5.1.2 A CO~"Tnn!ous SA!'!I'LER WHICH OBTAINS A REPRESIDlTATIVE SA."1PLE EltON Ci.TTAFJ.UGUS CREEK SEALL :BE IN OPERATION w1iENE'V.c.R L!QUID IS DISCHARGi:'i) rROH 'I"'dE S:l~RAGE IAGOO!;S TO VERlL'-Y CONrORl*!.-\I'CE WI-:'H THE P.ADIOACTIVE CONCE1~~T!ON Ln1!TS ESTABL!SHED BY SPEC~I~~TION 4.2.2 *
. AT LEAS'X A WEEKLY CO!a'OSI'l'E SAliPLE FROM THIS STAT!ON SHALL BE A.~LYZED FOR TRIT!"Ul-l :".~"D FOR G=--OSS ALPiL\ A!r.> GROSS BEl'A ACUVITY. IF THE CON-TIlo."UOUS WIFLER FAILS, A l-!AX:t1UM OF 2,000,000 G.~LIDNS M.I\.Y BE DISCH#.RGED ANNUALLY F:t!Y';!DED TF..;\T 5.UlPLES OF CAT'IARAUG'JS CREEK ARE COLLECTED H,\1\:.:ALLY TO VERIFY Cm;rORH.~NCE WnH SFECI!'!CATrON 4.2.2. Ir l-'...\IDAL SAHPL!NG IS NECESSARY, THE FREQt!!NCY SHALL BE AT UAST O:;Z S,,\liPLE PER DISCit~GE OR PER 100,000 GALLONS DISCR.~GED, WHICHEVER RESULTS IN THE GREATER SAHPLING FREQUE~:CY
- 5.1.3 THE 1-131 ~~ PARTICL~TE SAMPLER LOCATED BESIDE THE STACK WUICH COLLECTS A REPRESEt..*:A:i:IVE WIPLE OF THE STACK GAS S'rl.4.LL B~ IN OPL.ll.AT!'JN AT ALL TmES .um THE s..~!PLES COLL:E.GTE&> SHALL BE A.~4.LYZED AT LEAST WEE:~LY TO VERIrY t::>!>TOa......AN:E Wlm SPECIL'IC.A'l'ION 4.1.1. IN ADDITION, THERE S?_\LL BE CONI'IN'JOU5 MJI~lI'JRIN:; O!' THE STACK GAS FOR 1-131, KR-8S, A~'"D PARIICtl'!.-~TE
*BADIOACr:V:TY. IF TrlZ CONInWOTJS l-DNI'!'OR FAnS. A S.AMPLE COLUCIED 'l'SROUGH-OUT EACH SHIFT SR.~LL BE ANALYZED FOR 1-131 }~D PARTICULATE BAD!OACTIVI.~;
ltR-85 MAY BE C.~LCULATED FROM Fm:L BURNUP DATA. (Cbsnge No. 4 Revision)
- 4S -
BASES Technical Specifications 4.1 and 4.2 establish quantity or concentration limits for radioactivity released from the plant into the atmosphere and the watercourse. This specification est~blishea the locations where mon-itoring shall be performed and the monitoring equipment necessary to show with a high degree of certainty that co~,liance with Specificationa 4.1 and 4.2 is attained. The methods of operating the low level radioactive liquid waste discharge a,stems are discusGed in Sectiona 7.11 to 7.13 of the Final Safety Analysis Report and in Section XIV paragraph AS of Submission No. 27 of the Final Safety Auslysis Report. TneGe sections indicate that low-level radioactive liquid waste will be collected batchwise in interceptors at an approxirdte rate of 40,000 gallons per day end will be sa~led and analyzed. The weekly saeples at the off-site monitoring station will be analyzcQ for tritium ar~ gross alpha and Deta activity. This c~d~s ouer~ndi should provide knowledge of the quantity of radioactivity releasGa to tne storage lagoons and released to Cattaraugus Creek and will support a showing of compliance with Specification 4.2. T'ue w....kly 1l1uuy::n:. gf the cou:po.ite .ample. collec~ea oi radioiodine ana radionctive particulates will provide a basis for determining the complian~e With Specification 4.1.1. (Page 46 1a deleted) (Change No. 4 Revision) .--~"'--"'--;--.' - ... -.-.
*
- 110954 7.1 AmiINISTRA7IVE REOUIREl1E:N"""TS APPLIO.BILITx This specification establishes udministrutive standards for governing the operation of the facility.
OBJECTIVE To assure that a manage~znt system re5?O~5ive to the safety needs of the operation is established and r.zintained. SPECIFICATION 7.1.1 OR~~IZATION. FOR PURPOSES OF l~\I~~~J.NING SAFE OPERATION ~~ COt-l"TROL OF THE FACILITY A1'D OF ATTENDANT ACTIVITIES, N'JCLEAR FUEL SERVICES, INC., SHALL PROVIDE ¥~\GID1EN"T OF l~ PLANT THROUGH AN ADMINISTRATIVE FRAMEWORK INCLUDING, BUT NOT Lll'fITED TO, THE FOLLOmNG:
- 7. I.. L 1 A GENERAL MANAGER, HAVING THE OVERALL RESPONSIBILITIES FOR ALL ACTIVITIES AT THE PLA~"T INCLUDING HEALTH AND SAFETY.
NUCLEAR SAFETY, AND ADHERENCE TO THE LIMITS AND CONDITIONS ~r;:'r FORTH IN THIS LICENSE. 7.1.1.2 AN ASSISTAl-.'T GENER~L HANAGER, REPORTING 'IO THE GENERAL MANAGER, DIRECTLY RESPONSIBLE FOR ALL THE ACTIVITIES AT THE P~~~~ INVOLVING HE"I\.LTH AND SAFETY, :t-.'!JCL:t..'ill SAFETY. AND ADHERENCE TO THE LIMITS MlD CONDITIONS SET FORTH IN THIS LICENSE. THE HEALTH AND SAFETY DIRECTOR AND THE TECHNICAL SERVICES MANAGER REPORT TO THIS ASSIST~~ GE1LRAL ~~GER. . 7.1.1.3 A PRODUCTION 1,i.4....~GER, REPORTING TO THE GE~"ERAL MANA.GER, AND RESPONSIaLE FOR CARRYING OUT PRODUG'T!ON ACTIVI'1'IES IN ACCORDANCE WITH APPROVED PROCEDURES M'D ACCEPTED HEALTH AND SAFETY STANDARDS. 7.1.1.4 A ~~LTH:~ SAFETY DIRE~rOR, REPORTING TO AN ASSISTA~ GENERAL w..N.,\.GER, AND RESPONSIBLE FOR IJ.DNl'rDRING THE RADIOLOGICAL SAFETY OF ALL PI.Al\'T AG'TIVITIES AND FOR ADVISING ALL DEPARTHEt.'"TS ON RADIOLOGICAL SAFETY }tATTERS. 7.1.1.5 A TECHNICAL SERVICES i-tANttGER, REPORTING TO AN ASSISTAl-.'T GENERAL 11A;.~GER, ~'ID RESPONSIBLE FOR REVIEW OF PROPOSED CHANGES IN DESIGN WITH RESPECT TO R.II.DIOLOGICAL AND NUCLEAR SAFETY, Ah"D RESPONSIBLE FOR A CONTINUOUS REVIEW OF OPERATIONS TO ASSURE NUCLEAR SAFETY. (Change No. 4 Revision)
*
- 11U95 7.1. 1. 6 A PL.t...NT SAnTY CO:*l;*lIT72E ICSPO~~SIBLE FOR: REVIEW Ar-.1)
APPROVAL OF ALL STANDARD 0?Z~~7I~G PROCEDu~ES A.~ LETTERS OF AUTRORIZ,6.TION; REVIEl-l AND APnOVAL OF ALL CH.-'l.NGES IN 'iriE PROCESS, THE nOCESS SYSTEM, A~1) SIA:'iDAR::l O?SR.-\TING PROCEDURES; I~'VESTI GATION OF ABNOR}!.;\L OCCURF,ENCES j,;-:UCH !.:p.y AFFECT RADIOLOGICAL SAFETY OR CRITICALITY PREVEt-.'TION; i.:ill ;mcm*!}lE~"DATION OF MEASURES w1iICH HILL PREVEl'i"T REPETITION OF SUCH ABNOru"'_o"L OCCURRENCES. T'dE cm'lHITTEE Si'},LL CONS 1ST OF, Bu"T NOT BE LI}!ITED TO, 'idE GENERAL P.ANAGER, THE ASSISTANT GENERAL l-~-\~:AGER, THE TECHNICAL SERVICES M.6.N..l.GER, THE HEALTH AND SAFETY DIRECTOR, Al\'D THE PRODUCTION P.ANAGER. 7.1.2 PROCEDURES Sao.LL BE P.AIl\'TAI~~D UNDER THE OVERALL DIRECTION OF THE GENERAL }lANAGER COVERING TH,E: 7.1.2.1 PRE?A.:,\ATION, APPROVAL, AND ISSUANCE OF ALL OPERATING INSTRUCTIONS AND CHANGES TrlERETO, INCLUDING, Bu"T NOT BE LIMITED TO: STANDARD OPERATING PROCEDURES, LETTERS OF AUTHORIZATION, RUNSHEETS, SPEC LO\L l.J'ORK PROCEDURES, A~1) EXTENDED WOR-I( PROCEDURES, WHERE NUCLEAR CRITICALITY OR RADIATION SAFETY ARE CONSIDERATIONS. 7.1.2.2 I~'VESTIGATION OF ABNORK.l.L CONDITIONS WHICH INVOLVE THE PROCESSING, HANDLING OR STORAGE OF RADIOACTIVE M.A..TERLLS, AND WdICH AFFECT NUCL~.R CRITICALITY OR RADIATION SAFETY. 7.1.2.3 ACTIONS TO BE TAKEN IN EVENT OF AN EMERGENCY INVOLVING RADIOACTIVE }lATERIAL. SUCH ACTIONS TO INCLUDE, BUT NOT BE LIMITED TO: Sh1JTDOWN OF SPECIFIC EQUIP}iENT, ACTIVATION OF THE EMERGENCY PI-<'IN, Sl.J1U-'.DNING OF OUTSIDE SUPPORT, AND REENTRY TO THE ACCIDENT AREA. 7.1.2.4 PERFOR}!.ANCE OF PERIODIC REVIEWS OF OPERATING PRACTICES, RECORDS A1'D AUDJ:TS.
- 7. 1. 3 PLANT OPERATION. ME}!BERS OF TP~ PRODUCTION OPERATING STAFF SHALL HAVE A THOROUGH KNm.JLEDGE OF TrlE PROCEDURES r,oVER.'HNG THE v,'ORK FOR WHICH THEY ARE RES::?ONSIBLE. DRILLS SP.ALL BE HELD AT SUFFICIENT FREQUENCY TO ENSu~ PROFICIENCY IN EMERGENCY PROCEDu~S. A COMPLETE A1u CURRENT SET OF OPERATIONAL PROCEDURES SHALL BE PROVIDED IN THE C01'TROL ROOM AND IN OTHER APPROPRIATE AREAS WHERE C01'TROL FUNCTIONS ARE PERFORMED.
(Change No. 4 Revision)
11095t> 7 .. 1.4 DE'I'l.. IL:2~ ~..r:tI*~~Z'Z:: P:ZCC~:L-..'l:S) ?~:;.:: 5:=:':":'8, LZrI'ERS 0;;: AliIT.JRlz...~~..:~O~ P.. (W E}:?2r~D~J ~*:o[.'~,~ P1,':;CZDL:7SS Si-:L_:'L r;: *?3..::'i'v"2:J:n ?()~ OPERA,T!ON OF LhE P!AJ.T.
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.~UJ r03. ~;!)IA!::ON P?-DTECTION SPJ.LL BE PROVIDED.
- 7. 1. 5 LOGS AN;) RECO?J)S. LOGS :,"~:D RECO?DS SF-t.LL 3::'; E"U~;'!}.I!rr:J AS REQUIRED
- 3"{ TeS nOVISIox;..L LICEKSE A,.\!) S::!,:;"L I::CLUD3 1'!IX"tJJ:::::S OJ? }SETI::GS OF 7HE PL.<\NT SAFETY CO:'.!:-lI'f:I'EZ AS IlELL AS DZ*Z"':i:LS OF INVES'!IG.6.TIONS AIm aECOX2'olEND..<\a TIONS IN REGARD TO AllI(ORl*:AL OCCURR::::\CES Al:J AG'?!ONS TAKEN 7HEREON.
7.1.6 AUDIT OF OPE!l..I.TIONS. ~*:'\~~.t.G::::'.:s;;:: SH.'J..L PROVIDE FOR PERIODIC AUDITS OF ThE O?E?.'"J:'IONS THROUGEOl;-:' 7;::; Elens FAC"Jl,I?1 HITH REGARD TO R.<\DIOLOGlCAL Mil) NUCLEA..~ s!2ETY. TlillSE AUDITS SP'~~LL BE PERrORl'IED BY COHPETENI' Co}!PANY OR OTBLR TECH.:nCAL PERsm",,;;:L NO:.:' DIRECTLY RES?0;~SIBLE FOR THE OPERATION AUDI7ED. 7.1. 7 IF A:lY TECPJ:HCAL snCIFICATION LIi'GT IS EXCEEDED. THE ::OLLOWING PROCEDLKES WILL BE OBSERVED: 7.1. 7 .1 Il,;:'fEDL.!"TE STEPS SI{ALL !lE TAKEN IN 'I'l'lE OPERh.T!ON OF THE SYSTEH !N'vOLVZD TO REI':OVE TilE CAUSE O;? EXCEEDING TRE S?EC1?ICATION OR TO RELIEVE ITS EFnC'i'. AS APPROPRIATE. O?ER..6.TION K".Y Cm::7INUE IN 1-. "READY CONDJ:'I'ION" TEMPOR.,<l.RILY Ui-."LESS THERE IS A..'\07HER OCCURREI;;CE OR IlillIC-.l"TION OF Iu"l OCCURREYCE TEAT HOULD FURTHER REDUCE ~r:Z M.~1GIN 07 SAFElY
!N WHICH EVE;';"! IHMZDL-\TE SlftJ':i.'DO:"X IS REQUL.'tED.
7.1. 7
- 2 TI{tiEDIATE STEPS SHALL BE TAKEN TO ESTABLISH THE c..';'USE OF THE OCCUR.1U:NCi:: IN 7.1.7.1 BY RESPONS:i.ELE K.\NAGEMENT REVIEW.
7.1.7.3 NOTlHTHSTA1'DIXG J..lTY OTHER PROVISION or. THIS LICENSE w.s PLA~'T SHALL BE S"nuTDO:m A::"TD l\ORl*:AL PROCESSING OPERATrONS
't:1AY NOT BE RES'J}2D PRIOR TO ALC REGtrLA~O:'<'Y CONCURRENCE WHEN SPECITICATION 4.1.1 OR 4.2.2 HAS BEEN EXCEEDED.
(Change No. 4 Revision)
- anuary 2*1, 1967
;,.I~:\,:,. \ .. !~. '"~.ik~:** c. J Irradiated Fuels 3ranch lj. ',. -:- .. ,
. ,~. ~ * . , <0
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J~~:....!"';1.l':~":,", '.:": . . ~~ 7.3.:1. I.c:.n:l.tt<<);.:~ :;0 i:.~gh rad!ati-::n orear. w!-'~J~:,~ an indivi-dual :night l'ecei'le a dose 0; J.OO mlllirern in one hour shall oe cont.roUtd
~y locked ~oors witt) the possessiun of key~ to ~je5e doors 11~lt0ci ~o ~~S managonent per~0r!~el.
- ~~~C~ ~r~(l~ly ~~ }o~~c~; ? s:r~te~ !~ch Z~ ~tnnc~:in;~ c:~nE:~cc!
'..;Y ::~-"2:>2S 1/,'1:1; :1:gh rlldiaticn Z.~qIiS titt;;:;.ci~ec to \1.11 sic!eF will
;)~ u:Jt'l*i :;.\.) tL.;;~ :hG' ;,:*~diBti.on levf:l at trH? bou!idery ~,111 be r.:::, :"",,"""/~"\r 0-' ' ot"'c:-
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,';:-:2n they ('ntG!' cr'22lS where the r1!diaUcn expo!;ur'!': pctentL:,l may:::" 51:::n-iricunt. The amV0 prccecu:'e compliet with tr.f:' intent "f :J CfK 2C. :;;;;ne
<".teas of the ;.JLnt such a..:; :;C:::L-:;2S0s.:.:-,at Cl-e necessary !';;JI' (,vdcua-:io;1 puroo~es hr.".:'8 high r?ci{!tior, leV'~?l!: fro~ t.:i::t:; tc ti~~!? ~~i:-.~.; t:":~~~ ar~,:;z Cdnno~ b~ readily lockc>c f';;C for safety rearcns :;:houlc not ':~ locked ou.l.:, we
~~opose to use the methcc ccscribed in 7.3.2 to warn per£onnel of high xsd-iation a~eas, so that they can not unintentionally enter t~e~e erea~ * .. e bdJ.ev ;~:-:£ ,,':c"_';:' chan-;:).:; in tne Technical Specification£ is jl:.st!fied. 3hould any c;ue:sticms :uise, ;'ie shall be happy to supply additional inforoatio: Very truly yours,
- 'i'1L/33</sk I'i. H. Lew! s C--e(J02ral ~~an.a(
- -I:r cc: J. ).nccrson bee: M. E. ~eech
CHANGE NO. 5 110898 N'GCLEA~ [UEL § E ~VICES.li_N_C_._ __ A SUBSIDIARY or w. R.ORACE /i. CO. sox 124 .,. WEST VA 1..1.. EV. N. V. 14171 AREA CODE 7115 TE .. E .... ONE g~2-323e I September 21, 1967 Dr. John A. McBride, Director Materials Licensing Division U. S. Atomic Energy Commission Washington 25, D. C.
Dear Dr. McBride:
Nuclear Fuel Services, Inc. hereby requests a change to Technical Specification 2.3 of Provisional Operating License No. CSF-l. We wish to increase the possession limit for Cesium-137 so that we may use a sealed source for calibrating survey instru-ments. We propose to obtain a double encapsulated, nominal 30 curie source (U. S. Nuclear Corp. Model CCSD-30 M). Vie request that Specification 2.3 be changed to include possession of 33 curies of Cesium-137 as a sealed source. This source has been discussed with Mr. W. Ray of your office. If further information is necessary, pleace contact me. Very truly yours,
,j ;1
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J. P. Duckworth, W~nager Technical Services JPDlJRC:ah cc: T. C. Runion B. G. Bechhoefer J. D. Anderson
UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 205"5 IN "EP\,Y IW'L" _ DoCkot NO. 50-201 OCT 16 1967 Nuclear Fuel Services, Inc. Box 124 West Valley, New York 1"171 Olange No.5. License No. CSF-l Attention: Mr. W. H. lz.ds Vice P:-~sicbnt and General H.;:nager New York State Ato,.d.c and Space
.......,""0*..- ..... A . . ."' .......;ty
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230 Park- Avenue New York, l:aw York 10017
. Atter.tion: UrI Oliver Townser.d Ciainnan Gentlerne."'I:
This refers to Nuclear Fuel Services' request dated Septerr!ler 21~ 1967 9 for a c.~e to O~ ..ade in Technical Specification 2.3 to authorize possession of 33 curias of cesium 137 as a sealed source for c:alibr-at:i!'.g survey ins'tr\::r.an'ts. This request has been designated e.s Proposed CMnge No. 5 end r.as been considereci pursuant to the provisions of S~ction 50.S9 of 10 eFR ?a..-t SO, ~~ .: 10 CFR Pa..-t 30. We have reviet:ed the proposed cha."'l~ and have found that it dces ~ pre~ sent significant hazard considerations not: describo..d or :i'llplici't in the NFS "Fi..-.cl Safety l:lalysis Report" and that there is reasonable c:ssuraTl::e that the h!alth and s.aie'tY of the public will nat be endang~ by the change. Tecllnical Sp~ifica'ticn 2.3 e1:."3ntly ~\l'thx'izes the pc..ssession and use of rateri.als for calibrating survey instnur.ents. Authoriza-:ion to possess a.""ld use cesium 137 would provide NFS with a greater flexi-bility in call.!:rating instn:mmts. The cesium 137 will be :in a sealed aouroe assuring con:f1T.e:xent.
t.'uclear Fuel Services, Inc. AND New York State At~~c and Space Develop-nent Authority Accon1lngly, pursuant to s.ction 50.59 of 10 CFR Part 50, and the requirCt'mts of 10 CFR P.:..""t 30, the follco.nng a.uthority is added to Section 2.3 of the Technical Specifications of Licer-.se No. CSF-1:
,*".ater:ial -,
Fonn Possession Ll.:nit tt Ceaium-137 33 curies Slnceroely yours, C!::;:;~;!I S::!~~d to"l J. A. [;;c.;r;~; J. A. KcBr5.d3, Director Division of Haterials Licensing cc: Mr. T.' C. Runion Hr. B. G. Eschhoeier Mr. Jon D. Anderson
- UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON.O.C. 20'.'
- l1U72~
JAN 2 7 1967
'N "£P'L Y RU[R TO:
Docket No. 50-201 Nuclear Fuel Services, Inc. Box 124 West Valley, New York 14171 Attention: Mr. W. H. Lewis Vi~" Pr.~sid.ent and Generel !I..a.ne.ger Gentlemen: In your application dated December 16, 1966, you requested approval to install a beat exchanger in Waste Tank 8D-2 to boil off excess water. Since the proposed installation involves the possibility ot a nuclear accident of a different type than those previously analyzed, please submit a safety analysis re~ort of the installation and its operation in accordance with 050.59(d) of 10 CFR 50. The safety analysis should include, as a minimum, the following:
- 1. A complete description of the proposed installation including a description of the piping and controls for providing steam to and remOving condensate from the heat exchanger.
- 2. A description of the methods of controlling the dispersion of radioactivity during installation and servicing of the heat exchang~r.
- 3. An evaluation of the effects of mechanical stresses on the system due to differential expansion of piping, buoyancy effects, and the movements induced by the convection currents in the boiling fluid.
- 4. An evaluation of the consequences of and a description of the means for coping with the development of leaks in the heat exchanger and piping. Consideration should be directed to but not lim! ted to the following:
- a. Suck back of radioactive waste solutions into the heat excbanger and piping upon tbe termination of steam flow.
Nuclear Fuel Services, Inc. JAN 2 1 1957
.1..1.UI~U
- b. Discharge of radioactive waste solutions with tbe con-densate from tbe heat exchanger.
- c. Overloading of the waste tank condenser if 8 leak develops in the beat exchanger or its associated piping in the tank. Our calculations indicate that a complete break in the two-inch Schedule 40 inlet steam pipe could release sufficient steam to overload the on-stream waste tank condenser.
- d. Dispersion and entrainment of activity in the steam, resulting in a carry-over of radioactive material to the waste tank condensers, if break occurs in tbe heat Q
exchanger or its piping just below the liquid surface.
~2~~/).
A. E. Aikens, Jr., Chief Irradiated Fuels Brancb Division ot Materials Licensing cc: Mr. Oliver Townsend
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- iystlt!ll ~"~JI't'l 9racueUy anG avol<f cHf.rent101 r:e4Hn;: lind atr?u1n1 of thf: t.::ni< i'. lei V-c',,! t. ,:1~~;'. ~;.c tan¥. *:"ntenta have :r.'G~e<! 00111I'1<J
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Mt 11011 off frOfJl 9[.-2 ...111 ~ ::'7'Y.J ~otlnc, ~f ~tf11' ::-or hour. -:1'111 qwanU ty wHl !)f) 'I'd th1n the c"pa<:i ty of 1:;-5 tor reoooYapoutlon. Tho InstdllUon will eon,ht of *
- tut! he_tf'd tube btll\f.U. su.p.nt!~
Yertically throU9h the 12" nOl:tl~' ~u!;nllteC as the:ono!l1on hatch on 3;;':-2. Tn. bundle rill :. 1.1:' IM\jl!Y.i will HUh to wlt.l-aln 2" of ~t:.
;,ott. of 3f. -2. Thlt Ou:lclle I'tU 1 bf! Iua;ende<! fr~ " concr.~ HUed plU9
!lWunted at tM Up of th~ ~l'l'cdon hateh !ln~ .111 be nrviee4 !Jy a T stU:1l 11nt! and 1" coru:l~nU~0 ,:,~~ -;;u ~ 1~ :'\9 ;-:1 V? ~ te_ sup~ly tdll
~e from t.ht! U'U of th. nut(' l:aak cquiplUnt ellclolun throu9h tPPl'OX-1AIately l~' 0% ? ~cb-4J te:llpOrllJ'y pipe ISOlIIted .DooIe Ql'OIMlc:i. :,;onden.. te will :;>e l'OturM<i throu9b _ ~Ol'U"f 1- line ~1:ta"oly 30 fNt to l'llhUng !tf~2'"A at the clhah.rg,t of PUIlIP ~-~. nu. eoM.~tlo~ will allo. ste&1l CGni!.n.~~ tQ flow ~o the waite la<)oonl !JU"; !h9l'~ will .. ':'.9
)4. " >'y-~Uloi to ::onduct ~ .te;N r..oneenute into !L-:. l;te_ flow
~.ll~ .. r.,quh~c 'tJy mean' Qf a ;r glebe valv. one! ?nssun "i~.Ibe"
\'rill ~
- uaIOlo :wln~ et. the cb. trAp to P9mt condenute .-pl1t1og.
~ ~~ 1112 srfl 1h0ll<<"l on <tr.'lwing. ;;;.- ~-2.)7-J. 4413-1!).t-"-102-~ * .wl>!A-L-2-B a~~ h~8t exchftog_r deta sheat AL3.
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;~ :;-,,-c(]'~rr ..J ,yl~h U'", ori'"ir;"l. ph.."; oS' !f (.~~ cduy is only a ~~,. ainutc.
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to,,! t.'I& 31-1 12" hatch. 1hh will ':I",k~ 1t p0I81~)1. to '~"Ple ",1 thout
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- UNITED 51' 1\ rES ATCMIC ENERGY COMMISSION WASHINGTON. [.c:. 205.5
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11U734 I-
'" AlAR G 1! 67 IN FtCF'. Y "(FER TO Dock'3t No. 50-201 i'
I I' Nuclear Fuel Services, Inc. Box 124 West Valley, New York 14171 Attention: Mr. W. H. ~ewis Vice Presijent and General Manager Gentlemen: We have rev1.ewcd the info1:"IDStior subil1:ltted with your letters of February 10 and February 15, 1967 con/:ernlng your proposed instal-lation of a heat exchanger in waste Tank 80-2 and have determined that the fo110\1ing Itdditional infO::!Ia~b~1 should be submitted for our review!
- 1. The design modifications *.rhieh will minimize the pOElsibility of weld failures on the heat exchanger system.
We discussed this point with Mr. Weech and noted that weld failures might occur in steam and condensate lines due to misaHgnment of the assembly. ~.r. Weech informed us that design modifications to minimize this possibility would be considered.
- 2. The revised Inethod for hane.ling the condensate from the heat exchanger. As you knc*w, the proposal to discharge condensate directly to the lagoons is not satisfactory.
J., E. Aikene, Jr., Chief lrradiated Fuels Branch II I
£llvision of Materials L1censiug I I
I I I I I
* , 11U735 NUCLEA~ fUEL §E~vICE8.I_:N_~_c_._ _ __
A !"'H.}!JSIOlo\.MY 0'- W M; O~ACE & CO sex 124WEST VALLEY. N.Y. 14171 "R~A coo!: 71e T~L!:Pt-40N-= 94Z-323!5 March 20, 1967 Mr. A.E. Aikens, Chief Irradiated Fuels Branch Division of Material Licensing U.S. Atomic EPergy Commission Washington, D.C.
Dear Mr. Aikens:
In your letter of March 6, lQ67, you presented two questions in relation to our proposal to boil-dovm th~ contents of Waste Tank 8D-2 using a heat exchanger installed through ?ne of the tank nozzles. I trust that the following statements and enclosed prints will satisfactorily clarify these points.
- 1. Design modifications to minimize weld failures in the steam and condensate lines have been made per Mr. Weech's discussion with your staff.
Six (6) c0pies of print 8C-T-377 Rev. 4 showing these modifications are attached. *
- 2. The steam condensate from the heat exchanger will be collected in batches and sampled before disposal; any condensate determined to be above allowable release limits to the lagoon will be routed back to 80-2 or the General Purpose Evaporator (7C-5). Six (6) copies of the revised drawing 8A-L-2 Rev. 10 are attached. Since each batch is sampled before discharge to the lagoon, we have effected a batch-wise disposal method for this condensate.
Should any additional questions arise, we shall be happy to supply the information required.
~ulJY~UrS,
~~
Assistant General Manager RPW: pm Enc. Dwg. 8A-L-2 Rev. 10 8C-T-377 Rev. 4 CCI J.D. Anderson wiatt. T.C. Runior] wiatt. B.G. Bchhoefer wiatt. J.J. Merkley wiatt.
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CHANGE NO.6 UNITED STATE:S ATOMIC Er .. ERGY COMMISSION WA5"1INGTON. D.C. 20545 Docket No. 50-201 Nuclear Fuel Services, Inc. Change No.6 Wheaton Plaza Office Building License No. CSF-l Suite 900 Wheato~, Maryland 20902 Attention: Mr. T. C. Runion. President AND Ne~~ York State Atomic and Space Development Authority 230 Park Avenue New York, New York 10017 Attention: Mr. Oliver Tc~~send Chairman Gentlemen: The telegram dated January 19, 1968, from L. D. Low to you transmitted the Atomic Energy Commission's authorization to resume processing operations at the liest Valley Plant. Your letters of January 13 and 15, 1968, descriLE:d the procedures to be followed at the West Valley Plant and identified certain actions to be taken and information to be supplied to co~?ly with the require-ments of the AEC letter of December 28, 1967. While it is not our intention that they re~~in a permanent pert of Provisional Operating License CSF-l in their present form, it is necessary to incorporate the letters of January 13 and 15, 1968, as license conditions until such time as appropriate changes to the technical speeifications, License CSF-l can be made. In formulating these additional technical specification~ required, consideration will be given to the additional information to be submitted by NFS, as described in the le:ters of January 13 and 15, 1968. Shortly after receipt of this infor-mation we ~ll arrange to meet with you to discuss the additional technical apecifications, and we expect at that time to be prepared to discuss other chansel
*to the technical specificationa as proposed by NFS letter of August 18. 1967.
,I
Nuclear Fuel Services, Inc. -~-. New York State AtomiC'and Space Development Authority On this basis, we have issued Change No.6 to License CSF-l pursuant to the Atomic Enargy Act of 1954 as amended, and the regulations of Title la, Code of Federal Regulations, Chapter 1, Parts 2 and SO to incorporate Nuclear Fuel Services, Inc., letters of January 13 and 15, 1968, as a new Section 7.4 of the technical specifications, the text of which is attached. . Sincerely yours,
.. J. A. MCBride. Director Division of Materials Licensing Attachll'.ent:
As stated above ec: Mr. W. H. Lewis, w/attachment Mr. B. G. Bechhoef2r, w/attachment Mr. Jon D. Anderson, w/attachment
Technical Specification 7.4 of License No. CSF-l Aa Authorized by Change No. 6 7.4 In addition to the other requirements and limitations of this license. NFS shall conduct operations of the plant in accordance with the provisions of its letters to the Commission dated January 13 ancl 15. 1968.
- 11U'720 tt:r * .!. :. ;,lkf~', Jr., *;;~ief I:rN.c:'ll1t~c 1'\1(>1& '1r?lnch Livl.1on of Uat~rlal LI'~nsln0 U. ~. I',. to!!'!! c f*nz-;:y .":o~isslf)n
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~:ucl(;ar' ;':uel !::u'vicc!. Inc., !i.:;&t Valley, Uew York hEHOy' requtu.t& II eli hetion :,C mado ln ~.l. 7 of ":."le fechni"id S...ecHlcaUone 0 f:::iF-l inc~far 3$ it pertaint to product loadou" operation.. rhe l.st four word, "Q:~ ;'.1{l.LUg ~i)l\['lJvr f.;Fi:.R\TI()NS" of ~nh j:,aragraph 5hould be calotecl.
~>y choos;1lY~ on@ of' two d.tectorll$ t.h~ .tack p.r't1cvlat. IIIOnltor c.n :Je tl'1:151U'I1! to .. 1ther bot .. OT (jlllllll8 9m1 .. 10n, ~;.ut n.lther detector is
$cnt-i'~lv~ ':0 t!',~ ;-ril:lu'y r,;oC~ of c'.cays for plutonlU11l or urlnlw:a produc~.
ProdIJr.~ h~G :~4!!1 3n-!!1 YZ9C beror. lo.clout for fission .ctivi t"l anc.' !Dust n-!~t !"t~i(J :n"cc,t;::t s,~<)*:t:'~;::at.io0s. In Mic;~ don. vent118t1on air f~CiI the lCft.~o'Jt hooc ~I!HN\ tt"tl:ounh ~I' ~b.ol ute fll tel'. t., ltpray stages, thr... co~r8~ fU ter 3t~n ~n(! a final co.. ree I':M eot!olute tilt"l' belon dhch.rg ** he t-0l1cvr th.; rt'c;utr~-mt:': 'to h'!v~ tnt! !'t;)CK r.!onit.orl:1': Sy!tt!M Or.fi>rl3t1n; a:.:rl..nq Pl'oG1Jct lo&doHt oper8t.1ons It'rvu no useful pUI"J'OIe. tMftiOft it b fQE t,"lG for!~]oir.g ciehtlon 1n th~ reciinlr.al ~jp .. c1flcat1on. h just1t'lee.
- ,houlc ,1ny ~!;e!\t!ons l
- !rise. "'" .. hall N) r. .)>y to supply .additional information *
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CHANGE NO. 7 & 6 CHANGE NUMBER - 7 WAS INCORPORATED INTO CHANGE NO.8 BY TELECOMMUNICATION MESSAGE Dtd. 9-13-68, 9-17 -68, & 10-17-68 SEE PAGE 2 & 3 ("VENTILATION SYSTEMS") OF CHANGE 8
, - I 11 (! '? -;
January 17, 1967 Mr. A. E. Aikens, Jr. Chief Irradiated Fuels Branch Division of Material Licensing U. S. Atomic Energy Commission Washington, D. C
Dear Mr. Aikens:
Nuclear Fuel Services, Inc. West Valley, New York hereby requests that Technical Specification 7.3 of CSF-l be changed to read as follows: SPECIF rCA nON 7.3.1 Admittance to high radiation areas where an individual might receive a dose of 100 millirem in one hour shall be controlled by locked doors with the possession of keys to these doors limited to NFS management personnel. 7.3.2 In lieu of locked doors for high radiation areas, wh~re doors (J.-Uil,,7l);\ .) ... t-'-~"-i cannot readily be locked,Astanchings connected by ropes with
.J-I;f i~
high radiation signs attached to all sides will be usedJe/ ,'I" r-4-~!I;;;t.',:,... 1.-;/ ~7 11\.... ,f".....*h'1 /0'11/4.. .r I:f ,../';/ N ",.-.Ai . 10CFR 20.203 (c)(2) requires that a means be provided to warn personnel when they enter areas where the radiation exposure potential may be significant. The above procedure complies with the intent of 10 CFR 20. Some areas of the plant such as staircases that are necessary for evacuation purposes have high radiation levels from time to time. Since these areas cannot be readily locked and for safety reasons should not be locked out, we propose to use the method pescribed in 7.3.2 to warn personnel of high radiation areas. ~ r/:/~";'7 ?-- "?,tf7 L./n /~ ~.,.,7"";"/~ v-nl'~ -!f'J<- ",/~_r, I We believe the above change in the Technical Specifications is justified. Should any questions arise, we shall be happy to supply additional information. Very truly yours, WHL/BEK/sk W. H. Lewis General ManAger cc: J. Anderson Vice President bcc: M. E. Weech W. A. Oldhlm R. 3. Keely
i BOX 12~"'V/EST VALLEY. N.Y. 1~171 li.r. R. 3. Chit'::o:J:i, ChiQf Irradiat0cl Fuels 3=3nch Division of :.::(to::-1als Lic*:;l:,~.n;; Unitad St.at0s At~:~ic Energy CC~:1~ssIo~
\'/oshingto;: ;:5, D. C.
A dZ'ar-c 0:- -i:he- P:~C).:"'05S)d Ct:(:::gc ::0. ~I to t!~-2 Tc::h:!ic&l S)ec:'ficatioris of Lic0rJSC CS::-l :s enclo~J::;d fo~: YJu:- :-rvi0';.' 2::'1:.1 C(i;-i:~~;:::;~:':::. T~~ srccifj.c~tj.0n 'IZC1:~2 IntoY;(:C0 ~~r V0J.o:i.ty" i~ bcir:0 J~'*;0]C.-~:! a~~ ~as riot bCC'1) inclll:::*:::1 hO}'0. A b:'~,~f SL; .. :.~:~I::*y of tht."\ .:':*O.)O~0~: :':':';""l;;',-,:, is :r;:~u~i~:i; hO'~';')V2r, j SU'J~!2St th2t ','::..' ~!1'~0~L at you:C- (':(lrlicst con""*'::-i5.c';-~::*.:: ':\.>J cc:- ':>J: t ~ det21ilccl =cv~ 0':: o:~ thc::;c~ ;>TOP')S:":; :;,;~:.:'c:.. ~i.cc(ti*:;i"!cl' Vc~y truly you~s, j . \ . J. P. Duc~:'.. J~th, ::,,:1 ~S0:: Technical S0~~~C~: cc: \'1. r*
- u. U::00n E. D. l':o::ti1 B. G. 3echha~:~*::r D. n." Shafer
ilUDSlt Jcce~be= 20, 1967 Dr. John ;1. ~~Bride, Jirector Division of i.:aterl.als Licensing United 6tates '\tomic o:nergy CO!ll!IlissioIl iiashington, 0. C. 20545
Dear Dr. i,
~cilride~ The construction and installation of the tankage at tluclea:c- Fuel Services necessary for the storage of waste from Consolidated Edison Company' s ,~ore ,-,\ fuel is now complete. .,e hereby request that this tankage be approved and that the restriction on processing Category III fuel be removed froD Technical Specification 2.2 of Provisional License eSF-I. TIlis suumittal Drovides a description and as-built drawings of the storage facility. Information and drawings were al~o previously submitted with.
- 1. Submission lro. 1, Final Safety AnalysiS Report dated July 1, 1963
- 2. Submission lio. 2, Final Safety Analysis Report dated June 30, 1964
- 3. Submission No. 21, Final Safety ,\)1a1ysis i1e:Jort dated Gctober 26, 1964
- 4. N?S letter fror.l 'N. '"'. Rodger to ,\. 1.:. Aikens dated rebruJry 17, 1965
- 5. llFS letter from 1'1. H. Lewis to A.. E. Aikens dated
~eptember 6, 1966.
';'ie v'ill be pleased to answer any further questions and to assist in any inspection of the storage facility by Division of Compliance personnel.
Vory truly yours,
/, . . -I*i J.I: v~:t.-:':"
I
\t. H. Le\vis Vice President and iJi-iL'JL General Manager ce. ,..
,,, Runion J. E. ;:.nafer
~.
"". North
"'08-
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CO::SOLID.:..:;:u ED I SO;,; CORE A ;:U=L
'NASI:: STOP.A.G=: ?ACILITY The concentrated high level aqueous wastes, HAV:C, from the processing of the Consolidated Edison's Core A fuel will be stored in an acidic waste storage tank (8D-3 or 8D-4). The waste is transferred from the high level waste neutralization tank (7D-4) via a jacketed stainless steel line to the stainless steel storage tank where it is maintained in a non-boiling cc;;dit~on.. This stainless steel facility is located in the Waste Tank Farm area (see Drawing 40A-5-27) adjacent to the carbon steel facility (8D-l and 8D-2)
- Tankace Each tank (see Drawing 8D-8-4 for design data) has a nominal capacity of 15,000 ga110ns with a maximum utilization of 90 percent. One tank will be used for waste storage while the other identical tank will be maintained as an emergency spare. Access is provided so that waste can be transferred to the spare tank in Case of leakage. Another access port is provided for sampling the tanks contents.
Each tank has level, pressure and temperature indicators. A high level alar:;-, a:id a high temperature alarm are also provided and are connected to
- '~e 'Naste Tank Fa.:m trouble alarm which annunciates in the Control Room.
- ach ta;;k has three separate cooling coils, two vertical and one horizo:"tal, which together are designed to remove 1,350,000 BTU/hr and
- -,aintain the waste at less than 131 0 F when cooling water is supplied at BOO? (see Drawing 88-D-8). The fission product heat remaining in Con-Ed
110886
~::,::,~ ,-, ,:.:;;c:: Jarl'Ja::y 1, 1963 '::ill ::,e less t~a;-, 308,OCO 3TU/h=. 7he cooling
','late:: is nOrr:Jally supplied fro::l tt:e plant cooling "Iate:r system ~'ihich is connected to the eme:rgency powe:: system. Additional safety is p::ovided oy inte:rconnectio:1s that pe:rmit us'e of the pla:1t utility ~Iater, also connected to the emergency power system, as coolant with discha::ge to the sto::age lagoons. The cooling coils a::e always pressurized by either the cooli:1g water or by utility air. A radiation detector in the cooling water retu::n line and an air flow indicator in the utility air supply line monitor cooling coil integrity. Both instruments are connected to alarms.
The waste storage tanks sit on a stainless steel pan (see Drawing 8A-M-2) which is 18 inches high. Tank leakage would be collected in the pan which is sloped to a sump. The pan sump has a level indicato::, a high level alarm and a steam jet for transferring collected solution to either 80-3 or 80-4. The pan sump can be sampled through an access port. Vault The tanks and pan sit in a reinforced concrete vault (see Drawing 8A-Q-9) which is vented to the atmosphere. A minimum of 6 feet of earth is provided above the vault for shielding. Off-Gas System Any acidic vapors from the 'liaste sto:rage tanks are passed through Chemical scrubbe:r (8e-l), knock-out drum (8D-6), high efficiency filter (3T-1 or 8T-IA) prior to discharge from the plant stack. The off-gas system for Con-Ed waste sto:rage has been designed for 20 cfm so that
*
- 1108lf7
",;,'_' ... ::L.i:~ion of l.:tility air 'J:ill p::--2clt.:de the build-lJp 0: hyd:-oge:. to ex~los~ve concentrat~ons. The piping a~d instru~entation of the acidic
':laste system is sho'.m by D=a'.'Iing S~-A-4.
*
- 11088&
J-""'; """",-, _co,,_ .. Xo. 82-;"-4 2ev. 5 ?iping ana :nstru~entat~on Diag~a~ 33-i:J-4 Rev. 4 83-J-8 Rev. ~ Cooling Coil ....,e .. 2.1~S 8P'-,',;-2 Kev. 2 Vault Plan a::::i Details, il,etal Liner and Inserts SJ..-Q-9 Rev. 7 Vault Plan, Sections and Details BA-L-13 Rev. ') oJ Piping Sections and Details SA-L-12 2ev. 4 Piping Plan and Details 8A-L-IO ~ev. 6 Pipir.g Arrangement in \'laste Tank :-arm Shelter S,C,-J-2 Rev. 3 Instrument Location Plan 40A-S-27 Rev. 3 Paving, Grading and Underground Lines for ;'Iaste Tankage Area
111321
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r.lr. R. D. Chitl:o()(!, Chi('f IrrJu; ~d. cd Fue 1 s :)ranch Divi~,ion of ~.i:J"l('lj,l" J.iconsirl0 Unil0d StJl"~; ALolnic f:ncl'CJ), CQ:IUlsc,;on
. Vi::lsliin']ton , D. C. 20:J11~
DCJl' /.',1'. Cil l blOod:
\'Ie ar0 herC'CJY submi Lti ns Jns\':(';-" to ycc:r quest ions conccrni.ng the sti:Jin]rss CJL('cl \r'JQ::t(1 sLorasr t<Jn::'~, to b,~ u~;cd for th0 stor~<J~~ or v:JsL(: from Con~;oliddlcu Edison Com,'.Jny's Co?"e /1, fuel. TL*:- first series of answers a1'(:'
tho s.-me it:' th()s,~'rovjd,'u verl) . llly in i,:arch 1?68. The sccond se::ie5 of ilns\,!C'[s lc"ponci to' your letter to Vi. G. U~'bon on '\"Jri 1 ??, 1968. 1'01' clad ty, the questions arc ::ostai:ed befo::c* 'the Jns':I01'S. A cory of thr, results of tile aCccf,LJnco Jnu chock out tests mJdc on tho sto:Joe tJnks is also attached. I tlll~*.t that thi" infonllli:ion i.lncl t.hi.lt submittr.'*:i \~ith our letter of DeccmL)c:r 20, 1961, is surrlcie(lt. VIC' ill'E*i,), lOCjU,:'st tk,t lJSe or this tiln~:J0e 00 il;?oro'lC'c1 ilncl lhJ t t:-,,: restriction 011 ;J)'OC':'c""inc) CillC'OOTY III fuel be removed [1'o:n Tcchnic<il S::E*cifi-Ci.!llO" 2./ of Provi:;ionol. LicC'r1s'c CSF-I. Very trUly yours,
,tl
. /!)
( / ,I f ~., ,~..... >> J. P. DlJc\-:l'.'orth, /';!)l1ilger Technical Services JPD: Jh Att<Jci::r:ents CC: F.. D. north D. II. Sh.:tfcr
111322 STO~J:.G::* l/,.~::~,c; r~)-3 ':. ;:J *~3D-*.1
]. Q. Vault le,1k,1'Je--,'::h:li. se:~il i~IJ r:~('~!\I=,J h,lS been used to pre'lent inlC:\!;<>0O::
of ground wilte:::-? A. The botLom sln1J hJS iln cig::t mil PVC membrane-. The :our sid<:5 and top sl,il) arc cov':[rd \'iit!l ~I ,:::,t.erp:oof membranc of 3 fily, l::{; [dt., hot.-nJopq('d aSphiil'c ,\S1:':,-O,;1;9 Type- i3 felt acco!'ding t.o AS1.',:-J-276. Also, the fou!' sid,'c, "ric!' tor) slab ha'.'c a -}" t.hick insulating fibe:-- bOilrcl \'Ihich, V:ilS hot-,ilop;Jccl I'lith ilsr':vllt to protcct t.he fclt during backfillino;; ancl comoacLion of silty till~
' \ \
- 2. Q. VI:)s there a ,. flooclinn t(!~t?
A. Yes, althouQh tho consLruction specifications a!lcl clra',:ings dicl not cilll for SUCll a test.
- 3. Q. Is surface: C):-ad~d a':;*jY f::om tank for dTa inJC)e?
A. Yes, the surface ;:>:::-0rilriltioil is gradE:d to slope a',:ay prin.ilrUy fro:;] the Con Ed building and t.he ground contours a::e blcnd(:d to p:'cvenl impounding water over the vault.
- 4. Q. Will the, s('concl tank fl.),]t if the full tank ;-uptures?
A. No, neither tdnk will float if either tank ruptures. This can be deter-mined [rolll til':: construction o1'3'::ing5. On drawing SA-Q-9 <:I d,"t.ai1 of the feet are shown; th%0 arc six e~:bcddecl eight inch stainlc-:s ~te01 oipes (1 '-6") one foot six inches long with <:Inchors for hold do*,:ns. Furthe;-, the volu~e of one tank will not fill the vault suf!iciently to float the other.
- 5. Q. Is the tank held down as well as up?
A. Yes, the design and const~uction w~s such as to hold the tanks down ancl up. The tanks arc th~ce feet onc and a half inchcs off the stain-less steel floor and bolted down to e:;]beddEd base plates.
- 6. Q. Is the securing mechanism cor::osion resistant?
A. Yes, th~ mat,:":-iClls a:-e sL~inl.;:,s st~01 cith~*:- 3*J4 or 3'J~L dt;~~:'1din<J on the 3;:>olic~tio;: and ha\/l) b~':':1 inc;:311S'd ~~:- tan:: d:-a','ni19s.
- :? - 111323
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i:~ the ;H (1 t ., eLi 0 :", l: i.. i 1(' 5 .... ':.:::. ~,:,,: ,:"':-- ~ r :- 2. ~ 2.~ .j :" f A. 1h l} control ()uildlr.*j i* ..>:c,-,:. :~'-:J~*::i c..'j' ~ ~..'a:l :in 't1j:"":' h*:'Jt:..":- c:.:lJ ('l('cl~-lcJl ~lUi:iJ l.)!*, hC'~~ Cr];-j ;.:c* ~:.,.:.j t'~:,::J:-~~;-il! fo:- ~;dC;:;:1 ::' st~cJ;:)
~ystem is jno;}:':J'li'.'C:. l'~jC I.::iin h*:.:: (i.::, C':"~:lir,';: ::0:-:-: tL~ Ut.ili ... y ~~oo:'iI is buriod riC> Jess than fi',,'(,' f(:c~ u:*jci+::':*']!*~'*_i:1:i.
A. TIle corrosion allowJnc~ O~'C~ fifty years ;5 62.~ m!ls. Acco:din9 to dcsian criteria, the tan~~s a:-C thic~ eno'J'Jil.
- 9. Q. lIJVC £111 corlst.l'llcLlon mc'Lhods J;IJ (J.:.'L~ils 0,='(111 ChCC~0ci for st.:-c-;:.
COITosir:;? A. Yes, prior t 0 cO~lstruct.io;!, ti,e cJ,:lails of stress corrosion hod oee:1 carefully CV21UJtcd.
- 10. Q. VliE, it. esLJblislted that the stJinles5 sted material '/:35 tested by Straus or Hue, t'cst to ve;:ify against car;)on contcnt "nd precipitation?
A. Yes, the Iluey LesL or clectrol/Lic oxalic acid to,t V:JS rcqLlircd as called for on speCification C-2, Paragraph 3.2 .
- 11. Q. Vbs stoc:< rnaterial chcc~,"d for freedom of defects?
A. Yes, tho standard quality control rcquirc~ents of mJnufacturers called for such c!tcc;;s. The only iI'ue ~e.3ns \'Iould be by Ui. tra-Sonic Test and this would bc prohibited in cost to go over all material inch by inch.
- 12. Q. l/JcJ 5 it X-Rayed?
A. No, tho matc,ial v:a s na: ..y -~,ayea ei:c~*:>t for wcldm0ni..s.
- 13. Q. \'1<.1 5 it UI tra-Sonic tested?
A. No, unless material m.3nufacturcr quality cont;:oI required this, our requirements did not call for such a test.
- 14. Q. ~!~S t~l~ pipil19 and bends bQ0n t8St0d, particula:ly at th~ botto~ ~ortion of the coil?
A. Yes, iiIl piping and b'C'nds have bCC'fl 5ubjcct.::*d to the test !,,(Iqui!"'::':::':':1ts as outlln0ci orl sp~cifications or d~a~~ing~, PJrt~clI12~ly sp0cificati~~ C-2.
A. Y(,'j, by ViSll':-ll inst-'(~<L:(J:'~ a:;t:l bj' ;;.::v>.'j SI..1' ._::,~,j *. !", '0:1:"_':. L,:' ~.,'~ required t(*:.,t as cal1r.:,.:..1 fo! tJc:" s::>,:,cific.ji..ic:. ':;:13-C-~.
- 16. Q. What \':cldin0 Code I'las usr:d?
A. All weJciin'J ;):'ocedu;:-')~ to'y:U:." ;':ith ;.;:-oc* 0:.::*-:, qUJU fication :o.*c'.J:ds 0 est<lblishing tint th',' ;.:>roc'Cd:.;~-:- is fully qUJ::;i.cd ',':":e <;ccorJ:n:.; to ASME Section IX. All woldc='s we:e q~Jliried ~n accordance with ~S~E Section IX.
- 17. Q. Vlhat \'IJS the qualification of th*) ',:'2Jdc:-s?
A. The welders \"JCl'C certified fO.r this v:J!,~ and only pCl'forr:"jt;.:! ~.:,):-~: '::Ithin their certificaLion. Welder qualifications were required and rcvi~wed per spc~ci fic,1 L;'orls *
. 18. Q. ~hat welding methods wel'c uGed--tungst~n, inert gas?
A. The weldinri methods used were tungsten inert gas process and ~etJ11ic arc process. ,,
- 19. Q. Vlere any srr-cial treatments applied to minir.lize car-bid!:' precipitation at the vlelcl?
A. Yes, carbide precipitation at tho weld was n:inimizecl by purging with inert gas such as argon or helium and by using stainless sleel wi~c brushes. Grinding ';Iheels '/lorc only used on stairtJc~s st('d*
- 20. Q. Were the welds stressed relieved?
A. No, special stress relief procedu~cs were used.
- 21. Q. What tempcrature was used?
A. See Item 20. 22.Q. If it was annealed, was it quenched? A. See Item 20.
- 23. Q. What was the up:')er temp!:'raturc of annealing?
A. Sec It enl 20. D. Test
- 24. Q. What were radiog:'a:)hy acc<:.'pt~nc<:.' stanc!.:!rc!s?
A. All bult welds on all sea~s ~nd connections W0:-~ IOO~ radiogra~~cj ~n accol'danc~ \'/ith the r~qui:-e:;;*:nts of Pa:-2.s:ra;::1 :.J/tfSl AS':.?, S0ction '/iI!. KodJk tYr)': "A/," film* o~ il,:provs*d equal ';:~s l::-:,J.
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lCI:..:l Jnci fjrl,.:l p'Jss('~? A. Yf.I';j) J11 \':01ds tl:;lt Y.-;.~-J,/,:j ~*.C; coy.:' Cli[*~ ..:r:.'(l botll ~ooL and final pa~~0s.
- 26. Q. Do you hJVO In acc~ss ~ort for coupon test!rlg?
A. Yes, bJsic dc~i9!l provlck*s f01' "lhi~, and is so cons'!..ruct.oc.
- 27. Q. Do \','e hilvc s<J~nplc:; of tho meUds used fo!' coui)ons t0sting?
- >8. Q. Do \"1(
- ho'/e fil.;thoos of pedodicilily testing the spa!'e tank (a ft",r 10 y'ars)7 A. Yes, it is possible to qp this and also to incorpo!'atc the cooling coils in the test.
I' . QLe.L\!...~.UJ.:l.~ t 29. Q. \'lhCll tests \'Iill. '.'I'::; run on su,np tr<lnslcr jet? Ar~ there vJlves? A. Vhl'Cl' has been induc~'d i:1tO the sump and then jette:d out to the g:-ounci to sinllililte tI,e actual fllnction. As sho~n on the: design and consLruction prints, the~e is a thr~ewJy valve.
- 30. Q. Are transf'rs feasible without ,xpoSUI',7 Is iJ blank n('ccssa:y?
A. Transfers can be done readily as th~ v'alving a:rang':m':::ll is shield*::d and a villve extension handle Jllo':lS the Op0::'Jtion to be se:;-;,i-re:not,.:. A blank is not ne:cessary.$he thn?eway villve is us,cd.
- 31. Q. Has the Off-Gas Systems test to determine the efficiency of scrubbers been made?
A. There does not appear to be a me~hod of fully t'sting the scrubbers without filling the tilnk '!lith uOlling tli:03' A standard design has been used and the quoted efficIency for these units is better than 99%. , A. A 'lillve exists all both si::es 0; the jet so th2'_ it can 00 u:lplug::;"j with prcssu,:- ..? sr,ould a plug o:cur. The j~t ca:-l:-lol b~* !'S'?lac'=.'d b\..;~ i: '/~ is feasible to install.a n~~ jet syst£~.
- s-111~'26 Q. Can the vont lin~- be shut 0 , ,
A. Tho J;)provcd dcsis:n of these t::n;~s :'j.::.=, c CO:,l!,-IO;1 v*~r,t. sy;;,,:(*~ ,..::t~:out v~lvr:'..~ so ihJL the vent. sys-LC'~I O~t crl':' t~l;'I:< C:li-,:l:d. b(, s.hu~ 0:[. The intent of this syst.C!l1 is to ~._.,.:>p a n('0',.-:tjv.'J i"):'[I:;::'U:-0 in bot~: t.anks ot all ililies and to rnai.ntain a co,lsL;:~!~ ai:- punJo on the ~10nite:'inJ insL!'llnlcnL linC'. !ly routine*]y r:li)n:~o:in~! thC' levd inst:-:,:::lcnLs, ')"y buildup in th(- lanl; can b'_' d(L,*:Lc'c!. The 'purge gJj on th,: ins:;u[,IC'nt 1 incs coulc! iJo~,slbly be changf:,j to ::2 but we kilO':: of no r:'Json to justify tho:: CXi',)rlse of chansir.J f:'cI tho st,lnciJ"d US0 of d:-i'Cd inst:-u-mcnt. C'ljr to rl;? The scaled VJ1Jlt. contllining tho:: i-3n:':s is consirJr:!"'c'd anoLher rrolo'cLivo method for exlendins th,:; life of the stainJ'c~s steel tanks. , 36. Q. Is it poss.ibl'6 for ra in water to c:dd carbonic acid vate the stainless steel over a long period? fl. Ii is hig:'ly im;?l'obable thJ1.. !'ain \'jilter ctJulo ,:,nte:' ttl'" t~nks or the vault. The tilnks arc' sCJleci inside' a viiult 'lihich ','Ioulci ('1 ir;:ir.,lV* ra i;, Vlater from ent*:ring the tanks. Tho vault is a pou:';:j ca[lc[*'t*, ho/. os
,/.':\j C:l could l!ni'JS~ i-described in Ansvle!'s 1 and 3. The outsid,; of th0 vault '::ilS given .:.
wJtcrproof troatment before being covered witll mo!:' than six fent of silty till. fls described in Ans','lc--: 3, the surface \'1as g!'3ci*'d to furlil"r reduce the probability of rain \'1ate!' from ente!'ing the vault. From this, it is believed that the possibility of rain 'Nate!' adding c.:;rbonic acid to the outside or insidc of the tank, \'Ihich wculd un:)a~,siv"te the stainless steel ovcr a Ions period of time, is ext!'cmely remote.
- 37. Q. Mlat ore tl1c criteria fo~ wast0 stored i~ one tarlk to be t=ansr0~~ed to the 5,Oill'e? ror exarn~10: if all the cooling coils failed.
A. If all the cool inC] coil 5 in th*:: filled tank fai10d and th*: heat s:en,:,:'- atins rate \'.'a5 sufficient to CJus'~ the liquid to exce0d the r.1a x irl'J;:1 operating lr;mperatu!'c of 140 0 f, a standby sta;r.10~s steel jet wculd be inst,l11l.'d in the sample op(:nins and tn':; SOI!lllo~1 rc,;lOt(:ly jett,;d from one tilnk to the oth'r tan:~ .
- A. P. d0t0!Tlin,)ti0n '::,')uld b~ :7l~d*~ ':Jf th') slt l
.. ; ] L!~:I ,In:! Ui'S' nr:ct:'ss.:):"l .'):~:-=.:
gcncy r!J:J:l..!:-(*~ ",:,:,IJld b*') ted:*:?::. The S,J:.:;L'! C:~,.":iitL*;*:* ';::!ul--J ;)~:,;c'/r:' :!l! corl"Qctlv0 actions.
- (, "
111327 A. Th,) Ji1*':I.J,..**..:d ..JLL;Ci::; ~,:~, ;2.:: U*~*i.:..j)~j C;""I th'~ :-~t,: of lcr.!;. ":':lJ !.:J(' ~c~lvj~,/ conlenL of ttH:.' s ...dut.:o;., ;)t.:: .::11 crfJ:'ls '::0:..11.:5 Oj~ tcJ::~';1 to stoj) thc>> 1CJk and/o:- !'t:!,~ir 1.rlC \'J ..d:'. A. The effecl of lh0 level in the su~p On lhe aclion ta~cn 1n deciding vihelher t.o transier f::-o-:~ on<; -;',,;1;: to anot.lte:- ',-Jill d0:;c,:;d on t.ile source> of le;)k, viluH or tu:1k. ='_l1C':;':'ilCY 2ction viould 00 st,,:-t*:>ci if til" level exceceJc.d 6 inches ilnd ti,e :-"Lc of Duildu;J \,;<1" con~id<:'r('d '-,xc._'s-;:v':'.
- 41. Q. \',hell would you build a :1e;: v,J'Jlt?
A. A nc';: v~~l1. ~."0uld ,-'rOiJ:i!.:*.ly OC st<J!-t.'0d after a dcte!'minwtion 'Ita:. r:lij:iC of the situ,JLion ilc,d all :-DI'cdial \':or:": atter.:ptcd ~':JS u:1success;"ul.
- 42. Q. V.~l;Jt ilrc crii.e:'ia for f':c;xlI'.:,dness for us':, of the spare lank? fio':: lor.g would it lake to activate the spare tank?
~
A. Il is inlended to mJirllain the spare tank in a const.ant. standby con-dition, and it is conse:'vatively estimated that approved transfe,-s could be initialed in less than 8 hotcrs.
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AnCA CODt. 7!G TLL~~ .. tCIfL O,,"~-::'Z3~ October ]7, 1968 Dr. John A. ~cBridG, Director Di visicn of r.~Oltcl'i,ll. s Li ccn~ i:r:J U.S. Aterlic Enc-rgy Commissi.on Viashir.gton, D. C. 20545
Dear Dr. l.icBridc:
PursuOlnt to Paragraph 50.59 of Title 10 of the Code of Federi?l Regulations, Nuclear Fuel Services her0by requests Change No. 8 to the Technical Specifications of Provisional Operating License CSF-l. The proposed Technical SpecificaU,orls constituUng chango No.8 are attached. To supplement discussions betv:,~cn NFS and Division of
~aterial Licensing personnel, nuclear criticality reviews concerning
- 1) dissolution end feed adjustment of Core A from Consolidated Edison Company's IndIan Point Reactor and 2) recycle of off-specification r high enriched uranium product are also enclosed.
Nucl eelr Fuel Services do0S not b£>lieve that ther,e changes present significant hazard consid£>rations not d£>scribed or implicit in the Final S<Jfc-ty Analysis submitted under Docket 50-201; therefore, authori-zation of the changes is requested. To permit Hi:S to meet its processing comrnitr,lents, yOUl' earliest possible approval is desired. Very truly ycurs,
- I
/, 1 .~.L~,.A..v-\~-
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Vi. G. Urbon Vice President & General /,:anagcr ViGU:JRC:s1k Enclosures Specifications: 3.0, 4.4, 4.5, 4.6, 4.8, 5.3, 6.9 2.0, 4.15, 6.3, 5.4, 6.5, 6.8 and 6.10 Nucl ear CriticaJ.i ty Revle\'/5 cc: E. D. North D. H. Sh"fer B. G. Bechhoefer
~ - ---- ~~ .----~ ---
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111117
- 7he follo:dnS ter:ns are defir.d only for th:;? :;Jurposc of clearly indicatir.c the intent of the various provisions (,;i"len ....ithin these Tecnnical Specificaticns.
Blanking eff r The insertion of ~ removable positive barrier in a line. Boral A sand,dc:.-type plate .....ith e. core of boron carbide (B4C) crystals suspended in cast. al~in~, clad on both sides with aluminum. Concentration Control A technique used to ensure nuclear safety through control of the concentration of fissionable isotopes in ,rocess and product solutiona. Fixed Poison Tanks Atank (or vessel) containing fixed neutron absorbers, i.e., norosilicat~ - glass Raschig rings or boron-stainless steel Raschig rings. Flooding velocfty That velocity of one or both phases in a column at which the col~~ is no longer capable of pro-viding de entrainment of phases in the effluent streams. f Geometrically Favorable A vessel *which is safe by geometry for all credible concentrations of fissiona.ble material. Gross count ~otal alpha, beta and gamma radioactivity not classified according to nuclide, Locking Out A control switch or valve handle which is fixed in either the open or closed position by one or more padlocks. The lock(s) may be removed only by designated supervisors. Poison A material having a high neutron capture cross section (e.g. boron, cadmium). (Chango l\' o. e)
~ ~ ~-:-.-: .. --"'\~-: ..-.. -~,...J4_-~ ____ . -.
CHANGE NO. a UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. Z0545 111155 Docket No. 50-201 Change No. ~ License No. CSF-l Nuclear Fuel Services, Inc. Suite 906 Wheaton Plaza Building Wheaton, Maryland 20902 Attention: Dr. E. D. North. Director Technical Administration AND New York State Atomic and Space Development Authority 230 Park Avenue New York, New York 10017 Attention: Mr. Oliver Townsend Chairman Gentlemen: This refers to: (1) Nuclear Fuel Services' letter dated December 20, 1967, supplemented September 27, 1968, which requested approval to use newly installed waste tanks and authorization to process Category III fuel. (2) Nuclear Fuel Services' submissions dated May 10, 1965, May 24, 1965, July 2, 1965, January 3, 1968, and October 17, 1968, supporting proposed changes in Technical Specifications 4.4, 4.5, and 6.10 that relate to the use of neutron absorbers in fuel dissolution and feed adjustment vessels; RECEIVED NOV 1 S \968 VoJ. G. URSON
111156 Nuclear Fuel Services, Inc. NOV 3 1968 AND New York State Atomic and Space Development Authority (3) The Commission's TWX dated September 13, 1968, as modified by TWX dated September 17, 1968, authorizing resumption of processing operations under intertm Technical Specifications 4.14.1, 4.14.2, 4.14.3, 6.10.1, 6.10.2, 6.10.3, and 6.10.4, which is desig-nated as Change No. 7 to Provisional License CSF-l. These specified Itmits to the operation of exhaust ventilation system filters and surveillance of their operation. Information submitted by NFS' letter dated October 3, 1968, provided bases for replacing these intertm Technical Specifications with a new 4.14 and the revisions to Technical Specifications 5.5 and 6.5 included in NFS' submission dated October 17, 1968; (4) . Nuclear Fuel Services' request dated October 17. 1968, supplemented by TWX received October 26, 1968, for Change No. 8 to Provisional License CSF-l involving Technical Specifications 2.0, 3.0, 4.4, 4.5, 4.8, 4.14, 4.15, 5.3, 5.4, 6.3, 6.5, 6.8, 6.9, and 6.10 in connection with the foregoing ~nd authorization of facility modifications concerned with load-out, storage, and return for rework of highly enriched uranium product such as will be obtai~ed from processing Category 3 fuel. These revisions have been designated as Proposed Change No.8, and have been considered pursuant to the provisions of Section 50.59 of 10 CFR 50. Acid Waste Tanks We llave reviewed the installation of newly installed waste storage tanks aD-3 and aD-4, and have determined that with the i~corporation in Provisional License CSF-l of the Technical Specifications 5.4.1, 5.4.2, 5.4.3, 6.3.1, and 6.9.1 authorized herew:~h, the use of this installation to store wastes from Category 3 fuel does not present significant hazards considerations not described or impliCit in the NFS "Final Safety AnalysiS Report" and that there is reasonable assurance that the health and safety of the public will not be endangered by this use. Accordingly, the pro-cessing of Category 3 fuel is authorized. Specifications 2.1 and 2.2 of Provisional License CSF-l are replaced by new Technical Specifications 3.1.1, 3.1.2, and 3.1.3.
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111150
'Nuclear Fuel Services, Inc. NOV 8 196' AND New York State Atomic and Space Development Authority Since the product of the impending campaign is limited to 225 grams per liter concentration, we have for expedience revised Technical Specifications 4.8.1.3 and 4.8.1.4, which limit the concentrations in the fixed neutron absorber storage tanks, in the birdcages, and in the storage arrays, to the concentration limits authorized in the shipping approval you referenced.
This is without prejudice to further revision when supported by an adequate nuclear safety evaluation. We called to your attention the possibility that requirements for safe-guarding special nuclear material product, which are 'being developed, may be difficult to meet in the Fuel Receiving and Storage Area. Accord-inglY,we have revised the technical specification authorizing birdcage storage in that area to indicate the interim character of this autho-rization. We have determined that the changes to the facility pertaining to product load-out, storage, and rework of enriched uranium do not present significant hazards considerations not described or implicit in the NFS "Final Safety Analysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered. Operation of the facility with the changes described above is hereby authorized with the revision of Technical Specification 4.8.1 of Provisional License CSF-l authorized herewith. A copy of the Safety Evaluation by the Division of Materials Licensing related to the foregoing provisions of Proposed Change No. 8 to Technical Specifications is enclosed. Editorial Revisions The following revisions in arrangement and style of some technical specifications are included in Change No.8. These do not involve significant safety considerations. (1) The sequence of the "Authorized Materials" and "Definitions" specifications are reversed, to locate the definitions prio~ to the matters they define in the other technical spe(;ilications. The "Authorized Materials" specification has been changed to a standard format, eliminating fuel description details irrelevant to safety.
111159
.' Nuclear Fuel Services, Inc. NOV C 1968 AND New York St.Jte Atomic and Space Development Authority (2) The specification governing process evaporator steam pressure has been reclassified from Surveillance Requirements (6.9.1) to Safety Limits (4.15.1).
(3) The Specification 6.8.1 "Blanking-off and Locking-out" has been reworded to more accurately define the conditions subject to inspection. Pursuant to Section 50.59 of 10 CFR Part 50, the described changes to Technical Specifications of Provisional Operating License CSF-l, Numbers 2.0, 3.1, 3.2, 3.3, 4.4, 4.5, 4.8, 4.14, 4.15, 5.3, 5.4, 6.3, 6.5, 6.8, 6.9, and 6.10 (as set forth on enclosed pages 3, 4, 5, 6, 7, 8, 20, 21, 22, 23, 24, 25, 30, 31, 32, 42a, 42b, 52, 53, 54, 55, 60, 63, 63a, 66, 67, 68, 68a, and 68b) are authorized,and all technical specifi-cations so designated previously are rescinded. FOR TIlE ATCMIC ENERGY CCMMISSION Orir,il1o! Si~ned by J. A. Mc8ride J. A. McBride, Director Division of Materials Licensing
Enclosures:
- 1. Change 8 Revision, pages 3, 4, 5, 6, 7, 8, 20, 21, 22, 23, 24, 25, 30, 31, 32, 42a, 42b, 52, 53, 54, 55, 60, 63, 63a, 66, 67, 68, 68a, and 68b
- 2. Safety Evaluation cc w/encls:
Mr. B. G. Bechhoefer Mr. O. M. Ruebhausen Mr. H. G. Urbon
111118 Su;;:p A s;:-,a11 pit .:.t the 10" point in the floor of pro:::cssinc ar<:?as *..;hich serves as a collection drain for liquids and equipped with means for detection and removal of acc~~u1ated liquids. U-235 equivalent concentration (gil) = 1.66 x Pu concentration (gil) + 1.66 x U-233 concentration (g!l) + U-235 concentration (ell). This formtuntion should not be applied to solution systems that depend on geometry control. The conversion analyses are based upon calculations reported in mil'lL- 3 and ORNL-Tl"-686. Ready Condi tion __ ~_.____ _ A temporary condition of operation using prescribed alternntivc instrUmenta.tion and controls or additional administrative safe-guards "hile immediate corrective action is being taken in accordance with the require-ments of the license.
/
I (Change No. e)
SAFETY EVALUA7IO~~ BY THE DIVISION OF !JllTERIAL2 LICE':STfrG roCKET no. 50-201 NUCLE!~R FUEL SERVTCES, nrc. NEW' YORK S'l:A~ A'!Ol,!!C AND SPACE DEVELOP!,!ErIT AUTHORITY PROPOSED CF.AHGE NO. 8 'ID TECHNICAL SPECIFICATIONS INTRODUCTION Nuclear FUel Services (NFS) has req~ested changes in the technical specification~ of License No. CSF-l to authorize (1) the use of stainless steel storage tanks for high ,level liquid radioactive waste, (2) the use of fixed and soluble neu~ror. a"o50rbers in the dissolution and feed adjust.::lent vessels, (3) operation with imprOVements in the ventilation system, including additional ad::linistrative controls, and (4) certain modifications for the load out, storage, and rel!orking of highly er,riched uranium. 'Ihcse are discussed in detail below and the applicable change requests are identified in each sectior.. ACID WASTE SlOR.4GE TANKS Propo~ed Chs.nQ:e By e request dated Dece~~er 20, 1967, as supplemented on September 27, 1968, NFS requested approval of the design, construction, and use of stainless steel waste storage tanks, identified as 8D-3 and 8D-4, for ~he storage of acidic high level radioactive liq'.lid wastes from the proceSSing of thoria-urania fuel from the Consolidated EJison Company's Indian Point I Core A, identified in technical specifica~ions to the license as Category III. Discussion Fbr initial operation of the plant carbon steel tanks-were constructed to accommodate neutralized waste. The construction testing and emergency procedures for these tanks were set forth in the application and in our safety evaluation dated August 20, 1965, particularly in sections 4.2, 5.4.6, 7.2. As noted therein, eacn tank is seated in a metal saucer within a concrete vault which would contain any leay~ge from the tank itself. Monitors are provided to detect leakage. In the event of leakage, the contents of the leaking tank will be trans-ferred to a spare ta~~ which is required for that purpose.
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To reduce faulting difficulties experienced with DiEsolver Off-Gas (DOG) ar.d Vessel Off-Gas (\~G) syste~ filters, F.LPA filter units manufa=~ured with metal frames will be used to guard a£ains~ m~isture deterioration, and an additi~nal backup HEPA filter (with spare) has beer. installed downstream from the exhausters in these systems, in the t~Jnk leaking to the stack. ~e operating pressure drop across the final HEPA filter in each of the ventilatior. exhaust system is ~o be li~ited to 85 percent of the greatest pressure drop at whic each unit has been ~ested. Redundancy of filter pressure drop measurement in the Building EXhaust system will be achieved by adding instrumentation across the HE?A filter bank to the present instrumentation across the prefilter-HE?A train. A high differential pressure alarm setting at 75 percent of HEPA filter tested pressure drop is required. A low differential alarm setting must be maintained not more than 3 inches water gage below the mean operating pressure drop across the Building Ventilation HEPA filters whenever the operating pressure drop exceeds 5 inches' water gage. No more than 10 consecutive days of operation of the plant will be permitted withou a spare Building Exhaust filter bank operable, and immediate and continued effort to repair an inoperable spare exhauster will be required. ~e operability requirements for silver nitrate reactors has been changed from 0.16 to 0.6 curie of I-l31 per fuel batch. Discussion The provision of a new backup filter installation, with the HEPA filter operatir.g pressure drop limited to 85 percent of the tested value, is ample assurance against a major release due to filter rupture in the DOG and VOG syste~~. The pressure differential is monitored across the primary filters and the backup filters separately. So although flow fluctuates markedly, abnormal performance of either filter can be detected by comparison. Simultan~ous rupture of the tandem filters separated by extensive ductwork and an exhauster, is unlikely. ~e location of the backup filter downstream from the exhaust is not conventional. But the exhausters are located in a space vented through the Building Filtered EXhaust System and the piping to the backup filters is of welded construction and makes connections via gasketed flanges to eliminate danger of leakage where the ventilation pressure is positive. Restricting final HEPA filters to operating pressure drops below 85~ of their tested value eliminates overloading them. Prototype tests on HEPA filters indicate that they can endure impulse transients 5 times the routine test pressure drop.
Upon each installation of HE?A filters, a test is ~ade with submicron particles to verify t~t the collectio:1 efficiency is gres"ter than 99.95~. While on s'tream, the pressure drop across the filters is continuously ~Dnitored. ~inor varia~ions in filter resistance are not distinguishable from the pressure drop fluctua:.ions that nor~ally result from openir~ and closing confinement doors, damper adjustments) etc. An abrupt loss of a whole unit experienced in the 30 filter bank of the Buildi:1g Exhaust System under relatively high filter resistance conditions lowered the pressure drop approxi~~:.ely 50%. Requiring the low pressure drop ala~ set point to be "'ithin at leas't 3 i!lches w.g. of the :nean operating pressure drop whenever the ~ean exceeds 5 inches w.g. should provide prompt alerting to the need for switching to the spare filter, if 6 major filter rupture should agai:1 occur in the Building Exhaust System. A ~jor rupture at lower pressure drops is considered unlikely. In addition to the redundant pressure drop instrumentation, a continuous monitor of sta~k effluent is provided, and is set to alarm with the accumulation of radioactive pa~ticulates equivalent to the stack release limit for one week. It alarmed on the occasion of the DOG filter rupture, but failed to register the building system filter rupture, which evidence indicates did not release a week's limit of radioactive particulates. The con:1ection of the monitor to the stack sampling point is via 210 feet of one-inch pIpe ~Iii.h 16 elbuw::;i.htLi.. ::;elec Ll vel,y *luhl"ulL Lhe pl::I::;l:;l:!.ge u£ ltu'ge particulates, such as could be discharged. with an abrupt filter rupture. 'There-fore, the rrDnitor cannot be relied upon as a filter fault detector of incidents releasing only large par'ticles. Nor will it detect filter leakage in exhaust streams carr/ing little radioactivity, though it will detect abnormal conce:1tra-tion of small particulates in the stack gas. We believe these provisions are adequate to warn.of any major fault in the Building Exhaust filters, which are relied upon to protect the public in the event of a. major dispersive accident within the plant. The relatively low concentration of radioactive P.8rticulates impinging on the Building Exhaust filters is not sufficient to require toeir continuous func~ioning under no~l circu~~tances, but their performance is essential to provide confine:nen of upper limit accidents which have been postulated a~ credible within the plant. !he decrease of Building EXhaust spare filter inoperable time from 60 to 10 days is in keeping with practicable plant maintenance, and the "immediate effort" revision on spare exhauster inoperabili~J is more conservative than the previous 60 day allowance.
With ,he use of a solution in the roG cher.:ical scrubber of greater efficiency than the caustic considered in our safety eValuation dated August 20, 1965, the increase of I-l31 in a fuel batch fron 0.16 to 0.6 curies before requiri~g the use of the silver ~itrate reactor in the DOG system is unlikely to result in the reduction of toe nu~ber of fuel batches which ~y be processed per year, under the prevailing I-131 emmission limit technical specification. An upper limit can be established to the radioactivity available for dispersal in the event of a fil ter r..lpt~rc. UFS favors an assu:::ption that no more than 210 of the,burden accrued on a filter would be discharged out the stack in case of filter medium rupture. Now that screens have been installed to keep filter media from enterir~ exhausters, where it could be shredded, we feel that this is a reasonable assumption. The act!vity likely to accumulate on a final HEPA filter unit is estimated by NFS not to exceed 10 curies. We agree with the method used by ID"'S in trAking this estirr.ate, and we feel that the unshielded character of the final filter installations will tmpel NFS to service filter units before they accumulate this much activity. Tb put this in perspective, the disc~.arge of particulates from the stack at the technical specification limit .!ould total about 10' curies in 3 years. Under puff 'l"el eR,~e ~ond i t,1 on~ 1 0 ~ur.ieR nllt. t.he Rtack would 'Droduce a maximum :rround level
-4 - -
concentration of ).33 x 10 curie seconds per cubic meter. This is equivalent to 148 hours, or less than one month, at the occupational exposure limit for strontiur.: 90. Applying the 2% assumed release fraction and a: 71> Sr-90 composition factor, the maxirr.um exposure at ground level would be equivalent to 1/5 hour at the occupational concentration limit. From the foregoing evaluation we conclude that the proposed changes do not present significant hazards considerations not described or implicit in the NFS "Final Safety Analysis", and that the health and safety of the public will not be endangered. URANIUM PRODUCT LOAD-OUT, S'IORAGE, AND REIURN FOR RE.llOItl( Proposed Chanlle B,y letter dated October 17, 1968, supplemented by TWX received October 26, 1968" Nuclear Fuel Services, Inc. (NFS), requested a change in Technical Specification 4.8 of Provisional Operating License CSF-1, which establishes safety limits
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~ecr~ical S~a~ifications.
~~~e insertion of a removable positive barrier in a line. *
~ral A sar.dwich-type plate ~ith a core of boron carbide (B4C) crystals suspended in cast; &luminum, clad on both sides with alumintim.
- Concentration Control A technique used to ensure nu~ear safety through control of the concentration of fissionable isotopes in process and product solutions.
Fixed*Poison Ta~s A tank (or vessel) containing fixed neutron absorbers, i.e., Dorosilicnt~ - glass Raschig rings or boron-stainless steel Raschig rings. Floodir.g velocity Tnat velocity of one or both phases in a column at which the col~~ is no lnngcr capable of ?ro-viding de entrainment of phases in the effluent strea.-ns. I Geometrically Favorable A vessel*which is safe by geometry for all I
. credible concentrations of fissionable I material.
Gross cO\i,nt ~otal alpha, beta and ga.,.;na radioactivity not classified according to nuclide, Locitir.g O\i.t A control switch or valve handle which is fixed in either the open or closed position by one or J:IOre p~dlocks, T"ne lockes) may be removed only by deSignated superyisors, Poison A material having a high neutron capture cross
. section (e.g,. boron, cadmium) *
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A shlall pit at the lo~ point in the ' floor of ~rocessing areas which serves as a collection QrQin for li~uids and equipped with me&ns for detection and removal of accumulated liquids.
~23; equivalent concentration (gil) = 1.66 x ?u concentration (gIl) + 1.66 x U-233 concentration (Sll) + ~235 concentration (s/l).
This fomulation should not be applied to solution systems that depend on geometry control. The conversion analyses are based. upon calculations reported in Bi:'ilL-3 and Om,L-T:t.-686. Beady Cor.di~i9n _________ A te~orary condition of operation using prescribe'd alternative' 'instrU.'":lentation and controls or additional adwinistrative safe-guards ,,;hile l:.:lediate correct:.ve action is being taken in accordance with the require-ments of the'license. 0' " (Change No.8)'
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- 42a - 4.14 I
4.1... :::xr..'..ueT F!!.TE~ D!tFE:tE~;rIAL ~~SSl;~ Aoplicab:'l:.rv
.This specification est3~lish~s the maximum differential pressures that may be =aintained across the absolute filters in the exhaust ventilation sys te::lS.
Obicctive To minimize the probability of failing final filters in exhaust ventilation systems. Specification 4.14.1 TF.E SUST.!,.:n:ED OPERAT!NG P:tESStlU DUFE:tE~7IAL AcaOSS A!."'i FU:AL AESOLtJ'l'i:: FILT:::3. n: Al~ OF 'l':!E :;::-::.13S7 VE::'rlLATIOi' S'!ST=.....s SP~LL NOT EXCEED 857. OF LiE GR~TEZT PaESsur.r: DIF~EaE~TIAL AT lVA!CH TF~T FILTER HAS BEEN TESTED. Bases High efficiency (absolute) filters serve as the final filters in the plAnt'A vc~tilation SyAt~~s (Dissolver Off-Gas, Vessel Off-Gas, ~~in
. Building, t;aste Tank Farm ar.d ~OG-VOG :aac!u,;p). The Hain Building, Waste Tank Fa=m and tn~ DCG-VCG Backu? absolute filters act as the final con- I tainment of radioactivity prior to discharge to the plani stack. The service of the absolute filters is limited by this Specification to minimize the probability of failing a filter. Sp~cification 4.14.1 per-tains to sustained service of tce absolute filter; it is recognized that transient flow variations may cause differential pressure excursions exceeding the 851. limit as end of service lifeapproacnes.
The specifications for all abso:ute filters used at NFS include the cocmon strength require~ent tr~t the absolute filter withstand a pressure drop of at least 10 inches W.G. ~thout tearing or d~£orming. All absolute filters used at ~7S are tested by the manufacturer to a pressure differ-ential of at least 10 inches W.C. (Change No.8)
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st** VEin-IUT!CN This specificat~on establishes the ope=ability requirements of the ventilo:~on sys:~ws. Objective To cinimi.ze esc .. ?e of airborr.e r&~ioactlve contaminants from process equipment and cells. Spec i fic.1 t:'o!: S.3.1 DISSOLVZ~ OFF-GAS SYST!M (DCG)--D~ING DISSOLUTION OR SHEAR OPERA-TIO~;S, THZ EQ!J:::P:*3~:-: ':"~T SE.U.L !Z !'.AIl'o;"T.U;:El) IN OP::?.AT:ON Il,CLUDES AS A MINmUX A C:-iE:::;::C;.!. SC~L'3~::t Ai'i:l o:~ DISSO::'VER O::"F-GAS FILTER A~"D ITS ASSOCL\':ZD ELC:*:E:-:'. IF '.mE FUEL :a.~-':Cli CO~;-rAINS IN EXCESS OF O. 6CiJRIE OF IOnn,E-131, or::::: O:?Z?1..TIKG :::Qt::P:'3~T SEA:::'!. Al.SO INCLl;:n: O:;Z OFF-GAS HEAT~:3. rOLLC~.,'ZD "EY AN OFF-GAS SI:'VZl ~i:'l'MTE AE/.CTOa. IF Tli:rS REQUIREm::-iT IS NOT :'::':T, T:~E D:SSO!,VZ~ SP,:,!.!, :5E :!:'~D!ATELY COOLED Al\"D SHEARING OFERATIONS SHALL BE !"*;:*ZD::ATE!.Y DISCO:;:'!:;~::D. S.3.2 VESSEL OP!-GAS SYST~ (VOG)--30'l':{ OFF-GAS FILTERS Al\~ ASSOCIATED
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THE FEED .\D.;:;S::*~:;!'\"1' M:D ACCC~,;A:m.:TY TA!-;':<. THE EQUlr:':E~"1' SP..\LL Bl:: OPER-ABlE TF..1Ct:G:~C~",! A CA:*:?AIGX EXCEPT O?E~o\T:i:O.;S M.W BE CO:~TINUED roa 24 HOURS IF BOTH rrL7Z:~S A'!W/OR THE:3. .~SSCC!ATED BlOt.'ERS FAIL. I S.3.3 M.~!N VENT!4~TION SYS:Z~--Eor& SYSTB1 FILTERS A~~ ASSOCLATED BLUJEAS SH.4LL 3E O?E?A~!.E AT T:~ STA~T 0:: A CA!*;PAIGN. E.,\C!{ FILTER :BANK SHALL BE
~u\INTAIKSD l" AN OPERABlE CO~~:::LON E:>CE?T FOJ. SERV!C!I\3 PERIO;)S NOT EXCEED!:o;G TS~; CC:~SECUT!VE :AYS. Sr:C~.:..D AN E~J\UST:;:R EECC~ !};OPER..\BLE, L"t'~DIATE A:m CO~"1'IN";]!N:; A::r~T:ON SF':'ll BE DIRECTED TO ITS REP!,,~C~:ENT
~dI!.E EX:::;'C:S:X:; 1-3ASt-:tES TO ~:~:NTAIN SYST~: CON'l'AI~::;'!ENT. IF BOTH }loAIN EXHAUST n:.:rz3. SYS7::;}~S S:::CC:-3 ::,O?u..-\ElE SUJJI.TANEO:JS;'Y. Il'JMEDIATE AND CO:-1'IN"ul~~;; AT'!'EN!ICN SliAL:. SE Ii:RECTED TC:.]AlU) OADER!.Y PLANT SHUTDCWI~.
THE INS~L~~NTAT!ON MONITOR!NG !Jig DI:FERENT~~L PRESSUiE ACROSS THE OPERA-TING ABSC1.~E ZO:L':ER IN T.~ l'~"!N VE~iT:!"\'!ION SYSTEM ~~ALL BE OPERABLE DURING OP~~T!ON OF THE FILTER. IF TF.!S !NS~~~~~~.T!ON SHOULD BECOY.Z INOPERABLE. on<\.,,::!O~ OF Ti.E F!L,!J;;a Y.AY cO:rr!!:ti'E FOR 10 DAYS, PROVIDED Tr*.l.T THE INS:R~~~XTATIO~ MO~!TC~IN~ TEE DIFFERE~7lAL PRESSURE ACROSS THE ABSOLUTE FILTE.' PLUS RO;;:;~m;G FILTER IS O?EMBLE. ACCEPtABLE ,. FILTER ALTERNATES 15T-49 lSPDB.-ll lSPDB.-10 15PDAH-ll 15PDAH-S lST-49A lSPDR-6 15PDR-5 lSPDAH-6 15PDAH-4 (Change No.8)
- 5. 3.4 \~:S~=: T';!';~ O:'::'-G.A.S SYSTE:*:-!F A FILLER, B!.Om::n, OR A WASTE TA.~
O~F-G,';.S CO~D:::!\S!:R F.!.:l.S. :HE HASTE T;,.K"t.: VE:,T SYSTE~ SH..;LL DE S!-1ITCHED TO Ti:~ ;;pnon:.:::::: O?:?i-.r.LE ST:..'1D:;Y EQUI?:'::;~'T A..,{D I!-C,zDIATE REPAla SHALL BE I~ST!'Z','TED TO E:~EDITE THE RETUa.~ 0] THE FAILED EQUIPMENT TO SERVICE. 5.3.5 DOG-VOG BACKUP nLTER5.....A DOG-VOe BACKUP nLTER SHALL BE OPERABLE A'r ALL '!I~S. Bases The pri~ry con:~ol of ~irborna radioac:ivity in the plant i8 provided by fou~ ven:il.. :i::':l systarr..s. This s?ccification has been designed to assure the ~vail~b~li:y of sufficie:l~ v2~:il~tion capacity to provide the p~c?er p~essu~c Qiffe~E~ti&ls bE~ean o?e~ating equip~ent and occupied are~s so that plant personn21 are p~otec:ed f=o~ airbo~e activity. and to ~~n=~in in op~=.. ti~n essan:ial ~reat~an: systems for the rer.oval of radiocctivity fro~ the ventil~:1on strea=s prior to their release to the atll:Osp:te;:e. The DOe systc~ treats gaseous effl~ents from the dissolver, the bundle
; ar and the pin shear. rne off-sas from the she&ring operations is c~.~nected to the ~OG system upstrea::l fro~ the chemical scrubber and the co~!~~4 disso~ver and shear off-ci~saeS pass through the sc:ubber, reheater.
a silver nit=~~a =e~~tor. a cooler, and a filter prior to blOWer discharge into the st~ck. Tna cheDical scr~bber reooves about 90 percent of the .I iodine 131 and, if neces~ary. the cher.ical scrubber in coobination with a silvar nitra:~ =e~ctor rc~~ves about 99.5 percent of the iodine 131. If the mi~i~u~ ope=~ble e~uip~ntr£~uirements are not r.et, the evolution of radio-
~ct::'vity is rec:;.ced by discon:i:u:;ing the shearing o?eration and by cooling the ci~~solver, ~na=eby slewing the reaction. This will reduce the fraction of the ~~nual ra1aase limit (Technical Specification 4.1.1b) expended during equipr.en: inoperab!lity.
The VOG SystE~ ?rovides e~uipr.ent for the treat~nt of the gaseous effluents fro~ radioactivity-containing process ~ssels thrcuthout the plant. !hese gases are conda~sed. scr~bbEd, heated and filtered prior"to blower discharge to the stack. If both VOG filter-blower units fail. operations may continue for & 24-hour period because confine~ent is afforded by the DOG-voe backup filter a.~d tha ~~in VGntilation Syste~. which exhausts the spaces where the vessels on the VOG syatea are located. An absolute filter and a parallel alternate are installed 1D the common Gibehirze li~c :ro~*the DOG ~~d VOG exhausters to the stack. These filters provi~e in-depth protection against relea3es from a failed filter in either the DOG or VeG syste=s. T~chnic~l Specification S.3.S requires that one of T bac!tup filters m1.!st be operable. lienee. the spare 1:IUst be maintained
- 1r. re ..diness.
(Change No.8)
- S4 -
'1':1': }!ai:. Vcr.:il.::.ticn Sy:::;:c:n centrols th~ passag:! of air through the process buildi~g :re= cle~~ ~~a~s to succcssivaly :o::e conta=dnatad areas and fi:t~rs ~xh~ust~d air prior to Qi~char~e up rhe stack. To provide for con-tinuous c~e~~ti~~ a stand by filtcr-e~£uster unit is provi~ed. If one of the ;~l:~~ b~.ks b~co4zs inoparable, plant oper.::.:ions may continue for a 10-day period 'Witl:o~t a sp;::~e ,;hile the f:!.lter bank is be1n~ returned to sa~;ic~. ~~: days ?~==ito filt~= ~~?l~ee=e~t ~ithout u?setting maintenance p=o&r~~. y~: c~:;::.ils ~ini:31 risk of b~ing vithout s?are. If an exhauster becc~s inop~rative, pl~t op~rations QSY continue while i~ed1ate and contir.uing attantic: is ~iven to repair or rcplace:ant of the exhauster; hovevc:r, the d;;'sch.:rs~ th::ough the failed exha:Jster \:iust be prevented. If beth exha~st:!::-filter syste~ are inoperative at the same time, an orde::ly plant shut~c~ ~~st be initiated. Bec~~~e of th~ ?ot~=tially l~rg:! inventory of radioactivity on the Main Ven:i:~;~o~ iil:~=s, r~d~ndant ir.s:~~:ant~tion is provided. In addition to th~ stack ::lor-ito:. ~arfo~a.. ce of the operatin~ filter is c~nitored by d~~l cif~~re:.;1al p:~ss~ra reco=ders ~nd hig~ differential pressure alarms. The ?~r.a~y s~t 0: ~~stru~nts coni tors the absolute filters vhic~ are the final b~~ric:: to r~cicactivity release and the alternate set :enitors the
~t~r &t£ge (absol~tQ plus roughin~).
The waste tank off-S~s system condenses £Dd filters gaseous effluents from the storage ta~ks. In this syste:n du&l equip=ent (i.e. condensers, filters and blo.lars) is ?rovidad. Fa~lure of &n 1nline cO::l~onent vill require a I switch to the al:ern~te st&ndby co:ponent. Since a failure would decrease the defense in depeh, high priority is given to the rep&ir of a failed co::;;pc:~nt. lWn~ co~s~q~er.ce of v~olating this specification would be to risk*the exposure of o?erat~n3 parsonnel and the general public to levels of air-borne cor.ta=ination in excess 0: the no~~lly expected acceptable levels as defined in pa:ag=~?hs 7.6 thro~6h 7.9 of the Safety Analysis. In shoving that the conseq~ences of avents discussed in paragraphs 7.30 - 7.36 r.ra a:::cep;ablE:: "rj.thin the g-.:idalines of 10 en Part 100, reliance vas. placed On the absolute filters being effective. (Change No.8)
':his ~~~~~:ic~:io~ e~t~blis~~s the mini=um p=ovisions to be maintained to .. ccc~.o~~;~ s~o~~d w~ste li~uids, in the event of failure of storage
- an~& tnzt .re in usa.
~o prevent.loss of stored r~dioactive vaste liquids to the environ:ent.
5.4.1 S:?"_~ 'l'~"XS 0:: SUI7.u'L~ co:m.cs:~~ RESIS'!'M"!' :.'.ATERIAL SHALL BE
}t.;IN'1'.;:!\~D AT i~I. 'l'I}'::S ~']IT.~ SU:'~IC!;:::'1': CX~;.C!'r'f. :':'D APPRv?~/.TE COOLING nOVIS:::C;';S, TO A:::O:*':':.JDATE RESPECTIVELY ToolE CO:~T:::XTS 0:: 'l'F.E LARGEST TANK IN W:-{!CF. ?.ADIO.'.C:'IVZ t:GU-::> 0"1 EACH CO:G;OS:VE CHAP.i.Cn::USTIC IS STO~D.
5.4.2 '.-~:EN S:'C?AG::: OF :t-\D:::O.'.CTIVE L:QUIDS HAS BEE., INITIATED I~ k\'"l SPARE T}.!-::< R:SQ"G!;.ED BY S::::C!:!C.~TION 5.4.1 OR S1:CH A T:':::{ H..u; BZEN FOL~D TO BE U1\SU:TA31E &C~ S?A~ SZ~V!CE. ACTIO~ SaUL BE INITIATED n:".EDIATELY TO RF"I..ACE THE S?.n.~ CA?;.CITY AT THE EARI.IEST PaAC1':::CAL DATE.
.t.~u .. :" ....-.--
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.......**G *"'D PO'!>
,-. y,:, .., ,..... t.GA SL7PLY) ~OR T~\37ZR~NG l'liE ~~~IOACT:VE rLU~D STORED IN A.Y TAo~K TO I THE S?>.!'"\E TA.XAGE RESZRVED TO ACCO~*:ODA'l'E IT SHALL BE MAI~TAINED AT THE PLA.~T *
. Bass.;; Althow~h waste t~.k life exyect&ncy is half a century, the time ~hen a tank will fail is net ~cc~rately known. Rather thon e~~loiting the confinecent
~rovid~d by ~h~ v~~lts in ~hich tanks a~e bu=ied du=i~g the construction of re?l~ca~~nt t~~~~. :~is specification requires the caintenance of spare tanks. to whi:h storad w&stes could be t=ansferred without delay.
The added cargin of confine:ent assu=ed by the low per=eability and high ion ax:h~ge ca?~:ity of the silty till in which the tL~k-vaults are located is sufficie:t to protect the public. So it ia aafe Dot to require replacew3nt of sp~~e t~s until th6Y DO longer serve as spares. Since e~uip=ent fo= t=~sferring the centents of the vaste storage tanks to spzre t~~~~e is not built in, a techr~cal specification requ1=es such ~q;;i}:=.ant to be &vailable at the plant, to permit taking advantage of the provision of spare tanks. (Change No.8)
Appl iCc:~bil::tv this ~~ecif~c~:io~ requires pcrio~ic verification of the operability of instr~~e~tatio~ for cetecting :he presence of liquid in the pans that contain the buried waste storage ta=ks. c*. . z. "':. ...... .: ..
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To assure that liq~id acc~~lation will be detected. St:a~iiiea:.ien. 6.3.1 T.~ :C~S::-~L;:*~~T.!.T!O~ FC~ ~~O:i!TO!'J:I~G 'r:~ ACCtt*ruLAT!C!~ OF LIQUID I~l !PaZ P.;~~! CC~:-:A~:'::i':G E:~.C:i l-roa:al:G LIc:.U:D t'~J.S'n STOaAGZ T~n< SP_;LL EE 'c;:SC"=J F03. C?::>..:..z!!.~!Y AT !z"!.ST C:TC:; PZR }:C~;T':l, A:ID U FOu~D TO BE INO?:c::t.!J)LE, I:':'~DIATZ .r.A1) CO~TIUUL'\G E~?'O:tT S2AI.L BE DIR:::CTED TO EFFECT EPA!R. Bases Pans are ~~o'.7ided in the *w~!te te::k 'Vz~lt~ t~ ecl:.a!lee det~ct!on of t.:mk le~(age. Vault inlaeka~e above the rio of the PL' would also be acc~u latc~ in t~a ?an. Level inclic~to=s with a high level ala~ are provided to e~~u~ciate any major leakage so that remedial measures may / be pro:ptly instituted. Since vault leake~e is not expected to develop at a high rate and the silt:; till in which tea vaults are Dwried is. expacted to i:".~ibit migr~tion 0: liq~ids for cany yaars, a mo~thly surveillance fre~uency of tha functioni~6 of le~~ ~ateetion ala~s will assure that. the public will be protactad frc= ~cetected tank leakage. Failure to fulfill this specification would reduce confidence in the oper~bility 0: t~e li~uid conitoring .yst~. (Change No.8)
OJ 6.~
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.:.:.~ ~~e~:::ca-::..o:1 es~abl:s:,es s\;:-veilla:1ce =e~u~:e~en"ts for the final a- .**
;- filters used in the plant.
5::;.:1. 3: :-=:5::::, P2:C~ 70 : . O:;7:~*:= SE.~V!C:, :'.~~7:~ ?A~r~C'J!..ATES 0:= A~ .~.??;':?~:.-.-:= 5:Z:: :0 =.s-:;'.3L~S~ 7:;;:r ::~:: :XS7.!.!.:.::!:> :!LT=::~S P~OVIJE A
- 0::'::::-:::,: E::;:::::::\::Y q:= AT L~;S7 C;9.95;~ :CR ?ARr!CJL.!.7~S 0.3 MICRC~S IN D!A:.~=:-=~ ~:. :"';:=~G~~ ..
FILTE?S DISSO:VEF: OFF-GAS 61-1, 6!-lA VESSE: O??-G.!.S 6T-2, 6T-2A 81-1, ST-l':"
!I.~!N E!JIL:):;~G 151-49, 151-49A DOG-VOG 3;'C:(:J? 61-3, 61-3':"
//
6.5.2 *T~= D!FF=~E:'::I;'.L ?~ESS:;~: ':'.:2055 T~E C?E?-ATI,~G ,;3S0:-U7E FI!.T~~S (C~ r.~SOL~E ?!..L:S ~O:;G.~::\:G :',:--::,~= ::~= FIr.7E?.5 A;\E ~'1!:n!~ 7:-iE SA:'~E F?A~!E) s~.~:.:.. 3E ~~=:C~'::=:i ?,y r:\:STR~:':=:::-A7IC:'~. 0.5.3 6.5.4 PRESSURE J..'F7E? ~= C?=.=.A:::*ZG :iZ:FE.~=;::!':"': ?~ES5L~E E:\:::E:S 5 I~:C:~ES ~'J.G., THIS AU?..'.~ S:=.A:!.. :,= SE: ~'::7:;::\ 3 :;:::~::s ~*i.G. OF THE ,C?E?W\7IX.:3 Dlr:E~E:-:rIAL ??ESS:';RE A:\D S::..:.:.:. BE AD.;USTED :'!E=:'LY. Eases
- 'he :.:; .... -': fi:~e:s in ~hc vantila~icn and off-gas syste=s a:a the p:irnary
* * *
- G_
p:o-:a-c't!.cr, agai~s~ the d!sc~a=;e 0: ?ar~iculate =adioactivity during no~.l c;pe;:a't!.o~s .a~d pa=ticu!arly ~::de= accicen~ conditions. These "absolute" (Change ~o. 8)
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- ~~s 3~a::=:ca~:u~ re~~:=e$ pe=ioc:c ve=i=:ca~ion 0: t~e' operability c~ ~~e ;la=~s u~~d ~o de~ec~ excessive ::acioactivity in cooling wa~er e: ~:e~= cc~ca~~a~~ =e~u=r.ed f:c~ :te cji!s 0= jackets used to control
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"0 ;:.::o,::ce .. eeee ass"~=ar:ce e: ;>::c::;p~ de~ec ... ior. o~ e:ccessi ve radioactivity .
l~~~~ co~de~sate a~ci coolin; wa~ar. 2:,c:i::'cat:.c~ BaSeS 0: _.) .. \,;t:\:*~s. 7:.~ ~:'-eSs~res cf t:.asc: ~eat -:.=ansfer f2~ids a:-e !,\lgne: t~ar. ~~ose 0: ~~e p::ccess soluticr. in o::de:: ~o wini~ize leakage of
=~ciioa:tivi~y i~ a p~ssa;e s~cu!~ davalop b~~ween a process solution .I a~d a ~cat ~~~~S:e= :l~:d. In acci:~icn, ~ac:a~io~ ~onitc=s a~e incor- ;.c*!'.7: 't~c i~~o :.ne P:'!=,:':'l~ v::.e=e 't~a s'tea:", cc!'".ce~sa 'te a~d cool ing water
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S::1ce ~~e ~aciiatio~ i~st::~=e~ts a::e read at least once pe:: shift testir:g 0: ~he ~ac~aticn ala::s cnce?e~ rno~~h is suf:icien~ to verify alar.m iunctic:lability. (Change :\0. 8)
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Page withheld as containing Export Controlled Information 130
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"I of lall.."'!cry opc~atO:::5 to 2.iY'~0::"(.~ CC:1centrc.. tic..'15 of ~'G.dio3.C t.
tive r..aterial d~ri!"(!,; the hs..v:.dl:':'1.3 of co:",.ta:--:.i::atcd itc:r..s in C tr.e latT.d.ry facility, to d0tc:o.-:ine corrpli<:::1c0 '"ith 10 C?o1
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- r*clcc.:.S:,:~ to tl':'1!".:;.:;tl"icted a:..",c*a,s frc:n the s~aci:5 to d:::tc:o::::L'1e cc:7.::>11.c....1C2 with 10 Wi'{ 28.106.
- 1. 1.'1 violi:1tic.'1 of' 10 Cfo':\ 20.201 (b)
~---
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'. ~.~ c2~i0:,";~ 0:"" pc::.:.:-;::.o2:.:.! s~.c;.~ific:.r!t, plutc:-Ut.:::'! i~0~:tic:1, in tr!G.t
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\*;~s pr.::~cr:*~ in t:-.~ Ex\;:'::.:et~e:1 S,c::::lc t'::'slc m-,d a s~ift supervisor
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17..:u--:2.St2i.;2;1'C shc~: d folJ.o:*.~-:;~ to C:,::.t*2r,j".i.."18 that tr;" safety p~oce=:~£:s arc, in fact, effectively follo:*;cd. 7na prccr*2.--:l to cO:1duct sw:'Veys ir. arcas ':t.'1eI'2 the possib:!.lity of ") ( alp:-!,,- cC.-:tc.::-.:ir:atio:' exists is r.ot c:deou?~.-,J1J that h'FS p03SC5SC~ an ins:.lf':~ie::.';:1t nur:~e:' of calibrated, [opcr~;i~l alpha ::3i.t:~cy instru;.~~ts. ~.~ (
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tio~s.of r,~icc:ctive ~~terial is not ade~uatc, in that the v~J in;; cwdi tlODS "f:'lien occur in the facility arc not evaluated.
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\'jritten prcccdur2s i:-1 e:'fcct r;:)?2.rd:i.n~ c~tr2':ce i~to 2.!10 cxit frem th*3 vz='ic~s cC:1t~..'7inatcd zc::cs are not CC;ls::"ste!1t end r:zy cat.:.Se CC:1i\lSic:1 fo;:' e:::~::'oye.:"s, specifically ir:ckc::l.ns Sccticn 1.3.3 of :\:FS' I-1ealth and S~fcty i';:ar~ual; a. r.£:r.orc..~cur:~ catE'*j ,tach 30, 1967, pr2:;arcd by the P.ea).'.:;h 2..'10. Safety Director; a \':ritte~ pro-cc-dt.:..~ c:-.t.itl0~~ "1'(,e E::'fcetiv: Use of Protective Clo:;hins;" e..r.d
'Job ~o. 52 of the Health a:"ld S~fety Tcchricia'1's Job Descriptic:;
File.
'rr.e bio:!ssay pro&r'2..--:l needs i..x':'f'icr.tic.'1 a'1d ir.::JroveiT3nts. Specifi-caEy, t~le prOCCdlU'25 :~or issu2J:cc, follo':T-~;=l, .::;;d r~tricval of l~l1cd t.:.:"i.'1alysis s2.7./1c ::,ottle:s !'r-o:r. C';;-910~'ccs &.S ~:cll as tr.c r2CO~S t!:~r0of hc.v~ not b':;'2:1 :'rfe.:~iv~ 1:'1 SO:l2 i..'"15tcr;.ces. J.:.
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-"'.,..,v...."w-O ** a,.v .... 62 sc..;,)les, c:11y 38 of v;:-:ici1 ',*;:C::::'C sllb.:;,:-.:;,u:mtly r.;tl'iev2d. A better
., ... 110fJo2 ctt()~.... ~ i:i ::cc,-:~;~~*::-*:.' i:--. c:r.;**.*~~:*L:*I': ;:-:,),::-':': ti::!..:2.y :;~_~.~lc~ ~-o2.~c*:.*:n.::; cvlC:c:1cc: 0;,'" ;:>c'.~:~i;';2.e i:/~ _:';:~l c.~;*/c:..~:::.:.I(.;~:;. H:".s sho~!2.d cC:1~)iclc:r ::":y:.:.t::tti"C,:!"""!:.: [~ fcc2.1 . z~ ;;~)}.:.:;:: P!"o;~~~ "'!::Z!:1 Sl!~pcctc~: intc:".:2.1 c!.::r;C:,;::':~LC':!~j C:-' p2!..:tc:;iL~ :J2.vc,. ccc:.:!"'rc'::'. Pcc~l sc..~')le?' 2r~ G~ CC .. :.~-~iC.'::::*2*~ 10 v2.11..:.:: L"1 cV2.1u~"~1r,:; t::e: t"'..::'C;Y.i. tt!.::*~ or a possible it~~C:1:".. -::~l ci(::J0.:;ltic.~ &"":d J-'1 c.c.*tc:-r;ird.J1':; ~*.'n(:t;~cr c:.y insolujJe r.;::;.tcr.i.ccl is i:wolved. (a) T:,0 r.~thcd used fe*:.... t:-~(i.r.~: r.2..3~l Sr:-:~2~S is ncr. cC:1sist~nt i:l that sO::.C indi viot.::J.ls u.:;c dif(c:r.l.:':-.~ tcch!1iqucs. !*'or CZN:;' Ie , it \':<!S noted *t~?:* e~c~ C-'~81 0"(""\"""'\ t;'I('"}C -,....,., ~ 0""'" n::l~""" c----.c.r (;"~-J'n "0
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/
NFS has no cst2blishG'd guj.cleJ.0.2 for positive nD.3al cc;~t2.r.:';>;o..tio:'l w;,ich '*:O'..lld cal1se tho iir;r.cdi.ate re,,:o*.;aI of a'1 c;:;ploycc f;:-o::. risk of further e~:posurc. CC:1sidcratic:'1 shculd be ci V2n to:'/O!-"'Ci tl~e estaolisi'!!-':'.:;:ni;. of S1..:ch a pol-i.cy i."1 the ~o~ sio:ific[:."'lt C3.ses of nnsal conta.O'.in2tiw, b(;ocwsc t:"ere is a cmsideroble \':aitinG p~riod b8t\,icen t!1!3 tir:.e of submissia:'l of bioassay za.:;;:'):"~s and the rcc~ipt of the results.
'The "Lapse of Radictim Ccr.trol" reports are not al~'Jay3 p~pared prolT;)'.;;ly c::.r.d in sor.';:) instances ,,:"'::'13 co:-rrplctcly c:r.itted.
1108~'-
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I I I I I I NF"S N _1 "" UCLE..A.l'\.~ _!i,(GEL~FJ>YICvS r:-" _ _ _ _ _ \...:1 ~ , ~ I' "'...
- l' 1:*;~C I~ A. :lUO~IDfr.Hy WHeATON or VI. II, vnACL z;.. co*
PLAZA (JUILDING. SUITt: 0 0 0 WHC~... *rc.)N, MAnYLAND 20,:)0;:: Anr:A door: 301.Tt:LC;""~ONc.: ~'3:,,*~ .. , .. 1 c
};r. L:!ln'Cl1ce D. !,o\.:, Di.rector Division of Compliance United States AtODic Energy Co~"ission Washington, D. C. 20545 lX!ar Hr. Low:
Pursuant to 10 CPR 2.201 and in reply to Appendix A of your letter 50-201 dated December 28, 1967, Nuclear Fuel Services, Inc. hereby submits the following statement:
,. General Comment NFS believes that except possibly in the case citation La. of the investigation of September 26-29, the activities described in Appendix A were in fact conducted in compliance with the requirements of the technical specifications and Part 20 and Part 55, Title 10, Code of Federal RegulRtions.
In the case of Ci.tati.on No. La., September 26-29, the possible nOIl-compliance arose from the faillirc of an individual to [ollO\~ v.'FS procedures. The individual is no longer eQployed by NFS. The statement that NFS believes that in connection with practically all of the citations it was in full compliance is not intelldcd to indic~te any reluctance by 1'FS to remedy or improve conditions of health and safety within the facility, Our letters of January 13th and January 15th deal with our efforts to improve such cond itions. All of the citations are considered in detail below.
*In~peetion on '\w;tlst 7 - 11, 1967
* .110870
- 1. II tIm licen::ed indi.vidu.:11!' ~'fonned l~~~2.lIncti.olls of .1 senior opel.".,tm:." NfS believes th.:lt it h.:ls been and nov, is in full COl:lpli<1nce Hith 10 erR 55.3, Opera tors Licenses. This reGulation for reactors is explained <1nd interpreted in 10 eFR 50.54 (i.) throllchCm) part of Hhich cannot be literally applied to a chemical proces5i.ng plant. The essenti.:ll feature of 10 CFR 50.54 \10en <1pplied to .:1 che;nici\1 process inc plant arc (1).
and (m) ~ri\ich in effect require that a senior operator licensed purslIant to Part 55 be present at the facility or readily available on call at all times durinr, its opcr.:1tion. While two shift supervi.sors prior to the inspection did not h.:lve senior licenses, an operator l:it1l a senior license \.,as at all times present or readily available on call:
- 2. " * * . stack snr.lplcs 17e1'e not collected and .:lnalyzec1 .:It Heekly interval", [or the pcr;ods June 6, 1967 to June 16~ 1967 and July 6, 1967 to JU.!.L}4, 1967." - Technical Specification 5.1.3 requires th:lt the stack sampler be in operation at all times and that samples be collected and analyzed at least weekly. During the t\.,o periods cited, the stack monitoring system Has continuously sampling the effluents and the samples were removed and analyzed each \o,'cek--although not Hithin seven d.:ly intervals. One sample ~laS removed after ei!;iht days and the other after 10 days. There \~as no lapse in the surveillance of radioactive releases.
To assure continued compliance with Technical Specification 5.1.3, a system has been installed ~,;hich facilitates sample removal and the schedule for sample relnoval has been changed to t.*,ice per *.,eek, to insure that samples will be taken at least once eneh seven days.
- 3. " ** to.'FS has permitted personnel to \-lork in the laundry operation without havi.n:; detailed **.. ritten procedures outlining health and safety requirements for h.:1ndlin;; contaminated iteDs."
/
Laundry opera tors \,;ere trained in *heal th and safe ty prac tices I including the use of appropriate radiation monitoring equipment as part of the initial orientation program. To supple~ent and improve this trainin[;, SOP 15-12 "Laundry Operation" was revic\:cd by the Plnnt S:lfcty Co;:-;;:ittco on Scptcnbcr 8, 1967, ano ,,:1/.; iGSUCO on October 13,1967. \{e believe that Technical Specification 7.1.4. docs not apply to plant services.
*
- 110871 4.C1. " . . ndeCjtl::tte Stll-veys },:1ve not bccn--E!:rformccl to evalu.:1te expo_suret~ of l.:1l1n(lJ-y ~(:ra tors to airborne ConCCll tr.:1 t i.ons of rndioac tivL' nn teri.:1 1 durin': h.:md 1 in': of contarni.,:1 ted i ~er::s in the ]:1llllclr;f;-;ilitv." 1110'S belicV-c~ tha-c ac]eCju.:Jte surveys arc bein!; performed to eV:1lu.:tte the exposures of laundry operators to .:tirborne radio.:tctivity. Hcthods by vlhich laundry oper.:ttors ::tre protected .:1!;::tinst exposure to excessive concen-trCltions of airborne radioactivity include:
- 1) A continuous air monitor operates in the laundry. The monitor is set to alarm at 40-MPC hours and to flash an alert well belOl.' 40-;'lrC hours.
- 2) Sortin!;, the opera t ion dt.;ring v:hich contamina tion \-.'ould most prob.:tbly bcco:::c airborne, is done under a full exhaust hood in order Lo minimize airbol:ne contamin.:ttion in the breathing zone of the oper.:ttor. For .:tddition.:tl protection, the laur:dry operator v;ears a cannister mask during "orting.
- 3) The laundry operators are included in the plant bio.:tssay program vlhich includes routine urinalysis and whole-body counting.
To assure continued protection of laundry personnel, the follo.:ing additional procedures are nm-1 in eifec t:
- 1) Air samples are being collected once per shift during sorting operations. A pe=Hent air sar:lpler Hhich should be representative of the operator's breathing zone will be installed within the next ninety days.
- 2) Laundry opcrators have been instructed to evacuate the laundry if v<::ntilation air stops. A sign ~,.ith this instruction h.:ts been posted in the laundry. An audible alann will be installed on the ventilation £1m-l in the laundry to signal loss of nOI....
4.b. " ** no evaluation has been rnade of the concentrations of radioactive rr..:lterinl released to unrestricted <lre-"lS fror:J the s tacks of the l.1undry ** II An evaluation has been t1<1~i(;-Of- the concentra tions of radioac tive material released fro:.l the laundry stacks to the restricted site &re3. Our evaluation is continuing
.and ~'e have no evidence of signific.:lnt releases of radi03c tivity.
Tnis was to be expected since:
- 1) The laundry room vcntilo.tion is discharged through o.n absolute filter.
- 2) Air dischnr[;ed f1"o::1 the laundry dryer, 1.'hilc rllnnin;:;, "hOI:ccl airborne radioactivity st.:itistically the same as back[;round *
- 3) Air discharged fro:n the lnundry I,.:shcr, while runnin[;, sho;:ed 40_.' * * * . _ . : ** :,._,::~._ '" ._..... _.- -.' .---..... -.... ~- _._.--- ..._--_ ...---_ ..._- ------_._. ----_.-_. -
n maxi.I1111~l airborne raJio;lctivitj* o[ 3 x 10- 12 ;lCi/:,:l. I-:ll"n this concentr;ltion, ,.,h),cll is ab()vc the 2 x 10-12 pCi/n1 cO:1tro1 110872 limit used nt the l{FS site, is nvcrage,d over a ,,'eel: of 1nundry opern ti.Cln, the concen t rD. t i.on i.s \*le 11 be 10;, thc 1imi t cue to the intermittent opcration of the l",uncJry and y,'D.(;hcr. Weekly sar.lpling ,,-ill be continucd, Investigation of Septer.lber 26 - 29, 1967 c>.nGl October 2 - 6, 1967 Ln. "No cynluation \,-ar: m::lde of thc .:1ir])o1"ne concentrntions of radioactive m.:1tcrials e:,istjn~ in thc Extr,1ction Sn;n;)le Ai.s1e on Jun_c 30, 1967 prior te' 01- during the entrv of a-technician ** II A IIca 1th nnd Safety techn ic i.~m C;1 tered tile Extr"c tion Sample Aisle (XSA) on June 30, 1967, in order to tr.ake a routine survey *
. Prior to his entry, the technician should hm,e r...:lde an eV.:11uation of the existing airborne riidioactivity based "pon the previous survey, the \-lork being per[ori\\ed in related aL'C,IS of the plnnt
?
and thc history of nirbornc radioactivity levels in the XSA. Notations in the Health and Safety Shift Log for June 28 - 30, 1967 indicate that the technician ,-las a\,'nre of the existing conditions in the XSA. The technician exercised poor judg~ent nnd disrecarded es t:Lblished Health and Safety reqtlire:T.cnts. This technician, ,~hose actions led to citatiol'<; la, le, and 3, is no longer employed at NFS. To.provide more current surveys, the schedule of air sa~pling the plutonium sampling stations has been increased to once per shift. Lb. "No evaluation was m:J.de of the concentrations of rndioo.cLive material e:-:istino:; in the E:,trac~ion So.mple Aisle on Septer.\ber 9, 1967 prior to or during the entry of a technician durin~ a p1utoniura sar:lp'lin~ opera~io:1 * . " An evaluation ".'as r.ude of airborne radio:J.ctivity in the E:,traction Sa~ple Aisle (XSA) prior to the entry of an operator and an observer on September 9, 1967. Both individuals ,*.'ore respiratory protection. Tne NFS investigation concerning the one individual (the operator) \-lho sho\,ed plutonium in11ala ti0;1 indicated tha t the exposure occurred due to the operator's irJ~;-opcr ~isrobin~. It should be noted that the operator's internal deposition \~as subscc:uent1y determined to b~ belo~: the minir:lum detectable 1i~it of \-loole body counting.
l.c.
"An a(]equalc cV;1I~U__O~1_~,-~~()_~:::.:..~;~()f _~h('~!.!~'~!LdCJ!(0-.!.:..i22..
110873 of plutoniu;:l ~n ~ tcC;'ti:i_~j~'~_l~~(~J2-a'J -'s.2.~~:c<1 lh(:1'~': t1~~~.£.~..i0n S.:1!oir-J c Aislc, Hitilout r(,~;\lil""t.un' prot"clion 0.1 JUllC 30, 1967 .. "
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Nuclco.l" Fuel. Services bvlio::vcs thaL <! more tkm ac1cqu.:ltc evaluation was nl..l(lc of the possihlL! intc:rno.l C:cposition of pllltoniu~:) in the! Health [lnd Safety teelmieL,;l \'::10 entered the E,:traction Salilplc Aisle Hilhout respiratory protection on June 30, 1967. Urinalysis indicated that any plutonit':-:1 e:*:crcta ,*;0.5 10Her than the m~n~mum detectable eoncentr,.. tion (0.3 clp~\ per liter). Hhole body counting (copy of results ,*:ere sent to Region I, Division of Compliance on November 10, 1967) indicated that any possible internal plutonium "las belo;, the minim",,\ detectoble conlent. The survey to determine exposure I';OS initiated ,*,hen positive nasal smears were detected. The failure of the lle<!lth and Safety technician, who vms exposed, to fulfill his duties deloyed the evaluation. Hm-lever, a thorough evalu.:ltion ,,'as made. The technician is no longer employed by NFS.
- 2. " .
- on SeptEmber 9, 1967 ,~rnittec1 a Technician to be e:,posed to airb?rnc, c_~~_trations of plt1lO1~iuiOl in excess of the liiOlits in AEPenc1ix J\, To. hIe I of 10 CFR 20." - 1i1e NFS inves tiga tion of the plutonium inh.:llation that occurred on September 9, 1967, indicated that the C.:luse was improper disrobing and not inaclequa te hca 1 th phys ies proeec\ures. Both the opcr,l tor and the observer wore respiratory protection during entry. ~1ly the oper.:ltor shmved possible internal expos .. re. The observer had no detectable internal plutonium. The operator admitted that he had not fOUCi-led the specified disrobing technique although he knew the pro.cec\ure. Subzcquent evalu.:1tion shOl*:ec\ the operator's' internal plutonium content to be beloH the minimum detect<1ble limit of whole body counting, L e., beloH 20% of a body burden.
The investig<1tion also dete:r:nined that unsatisfJ.ctory sar.\pling equipment led to the are.:l contaminntion. Significant rev~s~ons have been and are being made to the plutonium sampling,equipment. These inc lude :
- 1) Use of radio-frcquency sealers insteJ.d of heJ.t scalers for closing sample bottle removal bags.
Z) Usc of heavy ~"nllcd polyvinyl chlo:.:ide bn£js instead of the thinner polyethylene bags for sample bottle rcmovJ.l,
- 3) Install.:ltion of sphincter seals for entry of sample bottles into the sampling glovebox.
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- NovL',ncnl or the pcn,,:mcnt :d.r ~.:I!nrler nearer Lo the \:or:,
110874
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- 5) PUl'ciJnsc nnG in.:.tnlLHion of o.cic1itiollnl zinc sulfiue: alpho.
monitors nt the c:d.ts [1'0;,1 pllltoni.um so.lllplinr; stations.
- 3. " . . no recol:'~~._!T::'int::.iEl~L().L~_"s<ll sr.lC',:'lr survey pcrforme..£ on the innivitlll.,l on Jtl11C :30, lY67, "ftel: hc exited from the t I '.. ....
are" of :::.i.l'borne plutoni.t1,.l i\ctivilv." - The cont<lmj.nation of the technici.,m on June 30, 1967 "l:l~; recorded in the Health nnd Safety Shift loG on that date. During the i.nvcstieo.t:l.on of the incident. thc smear survey rcsul ts \,'ere trnnscribed to a "Lapse of Control" report cl.:tted Atll;;ust 10, 1967 ,*,hieh is on file at }FS. Th is repor t \*ms reVie\'leu by the Division of C01:1pliancc inspec tors during September 26 - 29, 1967. Nuclear Fuel' Services nuinto.ins a system of logs and records morc extensive that Vlhat \'le believe is required in order to assure . compliance \'li th 10 CFR 20.40 1 (b) and the NFS license. ~7c believe that 10 Cl-'R 20 does not require a permanent record of nasal sr.1Co.rs. Nasal smears, hand and :Coot counting and self-monitoring are itelTlS of inten1al control. Very tl'llly YOtlrs. NUCLF..AR FUEL SERVICES) INC
- T. C. Rtmion President dr
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- llCJ~l Technical Specification 7.4 of License ~o. CSF-l As Authorized by Change No .. 6 7.4 In addition to the other requirements and limitations of this
'licen$e, NFS shall conduct operations of the plant in accordance with the proviaions of :i.ts letters to the Commission dated January 13 and 15, 1968.
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Ilfl760 IIQ-4G UNITED STATES ATOMIC ENERGY COMMISSION (!H~) RCGULA10RV MAlt. AND RECORDS SECTION Your ~ IcUC'r, 0 application, dnted ......J~~.. ~.J..J~9.? ......... . illcludillg ene losures .. 9.f.. C:l).~r1ge.J!9.~ .7...<E;:I?.Q~I!.~~D. ..~~.J~~l].,! .. ?.P~~?.*. is aclwowiedgcd und has bcen assigned: DOCKET No. _ .. 5.Q~2QL. ....... _...... or CONTItOI, No. Please refer to the nbove number(s) in future correspondence. Date Received: ... June . .7., .. 19.6B....... . This is an acknowledgment form only. It is not a reply to your communication.
CriANGE NO. 9 111111 ('" .
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Dear Dr. ~ic8ride:
Nucleor ruel. Services he:'*;oy requests Change 1,0.9 to the Tec.hnical SpecificiJtions of Pl'ovisionJl Operating Lic0nse 110. CSF-l to per<nit gr('ater f1('xibility in calibration of r.lonito1'ing equipment. ;'i'2 request tInt Speci-fication 3.3 be amended to include: Form Krypton-S5 2 curies gas KrypLon-85 ? x 10- 1 curie s(\1led source These sources will be procured fro~l co~nerciDl suppliers and will be used by the !ll?Jlth and SJfety De(li.Jrtmcnt for caJ.ib:-aticn onci functiOn'll checks of the g:!5 section of the stack m0n~.tor. The requested radioactiv0 quantities re~re5ent two sources in each for~ at concentrations appropriate for the hi~lest exposure fuel to be processed. We do not believe that tllis proposed change presents arlY significant hazard consideration not dcscrib'd or implicit in the' n::s Fin~l S;Jf'ty Analysis Report and that there is r'asonable assurance that the healtll and sa f ety of the public \'Ii 11 not be endi.Jngerec!. If furthe::: in forma tion is necessary, please contact me. Very truly yours,
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- Vice Presidont and Genera 1 1.~a nagel' VlGU:JRC: ah cc: D. H. Shafer E. D. No:-th B. G. Bechhoe[cr
Dr. J. A. ~:c3ride Direclor of ~:t~rials Licensing United Slate:., A'co",]c t:nol'gy CO~:'"issi(ln
\':ashington 25, D. C.
Dear Dr. ~:
cBrid~: NucleClr fuel Services he:'eby rc:quests Change rio. 9 to the Tec' Specifications of PI'ovisional Operating License rIo. C5;:-1 to permit 9 flexibility in calibration of nlonitol'ing equipment. ;'ie request that fication 3.3 be amended to include:
/.:a t eria 1 Form Krypton-S5 2 curies gas Krypton-85 2 x 10- 1 curie sealed source These sources \,lilI be procured fro:,1 co:r.'nercial stlp;:>liers ar,d be used by the Health and Safety Depart~lent for calib~ation and func' checks of the gas 50ction of tho stack monitor. The requested radioi quantities re~re5ent t~o sources in each for~ at concentrations appro for the hi01sst exposure fuel to be processed.
~e do not believe that this proposed change presents afl¥ si9 haz~rd consideration not described or implicit in the llFS Final Safe Analysis Rc*port and that the!'e is reasonable assuranc,-, th2t the heal sa f ety of the publ i c \'Ii 11 not be endangered. If furtllcr in forma tion necessary, please contact me.
Very truly yours,
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Vice President and General i.:anagcr VlGU:JRC: ah cc: D. H. Shafer E. D. No=th B. G. Bechhoefcr
f ,1 '-" ~ .\... , '-""-'. 'I t'~,' i . -. -;;;: :~ r\ UI'lITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 111108 Docket No. 50-20t DEC J 1 1968 Change No. 9 License No. CSF-l Nuclear Fuel Services, Inc. l'lheaton Plaza Office Building Suite 906 l'lheaton, I-Iaryland 20902 Attention: Dr. E. D. North, Director Technical Administration New York State Atomic And Space Development Authority 230 Park Avenue New York, New York 10017 Attention: ~Ir. Oliver Townsend Chairman Gentlemen: This refers to your request dated November 21, 1968, for authority to receive, possess, and use krypton 85 sources to permit greater flexibility in calibration and functional checks of the ~as section of the stack monitor. Your request has been designated as Proposed ...;.ange No. 9 and has been considered pursuant to the provisions of 50.59 of 10.CFR 50. The krypton 85 to be used for calibration purposes is 0.02 percent of the amount that may be released to the environment each day under Technical Specification 4.1.1 of License No. CSF-l. On this basis we conclude that the proposed change does not present a significant hazard consideration not described or implicit in the NFS "Final Safety Analysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered by the change.
111109 Nuclear Fuel Services, Inc. DEC 3 1 1968 Mm New York State Atomic and Space Development Authority Accordingly, pursuant to Section 50.59 of 10 CFR 50, the change in Technical Specification 3.3 of License No. CSF-l as set forth on attached page No.8 is authorized. FOR THE ATOMIC ENERGY COMMISSION OriGinol Sig"ed by J. fl. McBride J. A. MCBride, Director Division of Materials Licensing
Enclosure:
~ Change No.9, Revision Page 8 cc: Mr. B. G. Bechhoefer, w/enel. M~. O. M. Ruebhausen, w/enel. Mr. W. G. Urbon, w/enclt( <<~~
3.3 l'.ateria 1 Possession Licit Form Cesiu~ 134 6~ x 10- 5 curie any Iodine-131 6. x 10-6 curie any Iodine-129 s. x 10- 6 curie any
. -3 Strontiut:l- 90 6. x 10 curie any Krypton-liS 3. curies any Zinc-65 2. x'10- 5 curie any Cobalt-60 s. x 10-2 curie any 5
Carbon-14 1. x 10- curie any Tritium 1. x 10- 3 curie any 6 Any byproduct :nterial 3. x 10- curie any with atomic numbers each from 3 to 85 inclusive (Chotn:;e No.9)
CHANGE NO. 10
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PU):SU2i!'.. 'La P<<:2,'CrC;':~\;1 ~')'J.~/) of TitJc 10 of tit0 Code or F('~:.:rdl R.09uJ.;.:t:ions, ~'!11CJ.02~.~ Fuel Scrvicc'-s, Inc. h(.1X'0by YC(;:,'c.'sts Ch;:.:*,,;o i,I*:). 10 to i.h0 Tcs~lr,.i.(:~:l SpC'c:~,fic(,:'~:l(~nS of Provis:i.orl:'] Gpcl'(.;-c:i nJ J..:~.c.r:-'n:*c CSF-l. }('cll;li(:,:11 S;>"ci.f:i.CiIUOI'l~~ 3.J .1, 3.3 and 1:.3 '::hi,cIt c;c *.. :0;.,i~,', the I)TOr)o~.*::d C:h.~lIJJC' ;.\). ]0 orlcl tIle rCJ:'*t::i.ll"~*t!"L nuc] (':"".' c:r'.i.tjc-j' :~.,y rev:i.0~**~) D"I.'C (Jt*:'::'ch(~';. \'!c dt) no'c b(.llievc t!Llt thcs(' :lrOrOC,(~(: (.:.::;J~J(':; PJ:o~crd~ 8::y sic;n.~..r:;.c((nt l:0::2.}'cl considor2lt:7nn not dc:-,c:ribc,d or jr\*\lje*i."l in the i,::-:S f5.n~;]. S2;cty }\.1::11y::-*5.f. Report 5UIJil'littc'd l',rl(10:r 11..)c):':'~ :';.J-~~:)~; thcJ(~[o"CQ tl1..rLhOJ::i.7,i.*,'cioll of tIle. ch2n'Jc':'1 is l'C(~l.iCC,*~C:*cJ. To PC}, ,~.;. i;;::=; to meot :its rroc'::s~ljn'J COi":\;!1i"lf:~ent~~, your c'~;r'l:ic:::;t p(l~siblo 2:-,:,('cl;"'c:] is clC'sir8c1. VelY truly YCUYc" i / I / VI. G. U:rhcln Vice Pr~sid2nt and G~ner~l L:2i1~19CJ' ViGU:JRC: slk
Enclosure:
Technica' Sp?c~fic~tion 3.J .1, 3.3 and 4.3 Nuclear Crltic21ity Revlc~1 cc: Eo D. I,! (1 I i;il D. H. Shelfe:T. B. G. Bcchhoe:r('l'
Page withheld as containing Export Controlled Information 155
Page withheld as containing Export Controlled Information 156
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L These ,adioisotopes, ;*;hich '::ill be ;)u!':hased ::-Or:l cOr:l.'ne:-cial suppliers in liquid forms, will be in the tJossession and under the control of the Health and Safety Department *. C. Soecification 4.3.4 It is proposed that the present Technical Specification 4.3 "Storage Canister Loading and Spacing" be modified to permit storage of fuel from the "superheater" section of the BONUS reactor. This fuel will be provided by the USAEC, Division of Production, under its contract with NFS for processing. The fuel from the BONUS reactor consists of "boiler" and "superheater" types. Both types are Category 1 fuels. The boiler fuel satisfies the spacing requirements of Specification 4.3 but the superheater fuel assemblies (4 1/16 x 8 7/8 inches) are too large to fit within the spiders that are normally used to assure a separation of '12 inches between fuel assemblies. A criticality review (attached) has been performed which indicates an eight inch separation is more than adequate for storage of superheater assemblies. Some comments relative to the criticality review
- 1. The evaluation, as noted on page 5 of the attachment, was based upon un irradiated fuel and is therefore conservative.
- 2. The evaluation was made relative to a Kx:J = 0.90; however, an evaluation can be made relative to keff = 0.85 from Figures 2 and 3. From these figures it can be seen that the keff is < 0.85 for the equivalent superheater diameter of about 7.25 inches when a separation of 8 inches of water is provided.
- 3. The evaluation did not consider the interaction with other stored fuel; therefore, the proposed Specification 4.3.4.2 will assure a distance of twelve inches (neutronic isolation) between superheater assemblies and assemblies of other fuel types. Practically this will be done by keeping an empty aisle on both sides of the storage section where superheater assemblies are stored.
111092 I 4. Mention is made in the evaluation that additional nuclear criticality considerations must be made for ~hen the superheater assem~lies are removed from beneath the water. Such considerations are already intrinsic to the processing of fuel at ~FS. The canisters will be removed one at a time (:nerefore, one assembly at a time) and tran~ ferred to mechanical processing. The number of assemblies in the Process Mechanical Cell is limited by SOP 2-31 "PMC Handling Procedure" to a) not more than three in the Pl~C at any time. b) not more than one assembly at any time in the following locations: tilt fixture, north half of saw table, south half of saw table~ north half Disassembly and Pushout (DIPO) table, south half of~ DIPO table and feed magazine. J r
Page withheld as containing Export Controlled Information 159
Page withheld as containing Export Controlled Information 160
111095
*'.~ater ia 1 Possession Li~it Form Cesium-134 6. x 10- 5 curie any Iodine-131 6. x 10- 6 cud e any Iodine-129 5. x 10- 6 cu=:.~ any Strontium-90 6. x 10- 3 curie any Krypton-85 3. curies any Zinc-65 2. x 10- 5 curie any Cobalt-60 5. x 10- 2 curie any Carbon-14 1. x 10- 5 curie any Tritium 1. x 10- 3 curie any Cerium-144 3. x 10- 5 curie any Ruthenium-106 3. x 10- 5 curie any Zirconium-95 3. x 10- 5 curie any Chromium-51 5. x 10- 5 curie any Any byproduct material 3. x 10- 6 curie any with atomic number~ each from 3 to 85 inclusive
Page withheld as containing Export Controlled Information 162
Page withheld as containing Export Controlled Information 163
1110~b 4.3 Ad~inistrative procedures are established to assure correct canister loadings. The decreased water spacings permitted for Dresden canned fuel and Bonus Superheater fuel have been shown to be nuclearly safe in NFS letters to USAEC Division of Materials Licensing dated April 28, 1965 and January 22, lS68. The consequence of exceeding this specification would be to decrease the margin of safety for the prevention of criticality. In Paragraphs 7.33 and 7.34 and 8.29 of the Safety Analysis it has been assumed that despite all design efforts, a criticality incident somehow does occur. The con-sequences of such an unlikely event have been analyzed and show that neither operating personnel nor the general public would be injured as a result. The action to be taken to correct an exceeding of this specification is to take immediate steps to increase spacing of fuel in storage or decrease canister loading. (Change No. 10)
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I, \ '" \,1/ I I - V Suit,r~. s:<.S 1','llC~'~'~or:, :.1'..'. ,I',,:J :--~nlJ. 2.,./_ Attl2'ni..i.orl: Ge:ntle:, .. :;* : 111rsl~O,;lt to th>:: Atc,:::i_c E:-~',,;!_'~::/ t.ct of 195'+, tiC ae:cri<l(!U, a!1u the rcculo.t::'or-!,s issued P~:~~~L:-:--',:~~c t:v:':r'e:to, it is hereby ordered that: cfft!c t i \~c: ir('::1edi~.tcl:.p '_~~~';C:i yC"JY rccc!i.pt of thi s Ord.er, you sh:,J_l C0~_~,!)] 'v' ,*t:' th t!':.e fo.llc,,*i:-::: :-C:~l1.J.i.rC';r.cnt.s Governing the trD.nspor-t~.. tion (,f licensee. ~~!::ci~'.:" n*Jcl(~2.!* materials. These !"~1:.l:"!:c:*.::::nts r~~:':I.lJ only t~) tho~c ship;nents clf sp2cial nucl(:~~.;:- n::.tc:~*i2.1 Gl'*::~t~:: th(~n 5,000 crarns o:t ur&nitL71 235 (ccr:- t~titlc:d in m'"ni.ur'l e::!"ic]'J'::cl to 20% or more in th(; U-235 isotor:~), u.rftniu~~.'_ 233, or plutorlit~:, or a combination the2~cof. These rCCl1..'*irc;-.:~nt::; do not 2..ppl:r to; A. tlrc'r!ium CL1'iche:Q to lc~;s th:-:.n 20~ ir:. the U-235 isotope; B. special nuclc-:.r ::::~;;c,!'i;-cl deliverinG an c:zt8rn<:,1 dose in cxceGC of 100 re~s per hour at a distance of 3 fcet from ar~~ 2.cc(-'Gsiblc su~~f~~c~ ~*,*i.thGut intervening shicld.i!1~; and securi ty procedur,::s prescribed by the /,to:nic E:1erQl Cor~~7,ls:;:LOn or anoth'::l' Goverm:,e:1t agency for classifid material. Level r special ::u(;le.:).1' no;.terial shall be (1) transported in the continuo'J.s ":J9r.2o!:::.1 custcdv of C1.n e:J.tho!'ized f inclividu",~, or (2 d.eli vered to a" cOn'"-non or contract carrier for tre,nsport by such carrier in accord2,nce Hi th estz.blis::~d proccd.:..u'c 8 *..,*hich prov-ide for the ph::,"sic2..1 protection of */c,:,:~2.ble ::-.:::. terial i:l transit aml require an cxcha.~E:c of !:2.r~d-~c-:'18.r:d. receipts at origin Gnd
111335 of cu.ot::::ly. to 50,C'~J c:::~::::~ 'ul'::.n.l'",L.:. 2j~, c'..Jr1t~~~:.*::i in urc.:1ilJJ.1 c:~l"ic~:'..:d ~o 20~; O!' ::.:J~*C ::1"J th(; U-235 i::()~Ol;':~' O~" (2) ),GC0 to G),CCO br8..":".S of ur,:,:',:;:: ?~3 0,: ljluc,~"i".:'~_, O~* (3) 5,CC-J t,} 50,((0 c;~*,;:~s 0:' "- COmOi!l::' -:.~ on C1 t~'2 I:".:!. tCl' ie.l ;:;l::0C 2.1"'i cel E:.OOY*':! CC!~.pu :o:~:l b:: [:.-:1:1i ~s the Hc:i~:-::: cf U-235 to t~-tic(; ~~h~ ~./Jt2.-:" ';;'::iC1l":~ of U-233 p.t;d rJ.. IrAuthC!'j.?o:.:d i r.cl5.v.iduo..l" r::c~),~:~; c~r;~.'* indl*:j.du~~~., i:1clt:,di.:':G e.~ emploj'c(;) a c()n;.,u~.ta!lt, or o..:~ a,sc::.t of a licc::scc, ",';r!o has cC:-3::1 dcsigr.2.:.cd i!l "\';ritj.r..g by a lice:L>:c to h2.vC survcill£:.:!ce re-sponsibi.lit:; ever Level I or Level II s}Y2cial nucJ.ear r.1::.::erial or bot:!. Level II SlJecial n'1c1eo.r materio.l shall be (1) tre.r.sported ir. the contin'.wus pc:rsonal custody of an authorized indivldvC'.l CJr (2) delivered to a comr~on or cont!'act carrier for translJor" oy such
'carrier i,n accordance \\1. th established proced~Jres *.:~5,c:: p!'ovide for the pl:ysical p~'otection of vo.luo.ble matc2'.lal in tran.,:.t 2,:1d reQuire ee' IlL lnuou::; survc il1nnce by one or more e::1pJ.o:;-:!'2 S 0 f thf"2 carrier of t118 Dlatcrial or the J_ockcd vchj.cle~co~t~ini~z the materip.l.. "Level II special riucJ""r mo.ti:!rial" r.J.e2,n8 e.r.y q'.l.ar.:ity of uran'~'.l!" 235 (contain~d in uranium em'iched to 2C% or ::'c-:)!", ~n the U-235 isotope), urC'.niUIn 233, 0)' plutoni1..<.":l exce(,dir.g t::~,
quantities s,:;"cified as Level I special nuclear :,,~'.;erial. Requirer..ent ~;o. 3 Records 5:12.11 be kept of all shil=*!T.ents of LevlOl I and Level II special n';clear mC'.terial, i.nc luding the mea.ns cqlloyed to lJro-teet such rna~erial while in transit. Require!:'.ent ~io. L. A report shall be made in~ediately to the aTIDropriate Districo Safeguards Of:~ice, Di*... ision of Nudear !*:aterials Safes'.:.::.rds, by telephon~, telegra::*., or telet:rpe of any shipr.'.e:::~ of Level I or Level II special nuclear material that is lost or ~naccounted for after the expected time of arrival.
Ple::.:~ rei:.!l* C:!~j~ quc.-:-: ::::..c:~~; :;uu r~:~;.y h~;.vc tw the Di::cctor, Di *ri::;,ic!l of liucl'~ar l.":ate:tic:.:s S0.i\~~*J.::-:.2:cJ.S, u. S. /:.tQr:1ic Enercy Cc;;::,liss::'0n, HasninGton, D.C. 205 1;5. Si.nccrcly, QL/~:,~,I.~:l8 I
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t V" H?rold L.I Price Director of RCGul~tion e~'2.~'-
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.., , .,. ~ A !;UOSIDI/\MY OF" V'I R GRACE L CO BOX 124"'WEST VALLEY. N.Y. 1-1171 I,~a rch 17, 1969 Dr. John A. ~cBride, Director Division of ~JterjAls Lic0nsing United States Ato~lic Energy Commission Washington, D. C. 205'15
Dear Dr. ~caride:
The fo11o\':ing inform'3tion is submitted in support of Change No. 10 to the Technical Specifications of CSF-l, which was requested by the NFS letter dated January 22, 1969. TUs information is as requested in telephone conversations ~itJl personnel of Divisiorl of Materials Licensing. A. Specific~tipn 3.1.1 Since Change ~o. 10 will not specify cladding material, NFS requests that "plus cladding" be deleted in the second colur:m of the specifica-tion for Category 5 fuel. l~e specification would then read: 5 U - Zircaloy alloy No limitation Chemical or U - Zr alluy (U content not exceeding 10 IV/O of alloy) NfS also requests that the pre-irradiation U-235 enrichment in U for Category 9 fuel be changed to 2.5%. This enrichment will correspond to slightly higher than the maximum enrichment (2.1%) that r~FS expects to process. The specification I';ould then read: 9 U metal Not exceeding 2.5% Mechanical B. SpecULcation 4.3 The water retained in the structure of the Bonus superheater fuel assemblies will be removed during the first processing operation in the Process ~:echanical Cell after transfer from storage. The standard operating procedure for this fuel permits only one assembly to be on the sa'/I table at any given tbe; therefore, sup~rheater assemblies ":hich contain I'later l'Iill not be in close proximity in the Pi,lC. A nuclear criticality evaluation of storing Category 9 fuel in canisters in the storage pool is attached to this letter. The evaluation is based upon a pre-irradiation enrichr:lCnt of 2.1% U-235 which is the highest
I Dr. Joll;1 )\. :.:ci~=:id(.: 111~31 I\J SJQ ~
- .:a !CII U, 1969 enrichment of NPR fuel expected to be processed at NFS. If higher enriched fuels become available, appropriate criticality analyses will
- be performed. Only full canisters of outer NPR fuel tubes have been considered since this is the only available geometry for ilPR fuel of the higher enrichment. Under conservative assumptions, the keff of a storage canister is 0.75 vlhich cO(;lpares favor*dJly I'lith the 0.35 limit.
imposed by Technical Specification 4.3. NFS requests that the fourth paragraph of the Bases for Specification 4.3 be changed to: 9 N - (full canister), enrichments not exceeding 1.5% N - (-x-), enrichments above 1.576 Such a change will allow NFS the flexibility of processing various NPR fuel types that the USAEC might provide yet will assure that nuclear criticality evaluations are made for canister storage of non-standard fuel assemblies. A typographical error in the sixth paragraph of the Bases for Specifica-tion 4.3 should be corrected to "January 22, 1969." I trust that this submission will answer your questions. Very truly yours,
) I,_.f f'//, _.
1'1. H. Lewis Vice President and Genera 1 r:'a na ger V.'HL:JRC: ah Attachment cc: D. H. Shafer
- SMI.PLE CALCULATION FOR keff FOR 1lPR FUEL STORAGE The following core parameters were obtained from Ronald Chitwood, Richland Operations, Richland, Washington:
~2 = 2.182 diffusion length squared
* = 27.367 fermi age E = 1.19 fast fission factor p = 0.7377 resonance escape probability Assumptions:
- 1. A = 8.0 cm extrapolation length (Chitwood gav~ it as 7.8 but 8.0 was used as a conservative number.)
- 2. No credit taken for burnup of U-235
- 3. No credit taken for fission poisons
, ~h
~f
=
=
thermal non-leakage probability fast non-leakage probability 82 = geometric buckling f = thermal utilization Fuel element size = 2.406" 0.0., 1.764" 1.0., 23.2" length Canister sleeve size = 7.5" 1.0., 12' length
=
where: R' = R+}, H'" H+), R= ( 3.75") (2.54 cm/i n) = 9.53 cm R' = 9.53 + 8 = 17.53 H " (144") (2.54 cm/in) = 366 em H' = 366 + 8 = 374 cm
IlJ~IJ"~'
- u*J 0:2 = /:2.405)2
\--
.,. (3.14)2 17 .53 374 B2 = (.137)2 + (.0084)2 32 .0188
= '::f = neutrons from fissions available to produce second generation La of fissions v = 2.43 ("Introduction to Nuclear Engineering" by R. L. Murray, p. 105)
.235 = 590 barns (238 = 2.41 barns f a Cross-sections from "Introduction to Nucleilr Engineering" by R. L. Murray, p. 46.
(2.43) (.021) (505) ( .021) (590) .;. (.979) (2.41)
= 1.74
, 1 1
~th
= = .96 1 + ,J. 2 82 1 .;. (2.182 ) (.0188)
-if = exp - (B2 ,)
e-(*0188) (27.367) e-* 514 d.-f = = = .597 (;)~a )U f = I,)
\, 'a U T,(~) L.a H f = .239 + .0437
.239 + .0437 + .0985 f = .737 keff = ~, f c P d.-th J:.f keff = (1.74) (.737) (1.19) (.738) (.96) (.597) keff = .645 An f of .8594 was obtained from Hanford for an optimum array of fuel elements.
Even L. ; this f is used, keff is still only .752.
Ur-.IT£::> STATES ATOMIC ENERGY CO~""MISSION WASHINGTON. C.C. 10~45 MAY 6 1939 Docket No. 50-201 Change No. 10 License No. CSF~ Nuclear Fuel Services, Inc. Box 124 West Valley. Nr4 York 14171 Attention: ~~. W. H. Lewis Vice President and s;eneral lo'.anager AND New York State Atomic and Space Development Authority 230 Park Avenue New York, New York 10017 Attention: Mr. Oliver Townsend Chairman Gentlemen: This refers to Nuclear Fuel Services' request dated January 22, 1969, as amended by letter dated March 17. 1969, for changes in Technical Specifications 3.1.1. 3.3, and 4.3 that would authorize: (1) receipt of higher enrichreents of certain categories of fuels; (2) possession and use of additional radioisotopes for calibration sources. and (3) storage modifications to accommodate BONUS superheater fuel. We have reviewed the proposed changes and have found that they do not present significant hazards considerations not described or implicit in the NFS "Find Safety AnalysiS Reportll*and that there is reasonable assurance that the health and safety of the public will not be en-dangered by the change. A copy of the related Safety Evaluation by the Division of Materials Licensing is attached.
,I*
Nuclear Fuel Services, Inc. Accordingly, pursuant to Section 50.59. 10 CFR SO, changes to Technical Specifications 3.1.1, 3.3, and 4.3 of Provisional Operating License No. CSF-l as set forth on enclosed pages 5. 8. 17. and 18 are authorized. Page 19 is voided. FOR THE ATOMIC ENERGY COMMISSION OrIglnal *Slgned by J. A. McSride J. A. MCBride. Director Division of }~terials Licensing
Enclosures:
1*. Change No, 10, Revision Pages 5, 8, 17, and 18
- 2. Safety Evaluation cc: Mr. B. G. Bechhoefer, w/encls.
Mr, 0, M, RuebhauRp.n, w/enel_. Dr. E. D. North, w/encls.
Page withheld as containing Export Controlled Information 175
Page withheld as containing Export Controlled Information 176
Page withheld as containing Export Controlled Information 177
Page withheld as containing Export Controlled Information 178
3.3
.8.
!-faterial Possession Limit Form Cesium-134 6. x 10. 5 curie any Cerium-144 3. x 10. 5 curie any Iodine-13l 6
- x 10.6 curie any Iodine-129 5. x 10.6 curie any Ruthenium-l06 3. x io* 5 curie any Zirconium-95 3. x 10. 5 curie any StronUum-90 6. x 10. 3 curie any
!{riPton-a5 3. curies any Zinc-65 2. x 10. 5 curie any Chromium-51 5. x 10. 5 curie any Cobalt-60 5. x 10.2 curie any*
Carbon-14 1. x 10. 5 curie any Tritium 1. x 10.3 curie any Any byproduct material 3. x 10.6" curie any with atomic numbers each from 3 to 85 inclusive (Change No. 10)
4.3 STOP.AGE CJ.jiISl.:.H LOADn:G AIm SPAcn-rG Applicability This specification establishes limits governing fuel distribution in the Storage Pool. Objective To assure tha~ individual units and arrays of units are maintained in sub-critical configuration. Specification 4.3.1 IRRADIATED NUCLEAR ron IN THE roEL STORAGE POOL SHALL BE STORED IN Ck~IST.EJ-uS. 4.3.2 THE 0.t!.t111TITY OF FUEL STOP.ED IN A CANISTER SHALL BE LD.fIT;ED SO THAT
'mE EFFECTIVE !7E'.;'TRON !*rULT!!'LICATIO!l FACTOR (keff) 5:iALL XOT EXCEED 0.85 BASED <Il m7I?2ADIA~ FUEL. THE PRECISION OF 'IRE keff CALCULATIC:: ShALL BE CC11FIFU*:EI) EY: A??Lmm 'IEE CALCULATIO!lAL ME'mOD TO IalOWN CRITICAL sysro:s OF S!!-!!L.4.,R ~.JE!: !-!.":.!:.EP.!.4~.
4.3.3 IN LIEU OF DETEPJ-In!DlG 'mE keff OF A CANISTER LOADING, ANY SINGLE roEL ASSE*::ELY OR PACY.AGE ,r.-iICH HAS Emi STORED UI'II:ER WATER PRIOR TO SHIP:*:ENT MAY EE STOP.~D I?l A CJJIISTER, PROVIDED TnE GEQ!,IETRY OF THE ASSE:.mLY OR PACKAGE IS !lOT REARRANGED. 4.3.4 CP.NIS'l'IRS SF.ALL BE SPACED TO PROVIDE A MINIMtJl.1 OF 12 INCHES OF WAT.E...'l BETWmI FU:tI. COliTAINZD Di AJ:)JACENT CANISTERS EXCEPT AS PROVIDED BELOW. 4.3.4.1 '!SCSE CMrISTERS Cm."MINING DRESDEN CAl\~D FUELS SP.ALL BE SPACED TO PROVIDE AT LEAST 9.6 INCHES OF WATER Brn1EEI~ ADJACEr!1' roEL CAr:S AND THE Doll-iEDIATJ:.LY ADJACENt STORAGE RAC'!G SHALL REl*!AI!j EMPTY. 4.3.4.2 'mOSE CANISTERS CONTAINING BONUS SUPERHEATER FUELS SHALL BE SPACED TO PROVIDE AT LEAST 8 INCHES OF WATER BETWEEN ADJACENT CANIS'!!ES Co.lo:rTAI:-;r.~G StJP!..'{!!.EA'lL.!'! FllLL .A.~D AT LEAST 12 INCF.ES OF WATER BEnlEEN CANISTERS CONTAINING SUPERHEATER AND THCSE CANISTERS CONTAIlm,G O'IHER TYPES OF roEL. uses The Fuel Receiving and Storage A.**ea (FRS) has been designed to permit the handling of fuel assemblies such that geometry and administrative control prevents the interaction of one fuel assembly vith another. These precautions are neCeS9B-~J since the FRS vill at most times contain fuel in excess of that necessary to result in a criticality i t placed in optimum array.
4.3 The storage racks* and canisters provide a minimuo edge to edge spacing of eight inches between.adjacent canisters and a mini~m edge to edge spacing of twelve inches between the fuel contained in adjacent canisters *. This separation of twelve inches of water prevents significant interaction of neutrons and provides a s~fe array. A keff less than 0~85 provides a reasonable margin of safety to account for uncertainty in calculations and error in the identification of the fissile material content. By co~paring the calculative method with known critical systems of similar fuel material. uncertainties in the ~ethod are minimized. Individual fuel elements or packages previously stored under water have been demonstrated as safe and, therefore, no further calculations are deemed necessary provided that 12 inches is maintained between fuel in adjacent canisters in storage
- Administrative procedures are established to assure correct canister loadinr.s.
The decreased water spacin~s permitted for Dresden canned fuel and BONUS superheater fuel have been shown to be nuclearly safe in ~FS letters to US,\EC Division of ~~terials Licensing dated April 28, 1965 and January 22, 1969. The consequence of exceeding this specification would be to decrease the mar~in of safety for the prevention of criticality. In Paragraphs 7.33, 7.34 and 8.29 of the Safety Analysis it has been assumed that despite all design efforts, a criticality incid~nt somehow does occur. The consequences of such an un-likely event have been analyzed and show that neither operating personnel nor the general public would be injured as
- result.
The action to be taken to correct an exceeding of this specification is to take immediate steps to increase spacing of fuel in storage or decrease canister loading. (Change No. 10)
CHANGE NO. 11 (. ( .~."-, ,." 'I ( ,/1"/\, (
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\, ' .
F0b~uc~y IS, 196) Dr. John A. /,\c3rid2, Di::-ocl;or Division 0; Materials Licensing United States Ato;r.ic Energy CO;;:r:1ission Washington, D. C. 205*45 Deilr Dr. i,;cBride; Pursuant to Paragraph 50.59 of Title 10 of the Code of Federal Regula-tions, r;uclear Flwl Services, Inc. hereby requests Chilngc ::0. 11 to the Technical S?8cifications of ProvIsional Operating ;.icense CSF-I. Technical Specifications 2.0, 4.1, 4.2, 4.6, 4.7, 4.9, 4.10, 4.11, 4.12, 4.13, 4.15, 4.16, 5.1, 5.2, 5.5, 5.G, G.1, 6.2, G.4, G.6, 6.7, and 7.1 are attached. ~e do not believe that these changcs, which have been discussed in detail \'lith your staff, present any significant hazard consideration not described or implicit in the NFS Final Safety Analysis Re?ort subr:Jitted llf1der Docket 50-201; therefore, authorization of the changes is requested. If additional information is required, we will be available to meet with your staff. Very trul y yours, Vice President and General ,',ianZlger ViGU:JRC:ah
Enclosures:
Technical Specifications cc: E. D. North D. H. Shafer B. G. Bechhoefer
APPENDIX A TECW: I C.,\ L SP ECI::= ICAT 10;) FOR LICE}JSE CSF-l Nuclear Fu~l S~rvices, Inc. N'?VI York State Atomic and Space Development Authori ty
111:,42 TJbl (; a: ,~>: ;'~y-: ~l ~:;
.----- ------~
0.0 Ini:odustion 1.0 Pla~t Desc"i~tion 2.0 Definitions 3.0 Authorized ;',:aterials 3.1 Nuc18iJ" ?~el 3.2 Unirradiated Sou"ce ~aterial 3.3 Calibrition, Laboratory Standa"ds and Test Materials 4.0 Safety Li~its 4.1 Radioactivity Cont8nt of Gaseous Effluents 4.2 Radioactivity Content of Liquid Effluents 4.3 Storage Canister Loading and Spacing 4.4 Dissolv8r Charging 4.5 Feed Solution Conc8ntration 4.6 Fissile Isotope Conc8~tration in Solvent Extraction 4.7 Extractant Concentration 4.8 Uraniu~ Product Solution Storage 4.9 Plutonlu~ Ion Exchange Operation 4.10 Plutonium Product Solution Storage 4.11 Rework Evaporator Solution Concentration 4.12 Solid Radioactive Waste Burial 4.13 C,lUStiC Concentration in Carbon St8el \Vaste Storage Tanks 4.14 Exhaust Filt8r Differential Pressure 4.15 Evaporator St8am Pressure 4.16 R8spiratory Protection Equipment 5.0 Minimum Conditions for Operation 5.1 Effluent Monitoring 5.2 Process Instrum8ntation 5.3 Ventilation 5.4 Spare \'last8 Storage Capacity 5.5 High Radiation Area ACC8SS 5.6 Contamination Control 6.0 Surveillance 28quirements 6.1 Boron Raschig Rings 6.2 Sump Alarms and Eductors 6.3 Waste Storage Tank Pan Instrumentation 6.4 Emergency Utility Equipment 6.5 Air Filtration Equipment 6.6 Dissolver Dilution Air 6.7 Boric Acid 6.8 Blanking-Off and Locking-Out 6.9 Wat8r Activity Alarms 6.10 Poisoned Dissolver Baskets 7.0 Administrative Requirements 7.1 Administrative Requirements (Change No. ll)
These Technical Specificati~ns identify the significant design features, operating procedures and operating limitations which are considered important in providing reasonable assurance that the facility will be operated without undue hazard to the health and safety of either the pu,)lic or plant p0::-sonnel. The Technical Specifications have been grouped in seven sections whose purposes are described below. A summary description of the processing facility is provided in Section 1.0 to aid the presentation of the Technical Specifications. Details of the facility layout, plant design, process, equipment design, methods of protecting plant personnel,- methods of protecting the public and plant operation are presented in the Final Safety Analysis Report for the ;:uclear Fuel Services Fuel Reprocessing Plant. Technical terms which arc commonly used at the processing plant but which may be ambiguous are defined in Section 2.0 in order to clearly indicate the intent of the various Technical Specifications. The types and quantities of source, special nuclear and byproduct material which can be safely stored and utilized at the plant are identified in Section 3.0. These nuclear materials include irradiated fuel, unirradiated fuel for checkout or processing operations, calibration sources and laboratory standards. The limits established in Section 4.0 define the boundaries of safe operation yet permit the flexibility essential to chemical processing. The* limits have been set above the values required by normJI operation but well below the values at which an accident could occur or th"! public safety could b"! jeopardized .
111~)4~ Unli.~C' <i nuclE:ilr r(;actar v;rlicrl is desisn(;d to oiCcrate in a critical region, a chemical proccssinJ pJJ:lt is design'::! ane! oller-,d.crJ in such a way ,t as to remain subcritical at all tim0s. No single malfunction can lead rapidly to a critical incident; there is sufficient caracitancc inheront in the process to assure an extended time period before the limits for safe operation arc
-exceeC:i?d.. Secondary controls arc installed to provide componsation in the event of the failure of a primary control. In addition, administrative controls are imposed to further assure the safe operation of the facility. For these reasons, if the specifications in Section 4.0, other than those for effluents are exceeded, shutdown is not mandatory. If such an occasion arises, plant operations may continue in a "ready condition" until normal operations are restored; however, if during this period there is any occurrence that would further reduce the margin of safety, an immediate shutdown is required. If the specifications for gaseous effluents or liquid effluents are exceeded, process-ing operations will be shutdown and immediate corrective action will be taken.
The specifications included in Section 5.0 set forth minimum conditions for safe plant operation. If specifications for monitoring gaseous and liquid effluents cannot be fulfilled, the operations which could cause a release of radioactive effluents must be shutdown, with the exception of the main venti-lation system which is normally operated until the problems are corrected. Other specifications in Section 5.0 indicate primary and alternate conditions which may be fulfilled. If the alternate condition is in use the operations shall be considered to be continuing in a "ready condition." If neither primary nor alternate conditions for a particular op~ration can be fulfilled, the operations shall be shutdown with the exception of the waste tank off-gas system, which must be in operation while appropriate repairs are made.
lllQ45 but which are desirable for a defense in depth if a primary safeguard fails. The lone exception is Specification 6.1.1 requiring surveillance of tho boron glass Raschig rings which are a primary safeguard in the high enriched uranium product storage tanks and the off-specification plutonium product storage tank and for which due regard is given. The other specifications in this scction focus attention on controls which, while not primary safeguards, arc of sufficient importance that i~nediato and continuing action should be made returning the failed component to service. If inspection required by Specifications 6.2 through 6.10 reveals the inor~rability of any of the specified equipment, plant operation may continue under "ready condition." Section 7.0 identifies the administrative requirements, i.e. organization standard procedures and reviews, deemed necessary for safe operation.
Page withheld as containing Export Controlled Information 189
Page withheld as containing Export Controlled Information 190
- llla48
/.0 2.0 DEFli!ITIO::S Ter;n Assembly A group of elements or subassemblies combined in a structural unit. The asse::1bly is usually that fuel structure which is removed from the reactor as an individual unit.
Area A portion of the plant which is dc~cribed by physical boundaries for identification and communi-cation purposes. Blanking-Off The insertion of a removable barrier to flow in a pipe. Campaign The processing of a defined amount of similar nuclear fuel under a specific Letter of Authorization and Run Plan with a material inventory at the beginning and end. Concentration Control A technique used to assure nuclear safety that limits the concentration of fissile isotopes in process and product solutions. ( Favorable Geometry A geometry which is nuclearly safe for all credible concentrations of fissile material. Fixed Poison Tanks A tank or vessel equipped with neutron absorber that will not drain away, i.e. borosilicate glass Raschig rings or boron stainless steel Raschig rings. Fissile Material The fissile materials are uranium-233, uranium-235, plutonium-239 and plutonium-24l. Gross Count Total alpha, beta or gamma radioactivity not classi-fied according to specific isotope. Locking-Out Fixing a control switch or valve handle in either the opened or closed position by one or more pad-locks or seals. The lock may be removed only by the originator or a supervisor of equal or higher authority. MPC The maximum permissible concentration of radio-activity in air or .water to which an individual may be exposed for a specified period without exceeding regulatory limits for radiation protection. (Change ,:0. 11)
111J49 A f:1aio::-io! ;-;~."/~rIJ a h:gll p:-:<. -;:}lli ~:." :0:' cap1.u::n'j ncu~:<'j;-IS, 0.g. b:;rol1 ond c:::i:,,~u:;:. ROiJdy Condition A te~?o=ary condition of oporJtion using prescrib~d alternate instrumentation and controls or addi-tional administrative sc1fcgUZl!"ds while intrnediate action is being taken to restore normal operation. Routine Entry Area A plant area to which entry is routinely scheduled for at lea~t daily. System An integrated series of equipment and plplng in which a specific function or operation is carried out. 10 CFR 20 Title 10 Part 20 of the Code of Federal RegUlations which specifies the standards for protection against radiation. U-235 Equivalent A method of evaluating fissile material on the same Concentration basis. The formulation is not applicable to systems that depend upon geometrical control. U-235 equivalent concentration (g/l = 1.61 x Pu concen-tration (g/l) + 1.08 x U-233 concentration (g/l) + 1.00 x U-235 concentration (g/l). (Ch3nge 1-:0. 11)
111~50
. 1 This specification limits the discharge of Kryplon-SS, Iodinc-131 and radioactive particulates from the plant stack.
To provide reasonable assurance that ground level concentraLions of radioactivity occurring off-site fro;1I the plant releose of <.tic-uorne radioocti-vity w:l1 meet the USAEC standards (Ii tic 10, Part 20 Fcde::-al Code of Regulations) and the guidance values established by the Federal Radiativn Council. 4.1.1 RADIOACTIVITY RELEASED mOM THE STACK SHALL NOT EXCEb):
- a. KRYPTOi'J-85 3.9 x 105 CURIES PER r.:Oim*1
- b. IODINE-131 3.3 CURIES PER YEAR
- c. PARTICULATE 2.7 x 10 2 MILLICURIES PER ,',:ONTH (gross alpha plus beta) 4.1.2 NO DISSOLUTION SHALL BE INITIATED UNLESS AN AVERAGE V;Ii:D VELOCITY OF 2 MILES PER HOUR OR GREATER SHALL HAVE PREVAILED AT THE TOP OF THE STACK OR AT THE TOP OF THE PROCESS BUILDING FOR THE PREVIOUS 30 MIilUTF:S.
The discharge of radioactive effluents from the plant stack is discussed in paragraphs 7.6 through 7.9 of the Safety Analysis vlhere it is shown that the significant radioactive effluents are: Krypto~-85 for radiation dose from airborne radioactivity, Iodine-131 for ingestion of radioactivity via the milk chain, alpha particulates for inhalation of radioactivity and beta particulates for radiation dose fro~ radio-activity on the ground. This analysis was based upon a design batch of fuel (20,000 megawatt-days per tonne with 150 days cooling) and ave::-age meteorological conditions (5 x 106 cubic meters per second dilution) expected for the site. The resultant limitations of Specification 4.1.1 are conservatively assigned for adequate protection of the public and may be revised based upon the results of meteorological and enviro~~ental s tud5. es. The Krypton-3S content of a design batch of fuel is 6,300 cu::-ies. The dilution required to reduce the Krypton-85 concentration f::-o~ such batches to 3 x 10-7 microcuries per cubic centimeter, the ~r.r.ual average maximum permissible concentration in unrestricted areas, is 4.4 x 105 (Change' No. 11)
CU:.I! C ::-:'~'L':<:,"~', p*:.r S(:c'J;J:1, i .c. l'.:'~l::' t~~:Jn Oi:-:-t.0:-li.. !-". 1..:, .. : ,J'/C:c.:g(: c::':olian diluLion ,_,;::,.;'ct0d. The' Jirli1..cJi.ir)!1 on Si,,:,i~icaUa:1 '1.1.1 for K:'ypton-~:') release plovid0S os~~~~~~0 tllat acc~;:t~i)l~ annual ave!~g~ conc0nlration~ will not be exceeded off-site. The lodlno-131 content of a design batch o~ fuel is 1.8 curies. Off-ga~ treatment is provid0d to roraove 99.S porc'2:1t of tile iodine in a batch; therefore, only 9 x 10- 3 curies of Iodin0-131 would be released. If this amount of Iodine-131 we=e dischargcd each day (3.3 curies per year) an average dilution of 1 x 10 6 cubic meters of air per second would be required to maintain pasturage conditions consistent with the guidelines of the Federal Radiation Council for milk fed to children. This dilution is about
.qne-qfth}he average aeoHan,dil,ution E'!,xpected at the site. /.:ilk produced jV" "a.t::-the~dn;,,*si-ite ('fa:'rm--ancl' atn'cignbb"rin'g-:f'ar'ms is routinely tested for "
lodine-131 to assure that adequate dilution is provided. The limit for particulate release is based upon the average annual aeolian dilution reducing the off-site airborne concentration to less than 2 x 10- 14 microcuries per milliliter, i.e. the maxirnu~ permissible concentration specified in 10 CFR 20 for unidentified radioactivity in unrestricted areas. This limit is much morc strihgent than those (6 x 10- 14 for Plutonium-239 and 2 x 10- 12 for unidentified beta emitte~s) corresponding to the most radiotoxic materials actually present in the effluents from the processing plant. The wind velocities recorded in the plant's Control Room will be used to determine compliance with Specification 4.1.2. The wind velocity at the top of the stack will be the primary instrument; the wind velocity at the pro~~ss building roof will be used if the stack instrument or its recorder are inoperative. An acceptable wind velocity will be deemed to have existed in the last thirty minutes if during this period tile area of the wind velocity trace above 2 mph is greater ,than the area of the wind velocity trace less than 2 mph; ~,p,: ~ 'v"
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(Ch;]nge No.Il)
111~52 4, ** This specification establishes the upper limit to the raaioactivity that may be contained in liquid effluents. To limit the radioactivity in Cattaraugus Cree!: at any time to a safe concentration. S')(~ci fication 4.2.1 BATCHES Of LlQ'JI[)' v'!ASTE DE1T2!.iWEO BY i,iEASUilEl.;EiH TO COiHAIiJ LESS TflAN 3 x 10- 7 MICflO:UR1.ES PER i.1ILLILITER GROSS ALPHA PLUS GiWSS BEl"A RADIO"'.CTIVITY ,\lAY BE DISCHAflGED TO TIlE EiJVIRON!'.iEiH VIITHOUT ROUTI1lG THROUGH THE STOR.-'.GE LAGOONS.
'/
4.2.2 NO MORE THArJ 96 CURIES OF UNIDEtrl'j:~FIED ALPHA PLUS BETA ACTIVITY OTfiER THAt*) TRITIUi,l r,[I1,Y aE TPAi:SFERRED TO THE STORAGE LAGOO::S DURWG ANY CALENDAR Q'JARHR. TRANSFEt{S I,IUST B,E IN SEPMU,TE BATCHES \'"lICH M,\Y NOT COiHAIN ,',iOEE THAN 6 CURIES Of UNIDENTIflill ALPfiA PLUS oFf,'\ ACTIVITY AS DETERMINED BY I,IEASURFJ,!ENT. 4.2.3 LIQUID V:ASTE RELEASf:D TO THE CATTARAUGUS CREEK FRO;,; AU. SO:JRCES O:-J THE SITE SHALL BE REGULATED SO THAT (A) THE CO;;CEtHRATIOi: OF R/>,DIO-ACTIVITY AT THE r,iO:UTORING STATION m CATTARAUGUS CREEK SHALL i*)OT AT ANY TIi,iE EXCEED TVIICE THE C01\CENTRUION SPECIFI t:D III COLUMN 2, TABU: I I, APPENDIX 3 OF 10 CFR 20 AND (B) THE AUiJUAL THiE-AVERAGE COi!CELiTRATIO;l OF RADIOACTIVITY IN CATTARAUGUS CREEK SliALL NOT EXCEED THAT SPECIFIED IN COLUt.iN 2, TABLE II, APPEiJDIX B OF 10 cm 20. Title 10, Part 20 of the Code of Federal Regulations (10 CFR 20) specifies the maximum permissible concentration (r',iPC) of radioactive effluents to unrestricted areas. The MPC for Strontium-90, one of the most radiotoxic isotopes released in the effluent from an irradiated fuel processing plant, is 3 x 10- 7 microcuries per milliliter above natural background. The batch limit of Specification 4.2.1 assures safe releases by conGerva-tively assuming all the radioactivity is Strcntiu~-90 and by ignoring the natural radioa~tivity content. Specification 4.2.2 provides in-depth control to the release of radio-active effluents. Radioactive plant liquid discharges are collecte: batchwise in a plant interceptor ',Irere the liquid is sampl"d and analyzed. Activity content above the 6 curie limit is either returned to the plant (Chan:;o ::0. 11)
111J53 "t ** -: r for (',!: L: ,', :--:*~*c'::,:..lr<.! 0::- dl1"c'ct*.:.:i to C: hi0:~ le'\/..:,1 '::J::r> s.t('~*JJr' '!..~:-I~:. AcLivily C'-j:J\.':':j;~-, ~),: 10':: "Lh*') ::.ix :t:: i,~ li:-::).t ~:;y 00 t:'ans~e:-rr:i t.O str.)!'a:'F: LJ9Jon5,
~~-~licJl c~~sist o! thrae ~r!)2:Jt0 l~g~ons in SO:i05 ~it~ a tot~l ca~~city of about 5,000,000 gJllons, ;,rior to controlled release to Cattarauglls Creek. The ninety-six curies allo~ej each quarter for transfers of radioactivity to the storage lagoons is less than the annual discharge allo~ed to the Cattaraugus Creek even if all tho radioacti vi ty ',':'::5 Strontium-90 and is only about t':lenty percent of allo',',aole annual disch3rge corre,,?onc.iing to the creek flol'ls and the isotopic co~positions of discharges experienced during 1967 - 1968.
Column 2, Table II, Appendix 8 of 10 CFR 20 specifies the maximu~ permissible concentration of radioactivity in. liquid effluents to unrestricted area~; these specif:'<:!d conc,'ntrations are annual time-averaged concentrations. Specification 4.2.3 re:ognizes these limits as appropriate for the NFS facility but imposes additional safegu~rds by requiring the concentration at any time be less than twice the 10 CFR 20 limits. NFS intends to provide additional safety by discharging well below the limit.
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(Chance No. 11)
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lllQ~3 This specification e~tabli=h'<, tho liroits to 0') oosorvod in the transfor and storzge of solid radioJc~ive ~:Js'l~ n1oter"ial ~esulting fro~ t~la separation, in th0 ~eproc~3sin~ plant, of n~c10ar mat~rial frc~l nuclear fuel. This specification also applies to the burial of conta~inated plant equipment if b~!ricd in tl1C same area as separation waste. Objective To assure retention of activity from buried waste. Spec i f.i ce,t 01l
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4.12.t RA!):;:(',TfIVE SObIn PROCESS WASTE G::~jERATED 3Y THE OPEP.,,\TIO;,! Of l THE PLANT SHALL BE 8URIEl CO:,;PLETELY i'lITHW SILTY TILT.. Bf-FO":: A r~u: EXCAVATION IS USED, IT WILL BE INSPECTED TO ASSU::lE TfIAT IT IS fULLY WITflIN THE SILTY TILL FOR;:J\TIOI,J. BURIAL SHALL 3E RESTRICTeD TO THE PLANT AREA DR/lINED BY QUA::l2Y CREEK AND ERD:,~>\N BROOK. no BURIAL OF \',:"STE SHALL BE NEARER THAtj 100 FEET TO THE CREST OF THE Det=ILES IN ;-"ICH QUARRY CREEK AND ERD;/Ail SROOK FLO"I. THE I,; ItE r,;u:,; COVER OF SILTY TILL OVER THE \'IASTE SI-I,\LL BE [,OUR FEET EXTENDI,JG BELOI'! nlE TOP OF THE Ui:DIS-TURSCD SILTY TILL SBATUi',:. SUITABLE t,lEAr.1S SHALL BE PROVIDED 1i::LJ MAINTAINED TO MliJIlnZE EROSION IN THE DEFILES, SaV!EEU nIES:: Di'FlLES Al,ID BURIAL AREAS AND OF THE 8\RTH COVER AFTER THE EXCiI VA TIOUS HAVE DEI! FII~ALLY BACKFILLED. 4.12.2 THE LOCATIOn AT \'['-IICH RADIOACTIVE SOLID i'jASTE ARE BURIED Hi ACCOKDAnCE \','ITH SPECIFICATION 4.12.1 SHALL BE /.:J\"KED \':ITH COI~C;.;crE CAIRNS. A PLOT SHO\'/ING T'lE APPROXIiAATE LOCATIO;~ OF ALL \'j,;STE BURIED SHALL BE i,'L4ItHAINED ACCO;.:?AiHED BY AN INDEX DESCRIBING THE GEi;ERAL TYPES OF I'IASTE BURIED AT EACH LOCAnmr IiiCLUDING THE DATES OF BURIAL Ai!D CLOSURE. TO PREVENT THEI? LOSS, DUPLICATE REC02DS OF BURIALS SHALL BE Ml\HITAINED IN SEPARATE LOCATIOi'IS. 4.12.3 SOLID R.ADIOACTIVE 'NASTE ro BE BURIED SHALL BE PLACED 11; PACK,\GES WHICH SHALL PREVEm DISPERSIOII OF CONTEi'ITS AND P"EVEiH COilTAm;:ATIO:: OF HAiJDlERS. IF A PACKAGE IS RUPTURED ;{..JE,1 PLACED I:'; THE TREi:CH, EARTH OVERFILL SHALL BE Hj',:EDIATi:LY PL;l.CED OVER THE RUPTURED PACKAGE. NUClear Fuel Services operates two \'Iaste burial areas at the \':est Valley site. One area is for plant generated waste and is licensed undpr the regulations of the U.S. Atomic Energy Co~mission. Tho other area is (Change ;';0. 11)
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.ola:-lt and is 1 i:::':<:;;,:~d U:I"~':": t.:'.~' rC0'JIJLi.J:ls 0: i..hr:.' Statr: of ::'~'.' Yo~*k.
This spcific2tio~ aprl:~S te, tho b~~i2! area st:bjccl to US~~: licensing and regulations. As pointed c'-.l'L in ?2.rag:'~.::,l1 ::.;;~ 0: SJ.:-:*t, .:. nc:lysis, tho loc2.tion specified for tile bu~ial of S0iJaration ~:ast0 is of such a favo~abl~ geological fO=~I~tion that any radioacti*.*~ty in tl1e g:ound ~ater would eventually appea: in the spanning 5trcc~s, ~;ich a~0 subject to monitor-ing, and nO'.;here 01sc:. L '\' .' \'lIs discussed in pa:'agraphs 4.;:0, -/.14, 7.15, 7.16 and 7.17 of the Safety
;,S~ \J. ,.' , ,Analysis, the ion exchange a;::1 per,:lcability data for the soil in \';hich
* /, , , ' t h e radioactive .,.:astc is to b: buricd indicotc thot the radioactivity
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will be rct'li'lc:.J in the in:c:)s,::Jtc viCinity of the source. Fu::-ther, t.1e 1
*., - '. \;~ low permeC!bill.ty of th'~ silty till ,.... ill delay any possible S(,2pogC so i.,\.'0.~ X, greatly th2t the longest Ii v.:,:: ruUlcniu~, isotope, an eler:v'nt \':hich is not
'"\ j bound as v/cll by ion exchonY2 pIopcrti c:s of the so~ 1 os the other
, significant rluclides, w0uld unJc:rgo nca::-ly complete radioactive decay
~ before it could traverse 100 fcct of this soil to an adjacent water
...~ . . course. This speCification requires that at least four feet of silty
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._.; .,', '*The provision of r.:nkC'Ts and records of burial. on stat(' o',':nC'o property r \~'
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/' <~of radioactivc ;;:aterial.
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',' (. , ,0 The I'iaste transoort vehicles are surveY0d both before and after usC' to
;~~~ ~~ prevent contJDl~~tion and mini~iz0 rndiation cxposu~e of tran3port
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Exceeding this specification ~Juld merely increase the chance that
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radioactivity might escape tha burial area. But the chance that the rate of escape would exceed the established discharge limits is very
..,.. small.
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This s:Jccificotic'(1 cs1..:.:)1.::.:1C'-:" 1::',: -:..~. 10:: the r*,~.i-llr,.lU:-:1 concentration of CE!ustlc in th*~' c<1rb':"1l ~,:c":J ~':,'1:L(' ;j~0.:*.:tJC* "La::Ls. Oo-~cctivc To assu:-c UlrJ.t J~!~..:~ liq~Jid '::*.:~-tc irJ tho c.)~~)O;l ~,-t.(\cl '//astc storage: tanks shull be r::::.i_rJtJ.inccl }iJ J.l:::ll.inc c:'n~:;L!o:i at all times. 4 .13._ 1 EXCE '-'C:S C:"~'l'-C !-\u;:, 1 ("-' ::;"
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.. ' ;.;:" (R) t AT LEAST "J/V ~Cl OiJ THE S;\:,:;:: 31\,313 Ui:TIL TI'I: TOTrd, VOLUj,'c or WTRODUCED V/;,STE EXCEEDS 100,000 GALLQ;-iS ;'.::D (c) AT LF/,ST 1% ON THE SM.iE BASIS AFTEH THE VOLUi,:E Of IiiTRQDC:CED i':ASlE EXCEEDS 100,000 GALLO::S.
[ To minimize the corrosion ::,ate of the carbon sted high level liquid waste storage tan::s, the no::'mally acidic liquid wastes are neutralized prior to trarisfe::, into the tan':s. In addition, excess caustic is maintained in the tanks to prevent corrosion resulting from any inad-vertent Clddition of <tcidic ','I<Jste. The ::,rocedl1::'e for n1<Jintaining excess caustic is as follow5: the waste storoge tan~s will be initially filled one-third to one-half fuB of viator to v:hich \'Iill be <Jdded sufficient caustic such that the addition of neutralized waste with a 1% excess caustic will result in at least a 10% excess caustic in the w<Jste storage tank for the ~i::,st 10,000 gallons of waste and at least a 5% excess caustic for the next 90,000 gallons of waste. One percent excess caustic will be maintained in the tank fo~ w<Jste solution additions above 100,000 gallons. The amount of caustic could be reduced considerably still leaving an excellent margin of safety. If the pH of the solution falls belo',', 7, a rapid increase of the tank corrosion ;"ate would result and failure of the tan!: could be exp0ctcd. If this were to happen a very serious financial loss would occur but, as discussed in paragraphs 7.24 - 7.29 of the Safety Analysis, tile general public would still be protected. r (Change j;o. 11)
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111067
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t; * ] , This spoe] Ilc'Jtion C'"t;J;'~: ~lF'c th,) requi:C'rnenLs n0U'Ss,Jry to protect plant po~~orln01 f~o~ Ji:Lo~n~ concont~ati0n; n~ rQdi0~ctiv~ nl~tcrial exceedin~ th0 mJxim~m p~:~iS5ib10 concentrations of the 10 CFk 20 for restricted arcas. To assure that plant porsonnol will not inhale excessive qLlantities of radioJctive material. SDecific2tion 4.16.1 FULL FACE llESP IR;',TO;:(S .\FPROVED FOt'( RADIO:\CE VE r.~.l,TERIA LS Ui:iJEH BUREW OF r.i~;'JEc:i, SCc:::OUL;:: 2H3, SHALL BE USeD ':.'ieRE nie CO;:CEi:TRATIO:: OF AIRSOR,!E c:"\DIO;\CTIVITY ;\i:1ICUATED DURIiIG OCCUPi\i;;:;Y I.~W EXCEED 40 i:."C-
!lOURS 3UI \':ILL ;;OT EXCEED 800 i.:rC-HOUHS.
4.16.2 SELF-CONTAINED B~\Ei\THING APPARATUS SATISFYI;;G THE BUREAU OF MIr~ES 5Ci:E0ULi: 13 KeQUIRE:.iu;rs OK SUPPLIED AIR RE5P1::,\TOR5 SATISFYll-:G THE DUHE\U OF !,iIf:E:~ SCHmuu, 19 SHALL BE USED Ii! AT:.:()SPiIFRC:S \*.1IFRE TllE COj,:C'::;;Ti~ATlOi'i MiTICIPATEiJ DURH!G OCCUPANCY i.i!\Y "XCEED 800 i.;PC-IICU'iS. 4.16.3 PiUOR TO EACH GlrRY WTO A comAi.iINATED flT!.:OSPHcRE, IiiDIVIDU,.l,LS WEARH:G ,lE,5PIRATOKY PROTECTIOiI SIIALL CHECK THE i::ASKS FOR FIT Aim LEAKAGE. 4.16.4 FOLLO':/ING Ei\QI USE', R;:SPHiATORY F'HOHCTION ,'.~I\SKS SIIALL DE RETURnED em DECOmAt.:WATl 0:: u:mER APPROVED HEALTH AiD SAFETY PROCEDURES.
\'idE!: THE CLEAiHNG M:D REPAIR H*\S BEEN APPROVED 3Y HcALTfI Ai:D S..l,FETY PERSOi'11!EL, n,\SKS SI-IALL F1E PACKAGED IiIDIVIDUALLY IU PLASTIC BAGS AND DELIVEREO FOR ?EUSE 'dITI! CLEAi: CLOTHING SUPPLIES.
4.J6.4.1 MASKS S!!ALL ~JOT BE RELEASED }-OR ReUSE IF Flxm RADIOACTIVE CmiT!'}.ir:UITIO:-i EXCEEDS 100 CPM BETA/PR03E AREA OR 100 CPM ALPHA/PROBE AREA. 4.16.4.2 FILTER CANISTERS FOR r',L.l.5KS SHALL i:OTi3E RELEASED Ir (A) sr:'EP.RABLE Cm,TA!.H:::"TION EXCEEDS 50 DPI.l ALP1-iA/lOO c:) OR 500 DPr.; BETA/IOO c,\;2 OR (8) FIXED RADIC.':;CTI'lE CO:.TM.:I;J:\TIOii EXCEEDS 500 cpr.~ 3ETA/P203E AREA AT ONE INCH. The 40 ~?C-Hours concent:ation is the concentration of airborne radio-activity that a worker could breath throughout his work week and not inhale excessive radioactivity. NFS requires that if plant personnel (Change ~:o. 11)
111D58
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For usc in airbo:.nl::: cO:-:C*::'"lt:::'Clt!0nS ~:~co*:?c1lng 8,,)0 !.:~}C-hours, r:i=S requires the usc of s'J;.... . ;>li*::J ai:- cq'Jlp:,:-:'nL *..:::ich is a;:l:J':"'Jvcd by th,_\ ::;ur~a1..! of l,iines, a :,cca9:l1.::~d au-c:l'J:-lty ih ~cs:)irc1to:-y p:-otf'lct.ion. The contamination limits of rOlls~' of rTldsks awJ mask canister5 are con-sistent witil the limitations for uncontJ~inat0d plant areas (Zone II) and are expressed in racii.Jtion un5ts used Jt the plant. Specificat~on 4.16.4.1 is based upon (1) a 20% counting efficiency and 50 cm 2 probe area for betiJ monitoring and (2) a 50;0' counting efficiency and 75 cm 2 probe area for al~ha ~onitoring. Specification 4.16.4.2 is based upon (1) a mJsk area of 17[; c,~? and (~) a r,linimu,;J of 2,500 cpm per 1 mrad/hr. (Change lio. 11)
111069
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~' . ., Th1.~; spcci~ic,Jtjo;"l icJt'~lti:_~,::s til,; '=<Fdr!~':,r!t, frequency of ~,)rnpling and th0 un.J).y:"c:j :,~c:ui.:*cci [0: ;:111;'"J::(.:. in~l l'.:.ldlClJcti.v,_\ gaseous and liq~Jid p18nt 0fflurn"Ls. 0)) i octive Soecificdlof"\ 5.1.I \','!r:::::\!?~ l.IC~iJIU l,,: LJTS':Hi'.;:~~:J F!'(l':,: niE STO!~.'\GE LAG001!S, to. RUES:'::~[;:rI'J:: S/,,',:?U: ~;:::,U, :-;" cv:n;,;UOUSLY ,'JITIIDHAW,! BY TfiE CATTARAUGUS Cqi,S( S,*\,'.:?E;:;. I\T LE,ST EV;:,:Y S::':VEi; LJAYS, II COi'.iPOSITE OF TflIS SAI,:PLF. SHALL J,: Ai,,\!"YZci) FO~: E:lT 1 C;:,:, G20SS ALPHA A;;O GROSS BF.U, P"\DIOAC1 IVITY. IF liIE CWTI;;JOUS S,\;,;PE,; IlECOi.:ES H:OPE?"~3LE, UP TO 2,000,000 GALLOi-lS
!i...,Y SE DISCfL\2C::J r"O;,\ Tjii~ U.GOOi:S IN Mil' Oi!E YEAR PERIOD PHOVIDED C!\TTAF':,\~iGUS c:;;:>}( S,c,!,:?LE::; /,?:: COLLECTED rlEA? niE SA,*,iPLE? LOC/ITION AIJD Ai*,',*.L'[hi) iY~';.i:::C; Er\Cil L!\~O::;:; DISGf!'\;;(ji:: 0" FO;! EACf! 100,000 G,\LWi';S or D1,;C((I\,:(;[;, ':,;!ICfieVr::1 RESULT~; It: Tl:::: GREATER SA!.:r'LU!G Ff~fQUEf.!CY.
AI!id.YS::S SI:;,.U, :3C: SU['FIC~EhT SE;;SITIVITY TO APrr,i\lSE COi':r:Of,;,;:I;:CE ';IITH SPE:CIFIC/\TIO:: 1i./..3 !\:Ji) :,:W rr:CLlJDE ,\SS,\Y OF SPECIFIC ~lUCLI[JES. 5.1.2 THE Sr..l.CK S;.}:PLER LOCI\TED Bi,SIDE THE STACK \'f.-rrCH COLLECTS A REP,,[SE':TATIV:= $,:\,',:fJLE Ot: THE STACK GAS SHALL BE IrJ OPER..UImr AT ALL TII.:r:S /Ii:!) Tft::: S/\!.:;'lLF'S COLLECTED SHALL BE ANALYZED AT LF.AST EVErlY Sf V,,;: D,\YS TO VEi'{IFY CO;:i:Qii,','J':'*;CE \';mr TfIE RELEASE LHHTS FOR 1-131 MiD PA~TICUL\TE RADIOACTIVlTY. IF THE STACK SJlXPLER SHOULD BECOo',iE INOPERATIVE, L';,".\wIATE REPAIR SHALL BE HJSTITUTED TO EXPEDITE THE RETURil or: THE STACK SAI,li'LE:1 TO SERVICE MiD THE STACK r,:otHTOR SHALL DE USED Ii~ Tile HiTERI1.i TO Di:lc21,;r;.iE PARTICULATE AND I-131 HELEASES. THE STACK GAS SHALL BE COr!T WJOUSLY ,":O;HTORED FOR 1-13J., KR-85 AND PARTICULATE ?.AD 10ACTIV ITY. IF THE COnTINUOUS t:iOfJITOR FAILS, A SAt.iPLE COLLECTED THROUGHOUT EACH SHIrT SHi,LL BE AUALYZED FOR I-131 AND PAf~TI CULATE ?J,.DIO,;CTIVITY; KR-35 i:/,. Y BE C,~.LCULA TED FRO!;! FUEL BURtJUP DATA. About one-h2lf mile downstream of confluence bf Cattaraugus Creek and Buttermilk Creek, a sampling station withdraws a sample of the creek water. The samples arc collected and a portion is analyzed at least weekly for gross alpha, gross beta and tritium activity. Each month (Change No. 11) I I
111!J7D
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l'J~/):~'tC<;i' Z,): 'J!'OS, i< t- - ::J'(,, __ ;.1J[,; . .1 :!:--;~J ,:)t:O(jti~:**._~':\ -::-L.'1::'.!I..;livity. 1hc5C' r,riioJcti.vc: COrl:>:~;:_~Jt>:,;-.;) 0;:_" CC':*;i);J,**:*j tv t:~,~::- !*;,~.,;,.~'ctive ... n1e.xir:-ltrn pcrr:Jissiblc C0n(;*~:*jl::,J2..:.3.0:;3 to sho':: COnfOri;Jj:I'~(~' ~':it:l ~p,.:*cif'icJti{J:-1 4.2. The safilj.llcr li}~0 ,:Jil/ sue:) (*quipmc*nt is subject to r.l('ch~nical fClillJrc; th~:'!c[orG, a ]lr,litJ:cJ Z:~.,)U:T::' of inlcrmit-L~;nt So:tli1Ji.nS is pt:?I'- mi tt.8d in !-Jlace of th0 conU nuc'~Jc "";"[110r. Iociino-129 is present in such 10;( conc0ntrations in rlant efilu(;'nts that after dilution in Cotta2J~]~S Creek it cannot be detected by pres~ntly available analytical ~0thods; thorefore, the Iodine-I~9 con-centration in tho CatLorduC)U', C:-0(,:': is cal culated fro,~ the analyses of Lagoon 3 co;;]))05ite sa"liJl0 and the dilution of th0 lagoon discharges by Cattaraugus Creek. Gaseous plant effluents are sa~pled in the plant stack. For the stack sampler, air is drawn th~ouJh a particulate filter and an activated clliJrcoal filter to rOIll()V n "articulate and Iodine-l31 radioactivity. The sa~p1e5 arc removed fronl their location alongside tile plant. stack at least every seven clays and are analyzed to show conformance with Specification 4.1. j~)
~
For the stac;; monitor, air is dra'lin from the stJck to th,c U:Jpcr Extrac-tion Aisle '.':hen radiation moni tors continuously dets'li:lin0 the particulat0, Iodine-131 and Krypton-S5 radioactivity. The stack Monitor sign~ls an alarm in the control room when excessive gaseous radioactivity is released. (Chans'"' ::0. 11)
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111:]76
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This speci fj c;:d lon "u;':Jo: 2::c',; ill t<:'rrJCltivc~ t~J,Jt may b", llsed in 1 ieu of the control device specifinJ in 10 CFR 20.2J3 (e) (2).
To assure thilt personnel are ~arncd before they enter ilrcas ~Iere the radiation exposure pot",ntiJl may be significant.
SOGcifiC(ltioQ 5.5.1 W:KED DOORS S::'-'lLL li:: USED, ;'MERE FEASIBLE, TO COim~OL AD:,~ITTAI:CE TO HIGH RADIATIOii ARG\S \'i;iFRE i\~! l1:DrVlDU.'\L !.:IGST RECEIVE A DOSE IN EXCESS OF 100 i',m,URE:.: Ii') ONE HOUR. POSSE~;SION OF KEYS TO THESE LOC?','!Lr}ctin'! ~:~:-';*'.]i*.):i,jLr, Ol' tll,:, cont~:;1~n]t.!.0n ]'.:\/01 :s \':o:-n 2n~:
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This program recog iZ0S that periodically contt~ination will occur due to human or mccllan cal failure yet puts due emphasis on eliminating reoccurring contom natiorl .
- (Change No. 11)
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IllJ82 To as:?,'Jrc thc:t :::,'candLy l..:tj] ity E-C!lji~::,""'?;i~ r;0*::':::~'~.2r,/ fo!' cont:inu-::d f~ciljty Oi1C1'("ltj,JilS i£', m.:l~_ntJin(-'d in c!!1 o;)c:;Jb]c condition. 6.4.1 THE E:.:U:C;",,::;Y G:::,,,:.**.TC'f~ (30T-I), AIR COi.iPRESSDR (3lK-1!\) AnD TH " l:: C~O[ U -'.'~ .,....*.
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THE A'::JOVE cQUIP;:':;:T IS ;'Oi.:::~) '1'0 ~;E DEFICIEtn, Iiv1ii,EDIATE Ai-!D COiiTIiiUrr.:G ACTJ O>i SH.I"lI FE T,A,~(r:r! TO Hf,ClJfY TtIE COWITJO;,. THE NEXT CM,iPATG:! SHALL r:aT STArn U,'rI1L niE EQUIPr:iEiJT IS RETUiiNEfJ TO SERVICE. 6.11.;:> THE EQ'JT p;.:r::n LISTED Bn,O':1 SHALL DE OPEil,\TED AT LEAST Oi-r.:E EVEny Tfif1Ei,: i,;Orin,:=; TO Dl:TEF\:.aNE PEllFOri:.V,~CE FOR AT LEAST OnE HOUI\ UNI)!=R AN O?EilATIi'!C; LOi\D. ANY DEFICIENCIES \'IILL HE CORflECTEIJ AS SPl::CJb'IED ]:1 6.4.1. BOILER FEED PU,'.1?S 31G-2A A::D 3lG-28 BOILEI( DRc\FT FAr5 3lK-2 Ai!D 3lK-2A PI.Alff VIATER PUi.iPS 3;1G- 2A AND 32(;-::m 6.4.3 n:E QUi,,'rnIY OF DIESEL FUEL IN THE OIL STOHAGE TMIK (310-2) SHAlL, DURIi-:G lIOFF,:;"L C?:':f;'f1,TIOrIS, BE W\ IHfAI NED AT 8,000 GALl.ONS OH l,iOrjE; OF DIESEL FUEL. IF USED Dun INC; ABNORi.1\L CONDITIONS, o PERL', TIONS I/A Y CONTHiUE AS L01,!(; AS A VOr.ui,iE OF 4,000 GALWi,S OR GREHER IS MA INTA Ir!Ell. A VOLi~:*.iE LESS n,t\;J THIS LATTER VALUE VlILL REQUJf\E THE COI.i,',iEr!CEJ.:EN1' or PLM[f SHUTDO::i*; i';~!TC~i s: :ALL CONTHiUE UNLESS THE PRIr.1ARY FUEL (NATURCl.L GAS) SEHVICE IS RESTOHED OR THE rUEL OIL SUPPLY IS REPLENISiiED. Standby equipm0nt has been provided to enhance the reliability of util-ities supplied to safety equipment and devices. In order to insure satisfactory performance, the standby equipment is tested on a routine ba£i5. In the ev~nt of natural gas outage, diesel fuel has been pro-vided in sufficient capacity to assure normal operations for at least 10 hOUl'S. Unless ;':eather conditions are very severe, diesel fuel can be replenisilsci ~ithin 10 hours thereby permitting continued operations. The consequence of failing to meet the requirements of this specification is to ,cc1l,;ce thr? lev*?l of conficience in the operabili ty of the standby scrvicez.
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1110115 This spc'cific-.;clon cst~bJ.lc~I*;~) ar::-:-;lrdst!.(1t.J.V0. sttin-:.l~!Js fo~ the o~c!,",:!t!on of thc plant. Objective To pl'oviclc Don tld;;linisl.rzrLiv:_' :-,y,:t,-*:: C'::l:;odY~:-;J ;-;::In::J(J':-~1'i01 princip]cs of dcrnonstrotcd cffoctiv~.'n;.::.,:-; jil 2chi.:*\/in'j s(j!c*Ly of opc!'ation. Soecification 7.1.1 ORG.\NIZ;\TIO:!. FOr-: F:.' .. ~':::Sc,S 0:: !:clI1T".I:-n;JG SAFE OPER.*nIOl! ;,.:.:u CO~H'flOL OF THe FASILITY ,\::i) 0: i\TTE::Di\ilT ACTIVITIES, NUC:U:,1,R FUEL S;:R'JIS'<:, INC. SHALL PROVIDE ".~\::'.l;;:*.:::T OF TEF PLAin Tii?OUGI ;\il ADi.:I!:rSTp.ATIVE FRAMG'iO?'l( lii:;WDli:(;, BUT ,Jell LIi':iITE] TO, Tii:: FOLLO';m:G: 7.1.1.1 (, GEiJf:F;Al t':!\;:I\GE:~, !i.WH!Ci T!i:: OVER,\lL Rr:S?O::SIBILlTIES FOR ALL ACTIVITES I\T nlE PU,irr rr.:CLUJIi:G HEALlII Aim SAFETY, NUClEA:\ CRITICALITY S.*d'f.TY, MiD i\DliE:~::i*;Ct' TO THE LIJ'.;rrs I~I;D CONDITIOIiS SET FO?:Tfi Ii) THIS LICEt,IS". 7 .1.1.~ AN OPE::lAlIOi::.; :'.:t\!*,),\G::,':, REPccr HiG TO THE GU,Jr::l/d. r"~,\,,,\(J::~~ OR TO MI ASSISTAiH CiL;:cf:AL ::X),\GE!, i:lTfiOJT P,ESPOi!SWl LITY 1'0:: HEALTH AUD s;,;;~rY O~: '!'IUliHCi'.L Sf:2VlGi:'S, RESf'Oi!:';E;Lf: ;:0:, C(',::i-;Yi:\~ OUT PRODUCTIO;,1 ACTIVITIES Iii ACCORDi\:::::E 'i:ITH APPROVED P,{OC:::DURES AND ACCEPED HEALTH Ain) SAi't:TY STAi~i)"r:DS. 7.1.1.3 A HEALTH M:D SAFETY DIRECTO:-:, REPORTiNG TO THE GU:ERAL MANAGER OR TO AN ASSbTA~rr GEiJERAl ;:.:,!:,ICjE": mH!OUT R1:SPOi!::;lJILITY FOR OPERATIONS, RESPC,lSWLE FOP. MONlT02Ii*;G THE HADIOLOGICAL SAFETY OF ALL PLAi:T ACTIVIT ll:S AND FOR ADVISING ALL DEPA"T/.;t::JTS O(! RADIOr,(jGICflL SAFETY ;:LITTERS. 7.1.1.4 A TECHNICAL Sf.RVICES 1:;Ai,JAGER, REPORTING TO THE GE::ERAL MANAGER OR TO AN ASS I STANT GEi~ERAL j,::ii!AGER ;nTHOlIT RESPONS ISI LITY FOR OPERATIONS, RESPC::SIBlE FOR REVE,~ OF PRO?OSE9 CH;'.NG::S I,~ DESIGN VIITH RESPECT TO P.ADIOlOGICr\L .,\;'D NUCLEAR CRITIC/.L TTY SAFETY AND RESPOI'JSII3LE FO:~ ,\ COirrIi;~Al REVE;'; OF O?L't\TIOi~S TO ASSU:iE NUCLEAR CRITICALITY S:\':ETY. 7.1.1.5 A PLAm SAFETY CO;,::,:iTTEE, 2::POf(TI1!G TO THE GEi!E?.AL :,0\NAGER, RESPonSIBLE FOR 80TlI ?ADIOLOGICAL lJWCLEAR CRITICALITY SAFETY BY (A) R~....eVIE"1
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AlITHORIZATION AND E!.~ERGENCY PROCEDU:~=-S, (B) REVIHi AIm APPROVAL OF "ALL CHANGES HJ TH" PROCESS (OTHER Tr~,\i') THOSE PER,'.HTTED W THE LETTER OF AUll!ORIZ.HION OR OPERATING PROCEDURES) A1:D EQUIP:.:Ei:T DESIG:; AND (C) IiJVESTlGUIO;) OF A3i:OR;',:::'L O:CURRE:::ES ';:';D RECO:.:-
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l 1 ! I, li:(~:;:'~'~;:*'.L Sr:;-:',,'fC:_...: :.:.'.::'/~:'-:, Ti;~~ i:t':.r:i';: ;\~:.) :=';,:~i* .. ; Y li! .. ;_':1'C':~ /d~:) THE o~'r:'::\TIO:;S ;.'. :~.::. \!:;~::': O:~ THEI;: U>~i _;:::\T~.i .':"LT:* .. :::\T;~:*. ALL THREE ~\~E::,::3:~i~S O;~ Tl:Elr~ }\LT:::~~i!i.T~~; :.::j::;T l~r; }J:,:ESt:::T !i~ O:'<JL:~ TO CONDUCT OrFIClfl1. DuST ;:,::;5. 7.1.2 i','inlTE:: l'r,C'CEDc1c:LS s;:;,U, ;.or: 1:;,.I;:;;,l::::D U:::i::,i If:" O!JL~\LL j)I~:::CTION OF THE GErJ:::::,';L i:f.;:,:'.GE:: CO'Ji:::'.L:'.; ie,::: 7.1.2.1 PREPAHi\TICil, APPROVAL l,;:') ISSlJfI;::" OF :\1.1. OPERATING INSTRUCTIOi:S MiD CHM::;r:S IIIF.Ht::TO, I::CLUDI::::; ,lllT iiOT Ll,.:nE!) TO, STAND1\;W O;'EfiATH,C; P~:(iC':i)Uc:ES, LEI TL,:S OF AuniO",Ti':ATIOil, HUll SHEErS, SP[CI/\L \':0=:1< pr:OC::DU~ES I;',J EXTENDED v:o~;( PRocmUHi,S, Vn!EHi:: NUCLEAi{ CRITICi\LITY OR R;,DP,nOj*: SArETY AilE CO;,;SIDEf'JITIO!:S. 7.1.2.2 IiiVESTIGUION OF A13I]O['(i,;;\1. COi;oITIO;~S ;,:-;ICH I1)VOLVE THE PROCESSH!G, HA,'JDLlilG Oil STORAGE OF FU\DIOi,CTIVE ,':ATERI':d.S A1lD V:r!ICH AFFECT NUCLEi'-" CRIi IC,\LTTY OR RADlt.TIOiJ Si\~'ETY. 7.1.2.3 ACTIONS TO BE TAKEN IN [VEin or: ,~.:.) Et:h,:GU1CY INVOLVIl~G RADIOiicnVE [1)\TEfiiAL. SUci-! ACTIOi:S TO Ir!CLUDE, 3UT ,JOT BE LlII.ITED TO, SHUTDO':iil OF SPECIFIC EQUIPI,;Ei.fT, Ae'T I V;'.TIOi'! or: THE H,cRGEUCY PU\N, SlJi:;.:Oim~G OF OUTS IDe SUPPOET Ai'ID RE- E1HRY TO Tti::: ACC IDG!T AREAS * .( 7.1.2.<1 PERFORI,~,\i:CE OF PERIODIC REYIE'ilS OF O!'ERATIt,:G PRACTICES, REco:ms ALD AUDITS. 7.1.3 PLMIT OPERATION. i'W~flERS OF THE PRWUCTIO:l OPE:ATING STAFf SriALL HAVE t\ THOROUG'I TRAINING IN TilE PROCEDURES GOVE:2;,;I:,G THE \';O~~t~ FOR \'1iIICl! THEY ARE RESPOi\)SIllLE. DRILLS SIIALL BE HELD AT U:'.\ST YEARLY. A CURRf:i*rr SET Of OPERATInG PROCEDURES SHALL BE PROVIDED IN AREAS ','MERE CONTROL FUI,C'T lOilS ARE P ERrORIf1ED. 7.1.4 DETAILED W:lITTEN PROCEDiJ2ES, R Ui'l SHEETS, LETTERS OF AUTHORIZATION AND EXTENDED WORK PROCEDURES SHALL BE PROVlOED FOR OPE?ATIOr; OF THE PLAUT. IN ADDITION, 'N2ITTEN PROCEDUR[S FOR HANDLHlG AElNORr',iflL OPERATIilG CO~:DITrO;;S AND FOR RADIATIOH PROTECTION SHALL BE PROVIDED. 7.1.5 LOGS AND RECORDS. LOGS AND RECORDS SHALL BE MAWTAIi:ED AS REQUIRED BY THE PROVISION\L LICENSE AND SHALL INCLUDE i'.nNUTES C;:: 1,1EETWGS o i'- THE PLANT SAFETY COr,~,lITTEE AS ':/EL1. AS DETAILS OF INVESTIGATIONS MID RECO!,,',iE::-U-ATIONS IN REGARD TO ABNOil,':AL OCCURRENCES A::O AcnOe'lS TAKEN THEREOi!. 7.1.6 AUDIT OF OPERATIONS. ,\:"\iIAGEI,;ENT SHALL PROVIDE rOR Ar::jUALAUDITS OF HIE OPE?.ATIOnS THROUGHOUT THE ENTIRE PL';NT WITH REG:'..'W TO RADIO-LOGICAL AiW lWCLEAR SAFETY. THESE AUDITS S:!ALL 3E PERFORI.;m BY CO;',;PETENT PERSOUi-:EL NOT DIRECTLY RESPO:1SIBLE FOR TflE OPERATION AlJOITED. (Chang~ No. 11) I I
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SYSTE',: InVOLVcU TO :-.::.'.:,:/.'~: T~lr..: C;', ',..;,3:.: C> ~!'C~*.~*Jr:~~; 11:1: ~:~~ ..CIFI(;i\TIO:i OR TO ~FLlr.V~: IT::; E.;'-l*~ '~:T, t\S At',,:,,!]:):::L:"T::. Tr:~-: O.~-':::n.*\rlC:: ::_:\Y CO:!TI>~UF 11: f\ "2~':"~)'z' OY;JITTO:'l'l lE",::lC:~_,\:1ILY rYlLLSS Tii:-::-.:: IS ;\l:OTHEQ OCCUi'{;~E::C:E TH,\T '~';J~.H,U ;:;J:-':THt:~ ~::':~)*.JC!: lilE r:.;\~(~lJ:: 0:- S.:.. [":.:fY Ii: r.iiICH EVEUT l!:.:*.':~~~)I . .\TE: S~rUTi}:\':::l IS iH::_~:_::~~t:l). 7.1. 7.2 Ii;;,;EDL',TF, SEPS SH:l,LL ::,::: TAKF.lI TO :::STidLISII 1::;: CAUSE 0:: THE OCCUtii:ENCE IN "7.1."7.1 BY Rr:S~'OijSlflLE I!J;::,\GE,',;:::NT K::'.rrE ..:.
'1.1.7.3 IF SPECIFICATIOiIS 11.1.1 OK 4.2.3 ARf: EXCEFDElJ, (A) THE PlJ\NT SYSTEi.! CAUSWG T:!E EXCESSI'-/::: RADIOACTIVITY 2ELF.ASE SHALL BE Sl-IUTDO/fi'i, (s) F-:E~jIW I D1VIS10:J Of CO:'.~PLIAi:C:E SHALL BE iJOTIFIED AND (C) THE OP;Cc.,\TIO:; Oe THE SYSE'.1 SHi,LL LOT 3E RESUi2D Ui!TIL TEE SOURCE OF THE RfLLASE Hi\S BEEf! Di:'TER;,:IiiED l\e;O TIlE r';EC,;3Sr\,~Y COi-:RECllVE ACTIO:! ,[AS BEe'!.! TAKEi!. IF THE RELEP,SE IS ~OU!!il TO EXCEED THE A:,:OUi'!'[ ALLO:ic:D UUDEH THE SPECIFIGHIO:: FOR !, Oi;1" YE,\?
PERIOD, OPE'-J\TIOi'J SHM,L NOT BE RESUi,im ;'IITHOUT SPECIFIC ALrrHO~I
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7.1.8 rV,\LLi,\TIOi!S liJ\DE OF PROVISIOi!S FO? nUCLEAR C';HIGd.TTY SAfETY SHALL UTILIZE TliI:: DOUBLE corrrrtJGEi'!CY C;::ITi:r:1A TO [SrillLI~;1i Ti:.\T ,W;'EOVED NU '-LEI\R v ~nI'r-c'r--1--Y v;-\ 1 ':'..... 1 "'Fc-y wc\. '~_l SYSTr:"'"
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N F 5 BOX 124WEST VALLEY. N.Y. 14171 AReA CODe 716 TeLePHONE: D4Z-3Z35 September 17, 1969 Dr. John A. McBride, Director Division of Materials Licensing United States Atomic Energy Commission Washington, D. C. 20545
Dear Dr. McBride:
Pursuant to Paragraph 50.59 of Title 10 of the Code of Federal Regulations, Nuclear Fuel Services, Inc. hereby requests Change No. 11 to the Technical Specifications of Provisional Operating License CSF-l. The proposed changes contained herein are sub-stantially those proposed by NFS in its submittal dated February 18, 1969; however, modifications have been made to previously proposed changes to incorporate comments and directions of the Irradiated Fuels Branch. Technical Specifications 2.0, 4.1, 4.2, 4.6, 4.7, 4.9, 4.10, ~.ll, 4.12, 4.13, 4.15, 4.16, 5.1, 5.2, 5.5, 5.6, 6.1, 6.2, 6.4, 6.6, 6.7, and 7.1 are attached. NFS believes that these changes, which have been discussed in detail with personnel of the Irradiated Fuels Branch, do not contain any significant hazard consideration not described or implicit in the Final Safety Analysis Report submitted under Docket 50-201; therefore, authorization of the changes is requested. If additional information is necessary, we will be available to meet with your staff. Very truly yours, 111~c/£~~
/~. P. Duckworth Plant Manager JPD:JRC:js
Enclosures:
Technical Specifications cc: E. D. North D. H. Shafer B. G. Bechhoefer
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JUN 19 1970 Docket No. 50-201 Change No. 11 License No. CSF-l Nuclear Fuel Services, Inc. Wheaton Plaza Office Building Suite 906 Wheaton. Maryland 20902 Attention: Dr. E. D. North, Director Technical Administration New York State Atomic and Space Develo~ent Authority 230 Park Avenu" New York, New York 10017 Attention: Hr. *James Cline General Manager Gentlemen: This refers to your request dated June 16, 1970, for authority to receive. possess, aod use up to five mi1iicuries of strontium 85 as a tracer in investigaticn and evaluation of liquid waste treatment systems. Your request has been designated as Proposed Change No. 11 aDd has been considered pursuant to the proviiion of 50.59 of 10 erR Part 50.
- w. have concluded that the proposed change does not present a significant ~azard consideration not described or icplicit in the NFS It!!.,al Safety Analysis Report" a:ld that there is reasonable assurance t:~: t~l ~asl~h ~,d safety of the ~~~lic will n~t be en~a~glred by the c~ange.
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I . Nuclea~ Fuel Services, Inc. -**--AND New York State Atomic and Space Development Authority Accordingly. pursuant to Section 50.59 of 10 eFR SO, the change in Technical Specification 3.3 of License No. CSF-l as .et forth on attached page. No. 8 is authorized. POI'l'BE ATOMIC ENERGY COMMISSION Lyall Johnson Acting Director Divi.ion of Materials Licensing
Enclosure:
Change No. 11. Revision Page 8 ec! Mr, B. G. Bechhoefer: w/enel. Mr. O. M. Ruebhausen. w/encl. Mr. J. P. Duckworth, w/encl.
3.3 Material Possession Li.mit .I2!!!. Cesiwn-134 6. X 10- S curie any Cerium-144 3. x 10- S curie any Iodine-13l 6. x 10-6 curie any Iodine-129 5. x 10-6 curie any Ruthenium-l06 3. x 10';S curie any Zirconium-95 3. x 10-' curie any Strontiu:n-90 6. x 10- 3 curie any Strontium-8S s. x 10- 3 curie any Krypton-85 3. curies any Zinc-6S 2. x 10-5 cm:'i..;> any ChromiUCI-51 s. x 10-5 curie any Cobalt-60 5. x 10- 2 curie any Carbon-14 1. x 10~5 curie any Tritium 1. x 10-3 curie any Any byproduct material with ato~ic numbers 3. x 10-6 curie any from 3 to 85 inclusive each (Co'1an;e No. 11)
SAFETY EVALUATION BY DIVISIO~ OF ~~_\T;:;:U.'!'LS LIc:.:~ISI~IG truCLE.H Ft.:~L S::'WIC:::.5, me. DOC:S! ~;O. 50-L,)1 TRACER uS::: OF Sn0;:TIUH 8S By TWX dated June 16. 1970, Nuclear Fuel Services, Inc. requested a change in Technical Specification 3.3 of License C5F-l, to authorize 5 millicuries of strontium-8S for use as a tracer in investigation and evaluati~n of liquid waste treatment systems. Technical Specification 3.3 of Provisional Facility Operating License No. CSF-l lists nuclides. quality limits, and forms which are authorized for receipt. possession, storage, and use for standards, tests, measure-ments, and calibrations. By telecon June 18, 1970, I verified that the proposed tracer inves-tigations would be laboratory work and not environmental dispersal studies. Hence, any waste disposal from these investigations would be subject to the prevailing technical specifications in the license which govern these matters. The reason for the request to authorize use of .~ ..,",... r"'. ............. ___ __ __ ..._____ ..... _..... -"._--J ......._w ..... -_'" QC;; ., ...... ~"'~ .... .; .. _ ...... 1_ ...... ..:1 . . . . . . . 1. __ ': __ '"
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_ .. _ .... _ * .:. _ _ nl'\ ,, ______ .r_ prompt assessment of the presence of stronti~ in the fluids and solids used in xhe experimental investigation. Strontium-90 assays require several weeks each to obtain data read out. the concentration tabulated in Column 2, Table 11. Appendix B, 10 CFR Part 20 for soluble strontium-8S is 300 times the concentration for soluble strontium-90. If all S millicuries of the 6S-day half life strontiun-SS should be disposed of via liquid effluent system, the impact on the operation of the plant liquid waste discharge system under the prevailing technical specifications would be imperceptible. Each day's throughput of waste water would dilute 5 millicuries of strontium-aS to less than 1/3 the concentration listed in Column 2. Table II, Appendix B, 10 CFR 20. therefore, I conclude that authorizing the use ot the requested strontium-as for the purpose indicated does not present a significant hazard con-sic~=:1tion not described or implicit in the NFS "Final Safety Analysis Report" and that there-is reasonable assurance that the health and safety of the public will not be endangered by authorizing the requested change.
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Irradiated Fuels Branch Division of Materials LicenSing D.\IE: JeN 1 9 1970
CHANGE NO. 12 111'*40 Hheaton September 4, 1970 TO: E. A. Wick FROM: E. D. North
SUBJECT:
m'll f*leeti ng of September 4, 1970 A meeting was held with D~l on September 4, 1970, to discuss the preliminary license information recently submitted for the Plutonium Development Facility. The meeting was attended by: DHl NFS Dr. r'~ann Dr. North fk. Johnson Mr. Hick Hr. Chitwood Hr. Brennan r*lr. Ill:: sbaullier r*lr. Rouse
- 11r. Lipinski The fo 11 owi ng subjects were discussed
Natural Phenomena Dl1l has not yet received an evaluation of the Dames and f*loore Report on earthouakes and this subject was def~rred. A single set of earthquake criteria \'Iill be used for the ~!est Valley site. Dr. i*lann stated that the tornado criteria \'Jere satisfactory ex-cept for the pressure droD of 2 psi in 3 seconds. DMl is fixed on 3 psi in 3 seconds. iJFS requested justification for 3 psi and received nO!le. There was considerable discussion of what constitutes a Class I structure. DMl feels that the emoloyees within the Class I structure must be considered part of the Dublic. ~ultiple barriers must be present between plutonium and emoloyees. NFS' position is that this will be ach-ieved for nitrate solutions but that it is not possible to have multiple barriers in the glove box line. Solution container design must assure that major spills will not result from the occurrence of natural phenomena. This does not mean a full blown Class I dynamic analysis, however.
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111441 E. A. \*Iick September 4, 1970 Natural Pheno~ena (Continued) DML would like additional description of the flood problem. We should look at the Corp of Engineers method for determining maximum cred-ible flood; DML will supply the method. This does not appear to be a sig-nificant problem. NFS should justify the position that plutonium materials in the Class II stru'cture are truly non-disDensible. The possibility of fires and explosion~ must be considered. Three areas that should be given sDecial attention are: (1) pel-let sintering furnace; (2) tanks, vessels or lines carrying nitrate solu-tions; (3) scrap recovery area. An accident analysis should be made for these areas. There Vias much discussion on the filter question. NFS stated that the final filter on the exit streilrrl \'lOuld be Class 1. t*lann ~Iould like two Class I final filters since a single barrier is not fool proof. This will require careful study. Several ootions are available: (1) in-stall a backup final filter; (2) mount glove box exit filters to resist earthquakes; (j~ duct filters ahead of final filters that are shock resis-tant. There was some discussion of the procedure for buttoninq up the facil i ty \'ihen a tornado is illlilli nent. '*lann \'Ias not impressed by the button-ing-up technique and requested an evaluation of the consequences of a tornado strike without warning. If the conse~uences are reasonable, this approach will probably be acceptable althouqh we should be preoared to defend the concept. An earthquake almost certainly will occur without warning, however, the consequences are probably acceptable. Nussbaumer requested information on the instrumentation on the hydrogen supply to the sintering furnace to permit safe shutdOl'm foll011ing an earthquake or tornado. NFS stated that the criticality alarm system would be functional through the earthquake or tornado. A quality assurance program will be re-quired for the Class I system as a minimum. See ADpendix B, 10 CFR 50. NFS does not believe this program should be extended beyond Class I struc-tures. Some description of the standard NFS procedures should be orovided for sensitive areas such as: (1) poisoned tanks; (2) vessles and lines for Pu nitrate solutions, etc. The storage area for completed fuel assemblies must be capable of withstanding earthquake forces without rearrangement that could develop a critical mass.
111442 ( E. A. Wick September 4, 1970 NFS will take the position that absolute filters will withstand 3 psi under all conditions.
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E. D. North EDN/kac cc: Messrs. R. W. Deuster J. L. Brennan I-J. A. Oldham W. H. Lel-Ji s J. R. Clark* r
, 1.'1
COpy UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. I05U Oct 16, 1970 Docket No. 50-201 Change No. 12 Nuclear Fuel Services, Inc. ATTN: Dr. E. D. North, Director Technical Administration Suite 906 Wheaton Plaza Office Building Wheaton, Maryland 20902 AND New York Atomic and Space Development Authority ATTN: Mr. James Cline General Manager 230 Park Avenue New York, New York 10017 Gentlemen: This refers to Nuclear Fuel Services' letter dated March 1970, supplemented July 1970, September 4, 1970, September 21, 1970 and October 8, 1970, supporting proposed changes in Technical Specifications 4.14, 5.3, 6.4 and 6.5 that relate to operation of the new head-end ventilation system. These revisions have been designated by NFS as Proposed Change No. 13 and have been considered pursuant to the provisions of Section 50.59 of 10 CFR 50. We have reviewed the operation of the new head-end ventilation system. As we informed you, the following additional infonmation, based on operating experience, must be provided in a timely manner:
- 1. A 6- and 12-month report giving infonmation on filter loading and personnel exposure for operation of this new faci1i~.
- 2. A 6-month report summarizing your 1500-ga110n sump tank monitoring program experience.
We have determined that the changes to the facf1ity pertaining to the new head-end ventilation system, as submitted, do not present significant COpy
COpy Oct. 16. 1970 hazards considerations not described or implicit in the NFS "Final Safety Analysis Report" and there is reasonable assurance that the health and safety of the public will not be endangered. A copy of the Safety Evaluation by the Division of Materials licensing re-lated to the foregoing provisions of your Proposed Change No. 13 and revised as Change No. 12 is "enclosed. Pursuant to Section 50.59 of 10 CFR Part 50. changes to Technical Specifi-cations of Provisional Operating license CSF-l. Numbers 4.14.5.3. 6.4 and 6.5 (as set forth on enclosed pages 42a. 52. 53. 54. 54a. 54b. 54c. 61. 62. designated previously are rescinded. FOR THE ATOMIC ENERGY COMMISSION (Original Signed by Richard E. Cunningham) for Lyall Johnson Acting Director Division of Materials licensing
Enclosures:
- 1. Chg. No. 12, Rev. Pgs. 42a, 52, 53, 54, 54a. 54ab, 54c, 61. 62, 63.
63a and 63b
- 2. Safety Analysis cc: Mr. B. G. Bechhoefer, w/encl.
Mr. O. M. Ruebhausen, w/encl. Mr. J. P. Duckworth w/encl. COpy
*i 4.14
- 42& -
4.14 DBAUST FILTER DIFFERERrIAL PRESSURE Appl1cabUity This specification app1iea to the maximum differential preasures that ..y be maintained acro .. the absolute filters in the exhaust ventilation systems. Objective to minimize the probabUity of filter faUure in exhaust ventilation systems. Specification 4.14.1 THE SUSTAINED OPEBATING PRESSURE DIFFERENTIAL ACROSS AN'l ABSOLUTE FILTER IN AN'l OF THE EXHAUST VENTILATION SYSTEMS SHALL NOT EXCEED 8S% OF THE GREATEST PRESSURE DIFFERENTIAL AT WHICH THAT FILTER HAS BEEN TESTED. Basis Bigh Efficiency (absolute) fUters are used in the plant's ventilation systems (Dissolver Off-Gas. Vessel Off-Gas. Main Building. Head End. Vaste Tank Farm. and DOG-VOG Backup). The absolute filters act as the final containment of radioactivity prior to discharge to the plant stack. The service of the absolute fUters is limited by this speci-fication to minimize the probabUity of fUter failure. Specification 4.14.1 pertains to sustained service of the absolute filter; it is recognized that transient flow variations may cause differential pres-sure excursions exceedina the 8S% lillits as end of service life approaches. the specificationa for all absolute filters used at RFS iDClude the coamon strength requirement that the absolute filter withstand a pres-sure drop of at least 10 inches V. G. without tearing or deforlling. All absolute filters used at NFS are' tested by the.manufacturer to
- pressure differential of at least 10 inchea V. G.
(Chuge Ro. 12) October. 1970
5.3 5.3 VENTlLAXION Applicabil1ty ThU .pecification appl1.. to the operability requirement. of the
~tilation .yst....
Objective 1D a.aure that ventilation equipment necesaary for **fety i. operable during plant operation. Specification 5.3.1 DISSOLVER OFF-GAS SYSTEM (DOG)-DURlHG DISSOLUTION OR SHEAR OPERATIONS. THE EQUIPMENT THAT SHALL BE MAINTAINED IN OPERATION IN-CLUDES AS A MIN1Ml1M A CHEMICAL SClWBBER AND ONE DISSOLVER OFF-GAS nLTER AND ITS ASSOCIATED BLOWER. IF THE FUEL BATCH CONTAINS IN EX-CESS 'OF 0.6 CURIE OF IODINE-13l. THE OPERATING EQUIPMENT SHALL ALSO INCLUDE ONE OFF-GAS HEATER FOLLOWED BY AN OFF-GAS SnVER NITRATE IEACTOR. IF THIS REQUIREMENT IS Nor MET. THE DISSOLVER SHALL BE IMMEDIATELY COOLED AND SHEARING OPERATIONS SHALL BE IMMEDIATELY DISCONTINUED. 5.3.2 VESSEL OFF-GAS SYSTEM (VOG)-BOTB OFF-GAS FILTERS AND ASSOCI-ATED BLOWERS SHAU. BE OPERABLE AT THE START OF A CAMPAIGN OPERATION INVOLVING THE FEED ADJUSTMENT AND ACCOUNTABnITY TANK. mE EQUIPNE~ SHALL BE OPERABLE THROUGHOUT A CAMPAIGN EXCEPT OPERAtIONS MAY BE CON-TINUED FOR 24 HOURS IF BOTH FILTERS AND/OR THEIR ASSOCIATED BLOWERS FAIL. 5.3.3 AT THE STARr OF A PROCESSING CAMPAIGN IN TBE PROCESS MECHANICAL CELL. THE FOLLOWING EQUIPMENT SHALL BE OPERATIVE: BEAD-END VENTnATION SYSTEM
- 1. BO'l'H ELECTRlCALLY-DlUVEN EXHAUST BLOWERS.
- 2. THE SPARE PROPANE GAS ENGINE-DRlVEN EXHAUST BLOWER.
- 3. ALL FnTER STAGES IN Bora FnTER BANKS.
MAIN PLANT VENTILATION SYSTEM
- 1. am EXHAUST BLOWER AND ITS ASSOCIATED ROUGHING AND ABSOLUTE FlLTERS. .
(Change No .12) October, 1970
5.3 5.3.4 Ja THE START OF A PIOCESSING CAMPAIGN IN THE SOLVENT ErrRAC-TIOR AREA. THE !OLLOWING EQUIPMENT SHALL BE OPERATIVE: HAIN PLANT VENTILATION SYSTEM
- 1. BOTH EXBAUST BLOWERS AND THEIR ASSOCIJaED ROUGBIHG AND ABSOLUTE FILTERS IIJW) END VENTILATION SYSTEM
- 1. ALL FILTER STAGES IN ONE FILTER BANK.
- 2. EITHER BOTH ELEClRICALLY-DRIVEN EXHAUST BLOWERS OR mE SPARE PROPANE GAS EHGINE-DRIVEH EXHAUST BLOWER.
5.3.5 IF. !OR ANY REASON. THE REDUNDANCY IN FILTRATION CAPABILITY OR EXHAUST BLOWER AVAILABILITY OF EITHER THE HEAD-END OR MAIN PLANT VENT-ILATION SYSTEM IS LOST POR A PERIOD OF TUlE EXCEEDING 10 DAYS. ALL PLANT OPERATIONS EXCEPT THE AVAILABLE VENTILATION SYSTE.'i SHALL BE SHUT DOWN IN AN ORDERLY FASHION. PLANT OPERATIONS MAY BE CONTINUED BEYOND THE 10 DAY PERIOD ONLY IF THE FAILED EQUIPt-IE:fr INVOLVES A MAJOR COM-PONENT SUCH AS A BLOWER OR A DRIVE UNIT PROVIDED (1) THE SAFETY COMMITTEE BAS APPROVED A PLAN FOR EXPEDIENT REPAIR OR REPLACEMENT OF THE FAILED WIT AND (2) WITHIN 20 DAYS A REPoRT BAS BEEN FILED WITH THE CmmSSION OUTLINING THE FINDINGS. CONCLUSIONS AND RECOMMENDATIONS OF THE SAFETY COMMITTEE. 5.3.6 IF EITHER THE READ-END OR MAIN PLANT EXHAUST VENTILATION SYSTEM FAlLS TO SUCH AN EXTENT THAT NORUAL FLOW OF FILTERED AIR IS NOT AVAIL-ABLE IN mE PARTICULAR SYSTEM. ALL PLANT OPERATIONS EXCEPT VENTILATION SYSTEM OPERATION SHALL BE smrr OOWN IN AN ORDEBLY MANNER. 5.3.7 THE INSTRUMENTATION )l)NITORIHG THE DIFFERENTIAL PRESSURE ACROSS THE OPERATING FINAL ABSOLUTE FILTER IN mE BEAD-END VENTILATION SYSTEM SHALL BE OPERABLE DURING OPERATION OF THE FILTER. IF mIS INSTRUMENTATION SJI)tJLD BECOME INOPERABLE. OPERATION OF THE FILTER CAN CONTINUE FOR 10 DAYS. PROVIDED THAT mE INSTRUMENTATION H>NITORIHG THE DIFFERENTIAL PRESSURE ACROSS mE FILTER BANK IS OPERABLE. (C2lanse No. 12) October. 1970
5.3 FILTER PRIMARY DSTRDMENTS ACCEPTABLE ALTERNATES lST-73 15PDR-45 15PDR-44 lSPDAJI-34 15PDAB-32 15T-73A lSPDR-45A lSPDR-44A lSPDAII-34A 15PDAB-32A mE INSTRUMENTATION !l>NlTORlNG THE DIFFERENTIAL PRESSURE ACROSS THE OPERATING ABSOLUTE nLTERS IN THE MAIN VENTILATION SYSTEM SHALL BE OPERABLE DURING OPERATION OF THE FILTER. IF THIS INSTRUMENTATION SHOULD BECOME INOPERABLE, OPERATION OF THE FILTER MAY CONTINUE FOR 10 DAYS. PROVIDED mAT THE INSTRUMENTATION !l>NITORING THE DIFFERENTIAL PRESSURE .ACROSS THE ABSOLtrrE FILTER PLUS ROUGHING nLTER IS OPERABLE. FILTER PRIMARY INSTRUMENTS ALTERNATES l5T-49 l5PDR-ll 15PDR-I0 l5PDAH-ll l5PDAH- 5 l5T-49A l5PDR- 6 lSPDR- 5 l5PDAB- 6 l5PDAH- 4 5.3.8 WASTE TANK OFF-GAS SYSTEM-IF A FILTER, BLOWER, OR A WASTE TANK OFF-GAS CONDENSER FAllS, THE WASTE TANK VENT SYSTEM SHALL BE SWITCHED
'1'0 THE APPROPRIATE OPERABLE STANDBY EQUIPMENT AND IMMEDIATE REPAIR SHALL BE INSTITUTED TO EXPEDITE THE RETURN OF THE FAILED EQUIPMENT 'l'O SERVICE.
5.3.9 DOG-VOG BACKUP FlLTERS-A DOG-VOG BACKUP FILTER SHALL BE OPER-ABLE AT AU. TIMES. Baals The primary control of airbome radioactivity in the plant is provided by four ftntilation systeu. This speCification b.. been designed to
.. sure the availability of sufficient ftntilation capacity to provide (Change Ro. 12)
October. 1970
5.3
- 54a -
the proper pr...ure clifferentials between operatins equipment and Occupied area. .0 that plant personnel are protected from airborne Kt1vity, and to maintain in operation ...ential treatment 81'.t... for the removal of radioKtiv1ty from the ~tilation .tr.... prior to their relea.e to the atmo.phere.
'lbe DOG 81.t- treats s..eoua effluents from the dis.olver, the bundle
.hear and the pin .hear. The off-sa. from the .hearins operations is CODDect.ed to the DOG 81.t- upstre_ from the chemical .crubber and the combined diaaolver and .hear off-..... pas. through the .crubber, reheater, a .ilver nitrate reactor, a cooler and a filter prior to blower discharge into the .tack. The chemical .crubber removes about 90 percent of the iodine 131 aDd, if nece.sary, the chemical .crubber in combination with a .ilver nitrate reactor removes about 99.S per-cent of the iodine 131. I f the 1Il1Dimum operable equipment require-ments are not met, the evolution of radioactivity is reduced by discontinuing the shearing operation and by cooling the dissolver, thereby .lowing the reaction. This will reduce the fraction of the annual release limit (TechD1cal Specification 4.1.1) expended during equipment iooperability. The VOG system provides equipment for the treatment of the gaseous effluents from radioactive-containing process vessels throughout the plant. These gases are condensed, scrubbed, heated and filtered prior to blower discharge to the stack. If both VOG fi1ter-blower units fail, operations may continue for a 24-bour period because confinement is afforded by the DOG-VOG backup filter and the Main Ventilation Sys-tem, which exhausts the .paces where the vessels on the VOG system are located. An absolute filter aDd a parallel alternate are installed in the com-lIOn discharge line from the DOG and VOG emausters to the stack. These filters provide in-depth protection against releases from a failed filter in either the DOG-VOG systems. Technical Specification 5.3.9 requires that one of the backup filters IIIlst be operable. Hence, the spare 1IIU8t be maintained in readines ** The exhaust system for the plant includes two major system. Each .ystem IlUBt be fully operable before operations are begun at the start of a campaign in the areas served by each system. Thus the REV system asst be fully operable before fuel is moved into the PMC at the start (Change No. 12) October, 1970
~ . 5.3
- 54b -
of a nw capaip ad the Ka1.D VentUation Syat. . .uat be fully operable before co...aceMnt of sol'ftDt extraction at the atart of
*a capaip.
Partial faUure of either aystell vUl not result in UDdue riak pro-vided that prompt repair of defective unita ia effected. Plant oper-ati088 _y contiDue without a apare iD the areas aerved by . .ch ays-ta for a 10-clay period. If repaira ccmot be _de withiD 10 days. aDCl if the faUed equipmellt 18 a _jor coaponent, operation . .y CODtiDue whUe repaira or replacement is aade under the provisiona of 5.3.5. A total failure of either aystem vUl require the orderly ahutdOWD of plant operationa. Plant operationa may be reaumed upon the re-atoration to aervice of one full aection of the failed system siDce the condition then 18 the aame .. would result frOID a partial failure duriDg a campaip. The Ka1.D VentUation Syatem controls the pasaage of air through the proce.. areas beyond the Chemical Proc..s Cell frOID clean areas to auccessively more contaminated areas and filters exhausted air prior to discharge up the atack. To provide for continuous operation a standby filter-exhauster unit 18 provided. If one of the filter baDks becomea inoperable. plant operationa may continue for a 10 day period without a spare while the filter bank is being returned to service. Ten* days permit filter replacement without upsetting main-tenance programs. yet entails minimal risk of being without spare. If both exhauster-filter systems are inoperative at the same time. an orderly shutdown IllU8t be iDit1ated. . The Bead End Ventilation Syatem controls air flows for the mechanical proceasiDg areas. the Chemical Proc..s Cell and the Manipulator Repair and Decontamination Building. Like the Main Ventilation System. the Bead End Ventilation Syatem 1Dclud.. independent filter syatems and blowers as alternatea. The REV system has more flexibility since either fUter bank can be operated with either the electric-clriven or the propane-clriven blower. The REV system iDcludea an even greater defense iD depth aince double m,solute filtration 18 used. The oper-ability requirements for REV are abailar to thoae estabUshed for the Ka1.D Ventilation Syatem. Should the REV syatem become totally ioop-erable, an orderly shutdOWD 1IIUIIt be iDit1ated. . (atange No. 12) October. 1970
5.3
- SIte -
lecauae of the potent:lal1y large iaventories of radioactivity on the Naln Ventilation filters and the Bead !ad Ventilation filter. redun-dant instrumentation is provlded. In addition to the stack monitor. performance of the operating filter is monitored by dual differential pressure recorders and high differential pressure alarms. The pri- .ary set of 1nstruments monitors the absolute filters which are the fiual barrier to radioactivity release and the alternate set monitors the entire filter stage. The vaste tank off-gas system condenses and filters gaseous effluents from the storage tanks. In this system dual equipment (I.e. conden-sers. filters and blowers) is provided. Failure of an in1iae component will require a switch to the alternate standby component. Since a failure would decrease the defense in depth. high priority is given to the repair of a failed component. The consequences of violating this specification would be to risk the exposure of operating personnel and the general public to levels of airborne contamination in excess of 'the normally expected acceptable levels as defined in paragraphs 7.6 through 7.9 of the Safety Analyses. In showing that the consequences of events discussed in paragraphs 7.30 through 7.36 are acceptable within the guidelines of 10 CFR Part 100. reliance was placed on the absolute filters being effective. (Change No. 12) October, 1970
6.4 6.4 EMERGENCY urILITY EQUIPKENT Appl1cabUity This apecification applies to the aurveU1ance requirements for the atandby utility equipment. Objective 10 .. aure that standby equipment neceaaary for continued facility operationa is ..tntained in an operative condition. Specification 6.4.1 THE EMERGENCY GENERATOR (30T-1), AIR COMPRESSOR (3lK-lA) A.1W THE COOLING WATER PUMP (32G-4B) SHALL BE OPERATED AT LEAST ONCE EVERY THREE K>NTHS TO DETERMINE THE AT.JTOMATIC START CAPABILITY .AND THE PER-FORMANCE FOR AT LEAST ONE HOUR UNDER AN OPERATING LOAD. IF.ANY OF THE ABOVE EQUIPMENT IS FOUND TO BE DEFICIENT, IMMEDIATE .AND CONTINUING ACTION SHALL BE TAKEN TO RECTIFY THE (x)NDITION. THE NEXT CAMPAIGN SHALL NOT STAIn' UNTIL THE EQUIPMENT IS RETURNED TO SERVICE. 6.4.2 THE EQUIPMENT LISTED BELOW SHALL BE OPERATED AT LEAST ONCE EVERY THREE K>NTHS TO DETERMINE PERFORMANCE FOR AT LEAST ONE HOUR UNDER AN OPERATING LOAD. ANY DEFICIENCIES WILL BE (x)RRECTED AS SPECIFIED IN 6.4.1. BOILER FEED PUMPS 31G-2A and 31G-2B BOILER DRAFT FANS 31K-2 and 31K-2A PLANT WATER PUMPS 32G-2A and 32G-2B 6.4.3 THE QUANTITY OF DIESEL FUEL IN THE on STORAGE TANK (31D-2) SHALL, DURING NORMAL OPERATIONS BE MAINTAINED AT 8,000 GALLONS OR K>RE OR DIESEL FUEL. IF USED DURING ABNORMAL CONDITIONS, OPERATIONS MAY CONTINUE AS LONG AS A VOLtJME OF 4,000 GALLONS OR GREATER IS MAIN";' TAINED. A VOLUME LESS THAN THIS LATTER VALUE WILL REQUIRE THE COM-MENCEMENT OF PLANT SHUTDOWN WHICH SHALL (x)NTlNUE UNLESS THE PRIMARY rtJEL (NATURAL GAs) SERVICE IS RESTORED OR THE FUEL OIL SUPPLY IS REPLENISHED. (Chanse No. 12) October, 1970
6.4 6.4.4 'l'IIE AUXILIARY BEV BLOWER (15F-21) AND HAIN PLAHT SPARE EXHAUST ILOWER (15K-lOA) SHALL BE OPEIA1'ED Ja LEAST ONCE EVERY THREE !l)NTHS TO DETERMINE THE AlJTmu.TIC START CAPABnITY AND 1BE PERFORKAHCE FOR AT LEAST em: II)UR lJRDEll AN OPEIA1'IHG LOAD. 6.4.5 TIlE QUANTITY OF PROPANE FUEL IH THE PROPANE STORAGE TANK (lSD-3) SHALL, DDJlIHG NORMAL OPElA1'IOHS, BE MAIHTAIHED AT 600 GALLONS OR !l)RE. IF USED DURIHG ABNORMAL mHDITIONS, OPERATIONS KAY mNTIHUE AS LONG AS A WLUME OF 300 GALLONS Oll GREATER IS MAINTAINED. A VOL1lME LESS THAN 300 GALLONS WILL lEQUIRE mMHENCEMENT OF SHUTDOWN OF OPERATIONS WHICH SHALL CClfrINUE UNLESS THE PROPANE SUPPLY IS REPLENISHED. Basis Standby equipment bas been provided to enhance the reliability of utilities supplied to safety equipment and devices and for building ventilation. In order to insure satisfactory performance, the stand-by equipment is tested on a routine basis. In the event of ~tural ... outage, diesel fuel bas been provided in sufficient capacity to .. sure normal operations for at lesst 10 hours. A propane supply sufficient for 72 hours operation of the HEY auxiliary blower has been provided. Unless weather conditions are very severe, diesel fuel and/or propane can be replenished within 10 hours thereby permitting continued operations. The consequences of failing to meet the require-ments of this specification is to reduce the level of confidence in the operability of the standby services. (a.an8e No. 12) October. 1910
6.5 6.5 AIR FILTRATlDN EQUIPMENT Aepl1cabllity Thi. .pecification applies to survelliance requirements for the final air fllters in the off-gas aDdventllation systems. Objective To assure proper perfor1l8Dce of the final air filters used in the plant. Specification 6.5.1 IF ANY OF THE FILTERS SHOWN BELOW ARE CHANGED OR K>DIFIED. THEY SHALL BE TESTED, PRIOR TO ROUTINE SERVICE, WITH PARTICULATES OF AN APPROPRIATE SIZE TO ESTABLISH THAT THE INSTALLED FILTERS PROVmE A COLLECTION EFFICIENCY OF AT LEAST 99.95% FOR PARTICULATES 0.3 MICRONS IN DIAMETER OR LARGER. SYSTEM FILTERS DISSOLVER OFF-GAS 6T-1, 6T-1A VESSEL OFF-GAS 6T-2, 6T-2A WASTE TANK OFF GAS 8'1'-1, 8T-lA MAIN BUILDING 15T-49, l5T-49A DOG-VOG BACKUP 6T-3, 6T-3A BEAD END IST-72, 15&-72A, 15T-73, 15T-73. 6 .5.2 THE DIFFERENl'IAL PRESSURE ACROSS THE FINAL OPERATING ABSOLUTE FILTERS (OR ABSOLUTE PLUS ROUGHING WHERE THE FILTERS ARE WITHIN THE SAME FRAME) SHALL BE RECORDED BY INSTRtlKENTAl'ION. 6.5.3 ALARMS SHALL BE PROVIDED TO ANNUNCIATE HIGH DIFFERENTIAL PRESSURE ON THE FINAL OPERATING ABSOLUTE FILTERS OF THE MAIN BUILDING. HEAD END WASTE TANK FARM AND DOG-VOG BACKUP SYSTEMS. THESE ALARMS SHALL BE SEt TO ANNUNCIATE AT LESS THAN 75% OF THE GREATEST DIFFERENTIAL PRESSURE AT WHICH THAT FILTER BAS BEEN TESTED. 6.5.4 AN ALABK SHALL BE PROVIDED TO ANNUNCIATE LOW DIFFERENTIAL PRESSURE ON THE FINAL OPERATING ABSOLUTE FILTER IN THE MAIN BUILDING (Change No. 12) October, 1970
6.5
- 63& -
VEN'l'ILArION SYSTEM AND IN THE BEAD END VEN'l'n.Al'ION SYSTEM. APTER THE OPERATING DIFFERENTIAL PRESSURE EXCEEDS S INCHES W.G., THIS ALARM SIWL BE SET WITHIN 3 INCHES W.G. OF THE OPERAtING DIFFEREN'l'IAL PIESSURE AND SHALL IE ADJUSTED WEEltLY. I .. is The final filters ill the yent1l.ation and off-gaa systems are the , pr1maryprotection against the cl1scharae of particulate radioactivity dur1ng normal operations and particularly under accident conditions. These "absolute" filters are certified by the manufacturer to capture at least 99.97% of all particles 0.3 microns in diameter or larger. The filters are tested after insatllation to detect bypass leakage as well as filter damage that may have occurred during storage and hand-ling. Subsequent tests are not necessary as installed process instru-ments and the stack radioactivity monitors will indicate. filter inte-grity and performance after the filter is placed on stream.
'111ese tests are conducted by putting the filter-blower ill service, iIltroducing a known amount of dioctylphthalate (DOP) test material up-stream of the fUter being tested and takillg samples downstream of the filter to determine the removal efficiency.
The consequence of failing to meet the requirements of Specification 6.5.1 is to risk the introduction of a faulty filter. In such an event, the stack monitor would quickly show up the existence of the fault and corrective action would be taken. Specification 6.5.2 requires that the differential pressure (~p) across the final fUters in the off-gas and ventilation systems be recorded by instrumentation in the Plant Control Room or the Waste Tank Farm shelter. The differential pressure serves as an indicator of filter performance. Alarms which annunciate high differential pressure are provided, per Specification 6.S.3,'on the absolute filters which are the final con-tainment of radioactivity. These alarms are set to annunciate at about 90% of the maximum operating differential pressure allowed by Specifi-cation 4.14. '111is should provide the operator with sufficient time to switch to the altemate filter; however, the differential pressure may exceed the maximum operating differential pressure limit as a transient condition during removal fr~ service. (Change No. 12) October, 1970
6.5
- 63b -
Low differential pressure alarms are provided for the Main Building Ventilation and Bead End Ventilation filters. Initially the low Ap alarm is set at about 1 ineh W.G., i.e. at about 50% of the Ap experi-enced with a clean filter. After the Ap acros. the operating filter reaches 5 inches W.G., the alarm is adjusted weekly to be within 3 .tnches W.G. of the operating differential pressure. The purpose of theae alarms is to increase the potential for detecting a failed absolute filter. (Change No. 12) October, 1970
Page withheld as containing Export Controlled Information 254
Page withheld as containing Export Controlled Information 255
through an air...,asher and heater which the new head end 'Vent system does not haft. The elimination of the water spray air-washer and air beater is DOt expected to preaent a problem in the new 'Ventilation system dnce aateriale of construction were selected to be redstant to .oleture and nitric acid vapors whleb uy be generated in the chemical processing cell. The new system provides double absolute filtration versus the washer and single absolute filtration in the exhting system. The elimination of the washer and use of a IIOre efficient first stage absolute filter in this system should increase tbe filtration efficiency for na11 <<*1 II1cron) particles. The extsting technical specification which limits the IIIIOUDt of activity which can be released as a particulate from the stack ia DOt changed. The technical specifications which cover the operation and surveillance requirements for filter systems have been modified to include the new head end ventilation system and are consistent with the current specifications as they pertain to DOP testing of absolute filters and instrument surveillance of differential pressure on absolute filters. On September 4. 1968. HFS experienced the complete rupture of a final absolute filter in the main ventilation train. After review-ing this matter. NFS concluded that the failure was due to a minimal strength filter. The filter was operating at leas than 80% of the design pressure. As a result of the filter failure. quantities of filter media were drawn through the blower and di~persed out the stack. Subsequent to the September 1968 failure and prior to resuming operations following this failure. NFS inatalled a screen upstream of the main ventilation blower to trap filter media and prevent dis-persal in case of filter rupture. The REV system does not have a screen downstream of the final absolute filter to trap possible filter media prior to diaperal out the stack. A screen is. however. installed between the two banks of absolute filters to trap filter media from possible failure of the firat absolute filter. The first absolute filter will contain the bulk of the particulat.e activity. The final filters. which are not backed up by a screen. as expected have a low inventory of particulate activity. NFS will supply information on the particulate loading of the final filter based on 6 and 12-month operating experience to justify not using a screen after the final absolute filter. '
- 2. Personnel Exposure NFS. by Supplement 2. gives anticipated average exposure rates for performing filter changes in the head end ftntilation system. They
state that for the yearly operation of the system the cumulative annual exposure will be 1.3 man-rema with this exposure spread over 10-20 iDdiv1cluals. The exposure .. tillatea are based on four pre-filter changes per year. two roughing filter changes per year and one change per year of the first absolute filters. IllS predicts that the filters iD final absolute filter stages will have a service life of several years. The 1.3 man-rams per year exposure according to NFS represents an antici-pated reduction of about 2SO IIIUl-rem exposure per year. Tbe ... system will take so_ activity load off the main system and the 1Dcorporation of remote changing of roughing and prefilters in the HEY
.ystem will therefore reduce" the total plant personnel exposure. Oper-ation of the REV system will not eliminate personnel exposure resulting from main ventUation filter changing.
The analysis which was submitted by NFS in support of the 1.3 IlIaD-rem per year states that two minutes will be required to UDclamp 15 absolute filters located in a glove box. NFS's time and motion stu-dies indicate that four pre-filters can be changed in 92 minutes. 8 roughing filters can be in 105 minutes. and 15 absolute filters can be changed in 147 minutes. 'lbe operations which are involved iDclude glove port aisle inspection. change room preparation. removal. transportation. and replacement. NFS will be required to submit information on operating experience at intervals of 6 and 12 montha after this approval. On a qualitative basis personnel "exposure should be reduced from that experienced from past operation of the main ventilation system.
- 3. HSM Sump Tank A 1500 gallon waste tank has been provided to accumulate drainage from the master slave manipulator repair and decontamination shop. the fil-ter housing area and the crane room. The tank is buried in the silty-till adjacent to the MSM shop. The activity in the solutions trans-ferred to the sump tank are not accurately known but are stated by NFS to be low. The sump tank is stainless steel. 1/4" plate. welded construction and all welds have been radiographed.
There is no positive means of checking the integrity of the tank for leakage. NFS has installed a surveillance well from ground surface to the concrete pad foundation of the tank. The area around the bottom of the tank 1.8 packed with gravel "to assure that tank leakage would be found by sampling the well for activity. A water level will be
maintained in the well to permit a.-pling and to help verify that aolutions cannot flow from the area around the tank. This method of tank surveUlance will be uaed for aU: .onths, after which time the aystem will be reevaluated. Burial of the sump tank in the sUty-till, which is found in the NPS area, restricts the possible flow of solutions away from the tank and the ion-exchange propertiea of the sUty-till would also limit activity
.ovement for posaible limited perioda of UIlcontrolled and detected tank leakage.
- 4. RATURAL PHENOMENA The head end ventilation &ystem was constructed to meet Seismic Zone III standards of the Uniform Building Code. WhUe this was acceptable at the time the Plant was constructed it does not conform with the requirements currently imposed for aseismic design. In this connection NFS has assumed that in the event of earthquake or tornado the facility would faU.
The REV building is constructed with the filter areas below grade with-in a reinforced concrete structure. The above ground structure serves as an airlock and crane room for filter removal. The existing main ventilation system provides emergency back-up ventilation for those areas in the existing facUity that are aerved by the HEV system. Assuming that the HEV structure will fail under severe earthquake, the radioactivity would be contained under the rubble and no significant release would result. Location of the contaminated filters below grade reduces the possibUity of contamination being dispersed by local wind conditions. In the event of a tornado it is assumed that the- above grade structure wUl be carried away and the accesa plugs to the filters wUl vent with possible radioactive material release. NFS performed an analysis of the effects of a postulated tornado which released 50% of the radio-active material contained by the filters. We are unable to confirm the NFS evaluation for the release of activity to unrestricted areas. Our independent evaluation show. that the NFS postulated release of activity by a tornado would result in a worst case, lD8xi1llU1ll point, ground level concentration equivalent to 35 days exposure at the con-centration limit for plutonium in unrestricted areas. The worst case calculation 18 based on the release of SO percent (1.3 ps) of the
plutonium contained in the filter SY8tem. The iaotopic composition of the plutonium was a88umed to be that of irradiated power reactor fuel ** Our independent evaluation of the HFS estimated relea8e of 62 curies of c.-137 give. a 1IUi1llllli point ground level concentration equivalent to a one-day expo8ure at the concentration limit for Cs-137 in un-restricted areas. CONCLUSION Based on our review of the propo8ed installation. we conclude that it does not present significant hazard considerations not de8cribed or implicit in HFS's Final Safety Analysis Report" and that there i8 reasonable assurance that the health and 8afety of the public will not be endangered by the opera-tion of the new head-end ventilation 8Y8tem. Approval of the attached technical specifications incorporating the operation of new head-end ventilation 8ystem i8 recommended. Signed: Signed:
- w. A. Nixon Irradiated Fuel8 Branch Approved:
Rf?r~n,d R. B. Chitwood. Chief Irradiated Fuels Branch Divi8ion of Mat erial 8 Licen8ing
CHANGE NO. 13
/"
~i2
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NFS 6 0 0 0 EXECUTIVE BOULEVARO. SUITE 6 0 0 ROCKVILLE. MARYLAND 20052 ARE:A CODE 301- Tt::L.E:PHONE 424*17'50 February 11, 1971 Mr. Lyall E. Johnson Acting Director of Materials Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 RE: Change No. 13 Technical Specification
Dear Mr. Johnson:
This will acknO\~ledge receipt of your letter of January 26, 1971 concerning Change No. 13 in Technical Specification for the West Valley Plant. The suggested change does create practical problems in connection with Revised Technical Specification 5.1.4, Table 5.1, Section a XXIII and Section E. We b~;ieve that it should be pO~5ible to resolve these problems through further discussion, and therefore, lest these sections of the Tech-nical Specifications be finalized without further discussion, we request a hearing pursuant to 10 CFR Part 2, Rules of Practice limited to these tl~O sections of the proposed Rule. To repeat, we hope that the problems, which represent a minor portion of the total impact of the revised Technical Speci-fication, can be resolved through informal discussion. In addition, we call to your attention b'/O provisions of the Revised Technical Specification, which do not create serious problems but may not be realistic. Specification 5.1.4, Table 5.1, Section C. III Fish Samples The requirement for analysis of nine fish twice a year seems excessive, since l'/e believe that the anulysis of one or two fish per year would achieve the same results. Certainly an analysis of six fish I'lould be more than adequate. The method of determining "geometric deviation" should be clarified. RECEIVE.D Section C. IV Deer Samole~
- = ~ e. 1 6 1971 It is entirely possible that there might be no deer on site during the hunting season or that the hunting skills of NFS J. P. UUl,;I\WOKTH personnel might be insufficient to enable til em to take a deer for sampling.
We would appreciate some clarification on certuin items. These con-cern tile method of determining krypton in guseous effluents und the frequency of anulysis of particulutes to deternrine isotopic ratios.
Mr. Lyall E. Johnson Page 2
*
- 111976 February 11,-1971 A detailed statement of the tl'/O main problems encountered in connection with Section B. XXIII and Section E, where we have requested a hearing is set forth below.
Revised Technical Specification 5.1.4, Table 5.1, Section B. XXIII We respectfully request that tllis provision be deleted pri-marily because it serves no useful purpose, and the data accumulated under B. XXII can be utilized to achieve a more meaningful estimate of exposure in the various sectors. In order to make the determination required under this section, it \~ould be necessary for IlFS to determine the meteorological conditions durino each d:ssolver run and then make a separate calculation for ~ach run. This calculation is completely differ-ent from that required in the previous Section XXII and is ex-tremely difficult to accomplish. The result of the calculation in eacll instance would be a fig-ure reflecting an instantaneous exposure which might hold for a few minutes or a few hours, but which would be of no value in calculating average exposures. The limits of allowable MPC set up by 10 CFR 20, Appendix B are based or. average exposures over a period of a year as recommended by the Federal Radiation Council and as recognized in the ReQulations. There are no methods of determi ni ng \*/hether or not an ins tantaneous exposure at the e.xpccted 10\'/ levels of radioactivity is hazardous. A more meaningful estimate of exposure in the various sectors can be made from the data accumulated under the previous Section XXII. Technical Specification 5.1.4, Table 5.1, Section E The U. S. Public Health Service in their Report BRH/NERHL 70-1 concluded that the exposure to the public as defined in 10 CFR 20.106 and Appendix B, Table II is completely negligible. To the best of our knowledg~ during the entire operations of NFS, there has never been any "likelihood of public intakes in excess of 3% of those that could result from continuous exrosure to the concentration values listed in Appendix B, Table II, Part 20". We bel ieve that this prevision \'/ould be appl icable only in the event of an unusual incident which would have other effects re-quiring NFS to be in touch with the AEC.
Lyall E. Johnson
*
- 111~'I" Page 3 February 11, 1971 At the 3% level of exposure, the FRC merely requires routine sampling to determine that the contamination level is indeed low. If the level rose from 3Z to, say 4%, the action required of NFS should be quite different frOIl1 a situation I'lhere the level rose fron1 3% to 33S. While the requirements of the re-vised Specification - "resultant exposure to individuals and to population groups, and assumptions upon which estimates are based," - are probably suffi ci ent? y vague to cover a11 conti n-gencies, their ambiguity could be a source of unnecessary ar-guments.
We, therefore, suggest that the Section be deleted:
- a. Because tile situation visualized is unlikely to arise;
- b. If the situation did arise, it would be a relatively minor result of an incident I:ith other effects, which would require a course of action approved by the Commission.
NFS is not especially well qualified in the area of public ex-posures, and any judgellJents as to publ ic exposure that it might make could be clouded by its pOSition as a vested interest. It would seem desit'able to have such judgements come from an inde-pendent source such as the Publ ic "c~l th Service. Their I'lork in this area is above reproach, and their surveillance of the West Valley Plant effluents is continuing. If the Section is not deleted, it might be rc*. . orded as fo11ol'IS: E. "If levels of radioactive IT'oJtcriills in environmental media indicate the likclillood 0" public intakes in excess of 33Z of those that could result from contin-uous exposure to the concentration values listed in Appendix B, Table II, Part 20. lhe Commission should be notified imnediJtely in order that it may determine
\~hat further action is requit*cd.
Respectfully submitted,
\..1 r,\ /1'( :>J2)7 E. D. North. Director Technical Administration EDij: kac cc: B. G. Bechhoefer
UNlTEDsrAr~oy ATOMIC ENERGY COMMISSION WASHINGTON. D.C. IONS January 26. 1971 Docket No. 50-201 Nuclear Fuel Services. Inc. ATTN: Mr. Robert N. Miller. President 6000 Executive Boulevard Suite 600 Rockville. Maryland 20852 and New York Atomic and Space Development Authority ATTN: Mr. James Cline. General Manager 230 Park Avenue
. New York. New York 10017 Change No. 13 License No. CSF-1 Gentlemen:
This is in response to a letter from Nuclear Fuel Services. Inc. (NFS) dated June 29. 1970. in which was submitted a proposal for an expanded environmental program. We subsequently discussed this proposal with Dr. E. D. North. As a consequence of' our review of the information contained in the NFS proposal and the discussions with Dr. North. we have determined to revise the Technical Specifications of License No. CSF-l*to incorporate an expanded environmental program. This revision to Section 5.1 of the Technical Specifications is contained in the attached Change NO. 13. On the basis of our review. we have concluded that the change does not present significant safety hazards considerations 'not described or implicit in the NFS "Final Safety Analysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered. Accordingly. pursuant to Sections 50.36 and SO.59 of 10 CFR Part 50. Change No. 13 in the Technical Specifications of License No. CSF-l. as set forth on the enclosed pages 44 through 46f of revised Technical Specification 5.1. is authorized. COP.Y
_ . _N~cl~ar Fuel Services. Inc. COpy It should be noted that Change No. 13 does not reflect chances which may be necessary in connection with the operation of the low-level liquid waste treatment plant now being constructed. Pursuant to 10 CFR Part 2. Rules of Practice. you may request a hearing with respect to all or an~ part of this change in the Technical Specifi-cations within twenty (20) days from the date of this letter. FOR THE ATOMIC ENERGY COMMISSION (Original signed by Lya 11 Johnson) Lyall Johnson Acting Director
Enclosure:
Change No. 13. Rev. pp. 44 - 46f cc: Mr. B. G. Bechhoefer w/encl Mr. O. M. Ruebhausen w/encl Mr. J. P. Duckworth w/encl COpy
5.1 EFFLUENT A.~ ENVIRO~~llTAL MO~ITORING AppHcahUity This specification applies to the samplin~ and analysis of gaseous and liquid plant effluents and to environmental monitoring. Objective To establish samQl1n~ points, .aaplin~ fre~uency and sacple analyti-cal requireoents for r-aseous and liQuid plant effluents and to establish an environr.ental monitoring prograo and reporting requirement. Specification
'5.1.1 "'H~VER LIQUID IS DISCHA.ltGED FRO'! THE STORAGE LAGOO~:S, A REPRESE~TATn'E SA!!PLE Si!ALL BE tnTH.!H'.At~ BY TIlE CAT'!AT',At:Cl:S CREEK COXTI:;rOI:S SA~:PLER. AT LEAST EVERY SEV~i DAYS, A CO~!
POSITE OF THIS SA!!PLE SHALL BE A;'ALYZED FOR TRITIL;'[, GROSS ALl?HA A.'lD GROSS BEl'A RADIOACTIVITY. IF 11fE CONTI~ruOt:S S~'lPLER. BECO~!ES IXOPERAl'I\'E, CP TO 2,000,000 CALLONS ~!AY BE DISCIL\TtGED FRO~! THE L\GOm:s IX ANY O::E-YEAR PERIOD P~OVIDED CAl'TA!lAt:GUS C!'..EEK. SA!IPLES A!tE COLLECTED ~mAR THE CONTI:;Um;S SA!!PLER LOCATIO:: FOR EACH LAC'.oON DISCI!ARGE O?. FOR EACH 100,000 GALLm:s 0: DISCHA~GE, WHICHEVER !'-EST:LTS I:~ THE GREATER SA.":PLI::G FT'..EQUENCY. S~'!PLES SO COLLECTED SHALL BE INDIVIDUAUY A.'lALYZED FOR TRITIL~[. GROSS ALPHA A..'lD Gr-OSS BEl'A RADIOACTIVITY. 5.1.2 A CONTINUOUS STACK S~!PLER SHALL BE USED TO COLLECT S~!PLES OF STACK GAS. THE SA!!PLES SHALL BE ~~\LYZEn AX LEAST EVERY SEVE.'l DAYS FOR IODI!:! 131 A.'m PARTICt"!.ATE RADIOACTIVITY. IF THE STACK SA:'lPLER BECO~,[ES I!:OPEMTIYE, I:!"IEDIA!'E REPAIR SHALL BE INSTITUTED TO RETUR.'l tilE S~[PLER TO SE!tVICE. IN ADDITIO!: TO THE WEEJ:LY S~'1PLES OBTAINED FRm[ THE STACK SA~E. nlE 1-131, Kr-8S A.\'O PA.1tTICt'I.A1'E P..AnIOACTIVITY I~ THZ: STACK GAS SHALL BE CO!ITI:-'-UOUSLY !!EASU?.ED BY A STACK ~[O~ITOR. (Change No. 13)
i IF THE STACK S,uIPLER BEeO!-IES INOPERATIVE, N!EDIATE REPAIR SHALL BE INSTITUTED TO RETUr..:: THE UNIT '1'0 SERVICE, A.':D THE STACK ~to~lITOR SHALL BE USED IN THE INTERIM TO DETER!-lWE 1-131 AND PARTICULATE P.ELEASES. IF THE STACK MONITOR FAILS, A P.EPltESENTATIVE SA.'iPLE OF STACK CAS SHALL BE COLL!CTED EACH SHIFT A."!D USED TO DETin!*!!~;E 1-131 AND PARTICULATE R....DIOACT IVITY
- THE Kr-85 CO~lTENT OF STACK CASES SllALL BE CALCULATED rr..o!! Ft.l'EL BUP.NUP DATA DURI!lG PERIODS WEN THE STACK ~mNITOR IS IliOPERATIVE.
5.1.3 THE FOLLOtlIUG Il!FOR.'fATION, DETER.'iINED FROH THE SMfPLES TAKE~l AS REQUIRED BY 5.1.1 A::D 5.1.2, SHALL BE INCLUDED IN THE QUARTEFJ.Y OPERATING P~PORT: A) GROSS CURIES OF ALPHA ActIVITY DISCHARGED INTO CATTARAUGUS CREEK EACH l!ONTH. B) GROSS CURIES OF BETA ActIVITY DISCHARGED INTO CATTARAUGUS CREEK EACH ~:O!:TH. C) CURIES OF TlUTItrn DISCltAr.GED INTO CATTAI'.AUGUS CREEK EACH MONTH. D) CURIES OF SR-90 DISCHARGED INTO CATTARAUGUS CREEY. EACH H:)NTII. E) CURIES or 1-129 DISCHARGED INTO CA7TA.~UGUS CREEK EACH MONTH. F) CURIES or PA.TU'ICULATES DISCHARGED VIA TUE STACK FOR EACH HDNTH. C) THE PERCE"~T OF THE !iO~THLY TEcrellCAL SPECIFICATIO~ LIMIT FOR DISCHARGE OF PARTICULATES VIA THE STACK. B) THE MAXIMUM PERC~~ OF THE XR-85 DAILY TECHNICAL SPECIFICA-
- TION LIHIT IN THE STACK EITLtEY! FO!t EACH ~C!;TH.
X) THE CUMULATIVE PERCENT or THE 1-131 Y~~Y TECa~ICAL SPEeIFICATIO~ LIMIT IN THE STACK EFFLL~~"T REPORTED ON A MONl'HLY BAS IS
- Basis Effluent Honitoring (Changes No. 13)
Samples of water from Cattaraugus Creek.re taken with.a continuous sampler locnted about one-half ~ile dOWDStream from the confluence of cattaraugus and Buttermilk Creeks. ..tions of each weekly sa:!- pIe are composited to produce a sample rep~esentat1ve of one month's discharge. The weekly samples are analyzed for gross alpha, gross beta and tritiu~.The c~posite is analyzed for gross alpha, gross beta and strontium 90. A stream gage located near the sampling .atien 1s used to determine total flow in Cattnraugus Creek. Flow tz.m the la~oon is determined by a calibrated weir located on the discb2rge line. The flow ratio is used in conjunction with the iodine l2t analysis of lagoon water to calculate the iodine 129 content in caataraugus Creek. Gaseous plan~ effluents are sampled in tbe plant stack. The stack
'sampler contains a filter to collect particulates and an nctivated charcoal filter to collect iodine 131. Szrnples are removed from the stack sampler at least each week and .aalyzed.
The stack monitor is used to continuously determine the particulate,
!~dine 131 ~nd krJPten 85 r~io3ctivity ~ th~ s~3~k air ~d t~
alert operators if pre-set limits are exceeded. The particulate sampler is changed every 8 hours and will alarm if the acc~ulation of particulate radioactivity over an 8-ba=r period exceeds that ~~ich would occur if particulates were being discharged over the same t~e limit at the limit set by Technical Spec1ficntion 4.1. The iodine 131 monitor, a carbon filler paper absorber, is chan~ed on a weekly cycle. The instrument is set to alarm if. over a week's period, the counting rate increases 10,000 counts/ni~e. This is far below the increase in count rate (about 400,000 coomes/minute) ~hich would occur if iodine were released at the tecb=ical specification limit for one week. The krypton 85 s::onitor is .u to alarm if the ccunting rate exceeds five tices the background'rate. The alarm point is not, in thi9 c~se, directly related to allowable release rates. The ir~tru ment will alar~ o~ly duri~~ PQriods of h~ krypton 85 discharge, for e~le during dissolutio~ of h1~h ~~ fuels. 5.1.4 THE LICE::SE! SHALL CO~t!CT THE ~~~rr.'U. !'!O~"!'l'O!:.I~~G P?DG::A."f GIVEN IN TAtLE 5.1 /i!;D SH.UL !'.!:;:'1:T T!:! !'.E~t..!.:S O:l':.::~;::l ::: THE D.'D OF EACH SIX-MONTH PEr.IOD ~~m;G Fr.O~ JA.'\t:A:1Y 1, 1971. SUCH REPOR.TS "ILL BE DL"E Ill'mlN 60 DAYS AFIEP. DIE n:n OF EACH REPORTING PERIOD. IF QU~ES OF R.ADIOACTIVE MATERIAL r.ELEASED Dtli:.I::C TIlE RE?o!!I~C PERIOD ARE m.L1SUAL FOR
. NOR."fAL PLANT OPERATIO::S, INCLli'DI::C EXPECTED OPERATIONAL OCCUR-RENCES. THE REPORX SHALL COVER THIS, SPEC IFICAIJ.Y.
(Changes No. 13)
- 46a -
TABLE 5.1 EFFLUENT A.\'D E}"'VlRO~'!-n::!ITAL }!O~ITORING PROGRA!-f A. The licensee shall detercine for each month, based on samples taken at the indic~ted location and other information collected during the month, the following: i Cross curies of beta radioactivity other than tritium released at effluent weir. ii Cross curies of alpha radioactivity released at the effluent weir.
"iii Cu~ies of tritium released at effluent weir.
iv Curies of strontium 90 released at effluent weir. v Curies of cesium 134 released at effluent weir. vi Curies of cesium 137 released at effluent weir. vii Curies of ruthenium 106 and rhodium 106 released at effluent weir. viii Volume of water released at effluent weir. 1x Volume of water flow throush site in Cattaraugus Creek. x Curies of beta emitting particulates released via the stack
- xi Curies of alpha emittin$
~~rticulates released via the stack.
xii Curies of iodine 131 released vlf th~ stack. xiii Curies per cubic meter gross beta radioactivity of particulates (averar,e and maximum) collected by each of the 3 site perimeter
.amplen on fUter paper.
xiv Curies per cubic meter ~ross alpha radioactivity of particu-lates (average and maximum) collected by each of the 3 site perimeter samplers on "filter paper. (Change No. 13)
- 46b -
B. The licensee shall determine each quarter, based on sa~les and other information collected during the quarter, the following: 1 Identity of principal radionuclides whose presence can be determined by e~a spectroscopy of a sample (one per calendar quarter) of Buttermilk Creek bottom sUt collected at the Thomas Corner Road bridge. - 11 Kicroeuries per grao Rross beta ~adioactivity of a sa~le (one per calendar quarter) of Buttemllk Creek bottom s"Ht collected at the Thomas Corner Road bridge. lii Kicrocuries per gram ~ross alpha radioactivity of a sa~le (one per calendar quarter) of Buttemilk Creek bottom silt colleeted at the Tho~~s Corner Road bridge.
"1v Hicrocuries tritium per milliliter of water collected once per quarter at the ButterMUk Creek silt samolin~location during a normal liquid effluent release from the plant.
v .Ucrocuries gross beta radioactivity per milliliter of water collected once per quarter at the Buttemilk Creek sUt sampling location during a noreal liquid effluent release from the plant. vi H1crocuri~~ ~ross alpha radioactivity per milliliter of water collected once per quarter at the Buttermilk Creek silt sampling location during a normal effluent release from the plant. vii Curies of strontium 89 released at the effluent weir based on an analysis of a composite of the liquid released durin~ the last month of the quarter. . viii Curies of zirconium 9S and niobium 9S released at the effluent weir based on an analysis 0' a composite of the liquid released during the last month of the quarter. Ix Curies of iodine 129 released at effluent weir. x A quantitative analysis of al~ha emitting components in a quarterly composite collected at the effluent weir. (Change No. 13)
- 46c -
xi The exposure, in megawatts days. of fuel dissolved durinz the quarter. xii The curies of Krypton 85 released via the stack as deternined using the stack monitor. xiii Curies of tritium released via the stack. xiv ruries of iodine 129 released via the stack. xv Curies of strontium 89 released via the stack. xvi Curies of strontium 90 released via the stack. xvii Curies off ruthenium 106 released via the stack. xviii Curies of cesium 134 released via the stack. xix Curies of cesium 137 released via the stack. xx Microcuries ~er milliliter tritium (avera~e) in preci?itation collected at each of the 3 site perimeter sampling statior~. xxi Milliroentgen of radiation (includin~ background) accrued each quarter at each of the 3 site perimeter samplin& stations. xxii The maximum value at ground level offsite in each w/8 sector about the stack of the X/Q inter-rated for each seasonal
. quarter from hourly avera~es of continuously recorded meteoro-logical data. The X/Q shall be determinedu~in~ equation 3.144 given on page 113 of ~~teoro102v and Atomic Enerv.v (1968).
Seasonal quarters are defined as: Spring ~~~~~~ Summer June through August F~l September throu~h Novemher Winter December through February xxiii The curie seconds per cubic meter maxiauo exposure of Kr-85 integrated for the reported quarter at p,round level offsite in each w/8 sector about the stack, computed from meteoro1o~ical data recorded durinr. emission of the respective increments of Kr-85 that register above background on the Kr-85 stack* gas monitor. (Change No. 13)
- 46d -
- c. The licensee shall determine the following information according to the schedule given:
1 If, during any week from April to October, inclUSive, the release of iodine 131 from the stack exceeds 30 millicuries, the licensee shall determine the microcuries per milliliter of iodine 131 in s&~ples of milk from farms ~~thin 2-1/2
.tIes of the plant in each direction e~ected to receive the release. One sample shall be coilected each week for the four weeks following the release. Each sample shall be a co~site of one day's production from cows which are on pasture.
ii During August of each year the licensee shall collect a adlk sample from a f~rm within 2-1/2 Diles of the plant in the north-west sector and a milk samole from a farm wit~in 2-1/2 miles of the plant in the north-east sector. The samples shall be composites of one day's production from cO'JS which are on pasture. Each sample shall be analyzed separately to determine:
.) M:lernctl1"il!!I iodine l?Q
-~
".~ _4"4'~.ft_
r - - -------~-~ b) Microcuries strontium 90 per milliliter c) Hicrocuries cesium 134 per milliliter d) Microcuries cesium 137 per milliliter 1ii During the second and third quarters of each year, licensee shall take fish samples from Cattaraugus Creek between the Springville h:--droelectric dar.! and the Cattaraunus Creek-Buttermilk Creek confluence. One sar.!1)le shall be taken during each of the t,.ro quarters: A saJl!ple shall con.dst of at least 9 fish, each at least six inches lon~. Each fish in each sample shall be analyzed to determine:
.) Median and geometric deviation of cesium 134 micro-curies -per kilogram of flesh.
b) Median and geometric devi~tion of cesiu:n 137 micro-curies per kilogram of flesh. c) Median and geometric deviation of strontium 90 micro-curies per kilogra~ of flesh. (Change No. 13)
- 46e -
d) Median and Rcometric deviation of strontium 90 micro-curies per kilogram of skeleton. iv Once per year the licensee shall determine the follo,dng from a deer taken onsite during the hunting season and taken, preferably, north of the plant: a) Microcuries cesium 134 per idIogram of flesh. b) Hicrocuries cesium 137 per kilogram of flesh. c) Joficrocuries strontium 90 per kilogram of flesh. d) Hicrocuries strontium 89 per kilogram of skeleton. e) Microcuries strontium 90 per kilogram of skeleton *
.'D. The environmental reports to be prepared by the licensee shall contain descriptive material coverin~ the environ~ntal surveys performed during the reporting period including information on:
i The number and types of samples taken; e.g., air, surface water, soil, fish. ii The number and types of measurements made. iii Locations of the sample points and monitoring stations. iv 'The frequency of the surveys. v A SUlIII!I8ry of survey results. E. If levels of radioactive Nterials in environmental media indicate the likelihood of public intakes in excess of 3% of those that could result from continuous ex~sure to the concentration values listed in Appendix B, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based should be provided. F. If statistically significant variations in offsite environmental concentrations with time arc observed, correlation of these results with effluent releases should be provided. (Change No. 13)
- 46f Basis Environmental Monitorinp, The environmental surveY incorporates measurements to provide back-groundd~ta and measure possible ~lant effects. SaM~les collected at points where concentrations of effluents in the environment are expected to be ~reatest will be com~ared with sample~ collected con-currently at points expected to be essentially unaffected by st~tion effluents. The latter sa~les will provide back~round measure~ents a8 a basis for distinr,uishin3 significant radioactivity introduced into the environ~ent by the operation of the plant from that due to other sources such as nucre~r detonations.
This schedule will assure that si~ificant changes in the environmental . radio~ct ivity are sampled most frequently. Those 'Ihich are less affected by transient changes but show long-term acc~ulations are sampled less frequently. The monitoring program will be reviewed and re-evaluated periodically after data such as composition. quantity and frequency of relp.;!!';p~. dilution factors and measured concentrations in food and other
~rganisms (if any are observed) are obtained.
(Change No. 13)
CHANGE NO. '4
.~
.. ~ N F S NUCLEA:Q. FUEL SE ~vICEs,I_N_c_.___ BOX 124"'WEST VALLEY. N.Y. 14171 AREA CODE 716 TELEPHONE 9042-32315 July 12, 1971 Mr. Richard E. Cunningham, Acting Director Division of Materials Licensing U. S. Atomic Energy Commission Washington, D. C. 20545
Dear Mr. Cunningham:
Pursuant to Paragraph 50.59 of Title 10 Code of Federal Regulations, Nuclear Fuel Services, Inc. hereby requests a change in the Technical Specifications for Operating License CSF-1. The proposed changes will permit the NFS Processing Plant at West Valley, New York, to receive and store plutonium nitrate-uranyl nitrate solutions now being prepared at the NFS facility at Erwin, Tennessee. The safety evaluation of the pro-posed processing plan and the necessary amendments to the Technical Spe-cifications will be the subject of an up-coming submission. NFS believes that these changes, which are necessary for receipt and storage and which were discussed with personnel of the Irradiated Fuels Branch, do not contain any significant safety consideration not described or implicit in the Final Safety Analysis Report submitted under Docket 50-201; therefore, authorization of the changes is requested. Very truly yours, (l,/ J~~_LwCf:
/ ;. P. Duckworth Plant Manager JPD:cp Enc.
cc: E. D. North D. H. Shafer B. G. Bechhoefer
PROPOSED TECHNICAL SPECIFICATION CliANGES FOR THE RECEIPT AND STORAGE OF PU(N03)4-U02(N03)2 AT THE WEST VALLEY PROCESSING PLANT The solutions of plutonium nitrate and depleted uranyl nitrate will be packaged and transported to the NFS Fuel Processing Plant in containers ap-proved by the USAEC Division of Material Licensing and Department of Trans-portation. It is anticipated that these containers will be either NFS 10 LI or ASDA 10 LI packages. The packages will be stored in Product Packaging & Storage (PPS) Area of the Processing Plant which has previously been reviewed by the USAEC and approved for such storage by Technical Specification 4.10 of License CSF-l. The total number of containers in the PPS will not exceed 125; therefore, the possession limit for the facility as listed in Specification 3.1.2 need not be amended. The amendments that NFS believes necessary are shown below. 3.1.1 (new paragraph) Source and/or special nuclear materials may also be received solutions in the following category: Category Fuel Compound Fissile Concentration gIl 10 Plutonium Nitrate-Depleted Not exceeding 250 grams Uranyl Nitrate fissile plutonium per liter 3.1.3 (new third paragraph) Material Category 10 authorized in Specification 3.1.1 may be received in packages authorized by the USAEC and the Department of Transportation. Storage shall be in accordance with Technical Specification 4.10.1.2 until processing. Bases (change) Delete irradiated from second line.
.~ ';,"~'
.: .. I ~ .
";'~~'~/~~ sox 1 2 4 " ' W r , : S T V A L L E Y . N.Y. 14171 ARE:A coot:: 710 TELEPHONE 942-3235 July 27, 1971 Mr. R. E. Cunningham, Acting Director Division of Materials Licensing United States Atomic Energy Commission Washington, D. C. 20545 i ..<~,:.r. 1>1::. Cunningham: The follm~:tng inforT:lation is presented to supplement our request
,~'i July 12, 1971, for authorization to receive and store plutonium ni-trate solutions at the Hest Valley Processing Plant. The NFS Plant Sabry Com..'nittee has revieHed the proposed receipt and storage and believes that these actions can be accomplished in a safe manner using the plant's stan-dard operating procedures that have been developed during the storage and shipment of more than 1700 kilograms of plutonium as nitrate solutions.
The receipt p:1.d storage will be und8r the supervision of personnel possessing se:---ior licenses; however, since these operations will be in geometrically sat", c~*.'t:ainers, 1'1FS docs not believe the operators themselves should need specific At:: licenses. The shipping containers Fill be vented through fil-ters during stu:::'1ge. Subsequent transfer to prc.c. ~ss '~-ill be accomplished by operators licen ... :-r:l by the USAEC for plutonium l.oadout and will be under standard operating procedures approved by the Pla:'.t Safety Committee. Very tru y yours, Plant Nanager JPD:cp cc: E. D. North D. U. Shafer B. G. Bechhoefer
UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 10545 COP.Y August 30, 1971 Docket No. 50-201 Change No. 14 License No. CSF-l Nuclear Fuel Services, Inc~ ATTN: Mr. J. P. Duckworth, Plant Manager Box 124 West Vall~, New York 1417 And New York Atomic and Space Development Authority ATTN: . Mr. James Cline, General Manager 230 Park Avenue New York, New York 10017 Gentlemen: This refers to Nuclear Fuel Services' letters dated July 12, 1971 and July 27, 1971, requesting a change in the Technical Specifications of License No. CSF-l to authorize receipt and storage of plutonium nitrate-uranyl nitrate solutions at the West Valley, New York, facility. We reviewed the existing Technical Specifications and determined that changes in specification 3.1 and 4.10 would be necessary to authorize receipt and storage of plutonium nitrate-uranyl nitrate solution. In addition, we decided to take this opportunity to modify other portions of specifications 3.1, 4.10 and 6.1 in accordance with earlier NFS requests or as discussed with NFS personnel. We have determined that the changes in the Technical Specifications, as set forth in Change No. 14, do not present significant hazard consid-erations not described or implicit in the NFS Final Safety Analysis Report and that there is reasonable assurance that the health and safety of the public will not be endangered. A copy of the Safety Evaluation by the Division of Materials Licensing relating to Change No. 15 is enclosed. Pursuant to Section 50.59 of 10 CFR Part 50, changes to Technical Speci-fications 3.1, 4.10 and 6.1 of Provisions Operating License CSF-l (as set
forth on en:closed pages 5, 6, 7. 8. 35, 36, 36a, 57 and 58) are authorized and all Technical Specifications so designated previously are rescinded. FOR THE ATOMIC ENERGY COMMISSION (Original signed by Richard E. Cunningham) Acting Director Division of Materials Licensing
Enclosures:
- 1. Change no. 14, Rev. Pgs. 5. 6,
- 7. 8. 35. 36, 36a, 57 and 58
- 2. Safety Evaluation cc: Mr. B. G. Bechhoefer, w/encl.
Mr. G. M. Ruebhausen. w/encl. Dr. E. D. North. w/enc1. Mr. Robert N. Miller, w/encl. CO~y
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.-/'
Haterial 'ossession Licit
-Pom 'lutonium 62. Brams . a1 '1utoni= 14. crams .ealed source '1utonitD-242 6. crams any '1utonium-238 1. sram_3 ay Neptuniu::a-237 3.5 x 10_9 curie ay AmariciU3-241 1.1 x 10_7 curie any . .rici U3-241 6. a 10-6 curie .e&led source thalliu:ll-204 5. a 1O_S curie aDY Cesium-137 6. x 10 curie cry Caaiu=-137 33. curitt!S ..aled source Casi U!:J-l34 6. a 10_S curie ay Cerium-l44 3. a 10_6 curie any Iodine-l3l 6. a 10_6 curie ay Iodine-129 5. a 10_S curie lilly ltutheni e:1-l06 3. a 1O_S curie 1IIl1 Zircon!\Q-95 3. x 10_3 curie any Strontic-90 6. x 10_3 curie any Stronti\C-85 5. a 10 curie ay Krypto:l-85 3. curie! ... lilly Zinc-65 2. a1O- curie 'ay Cobalt-60 s. a10-2 curie lIllY Any byproduct material with ato~ic nucbers 3. x 10-6 curie any . from 3 to 85 inclusive each (at8Dge Ho. 14)
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- 36a-The consequence of using other than nuclearly safe systems for the storage of plutonium solutions is to provide a possibility for the occurrance of nuclear criticality in an unshielded area.
(Clange No. 14)
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)
SAFETY EVALUATION THE DIVISIO~ OF K~TERIALS LICENSING NUCLEAR FUEL SERVICES. INC. DOCKET NO. 50-201 RECEIPT AND STOP~GE OF PLUTONI~! SOLUTIONS Authorization Reouested By letter dated July 12, 1971, as supplemented by a letter dated"July 27, 1971, .Nuclear Fu~l Services, Inc. (~7S) requested a change in Technical Specification 3.1 of License No. CSF-l to allow the receipt and storage of plutonium nitrate-uranyl nitrate solutions at the West Valley plant. After review of the existing Technical Specifications it .was determined that changes should be made not only in Technical Specifications 3.1, Nuclear Fuel; but 'also in 4.10, Plutonium Solution storage and 6.1, Boron Raschig Rings. The modifications required in Technical Specifications 4.10 and 6.1 are similar to those requested by NFS by letter dated February 10, 1970 as part of an overall Technical Specification updating. Modifications to Technical Specification 6.1 were not necessary for receipt and storage of plutonium solutions at NFS, but were made because of the relationship between Specifications 4.10 and 6.l.*Hodifications to be made to Tech-nical Specifications were discussed with NFS personnel, and their verbal agreement to the changes was obtained on July 26, 1971. Authorization for receipt and storage of plutonium nitrate-uranyl nitrate solutions at the West Valley site has been granted by changes to Technical Specifications 3.1, Nuclear Fuel; and 4.10, Plutonium storage. Specification* 6.1 has been modified to be consistent with Specification 4.10. An additional change to Technical Specification 3.1. Nuclear Fuel,. was made to make it clear that NFS may possess 'quantities of materials exempt under the provisions of .10 CFR Part 30.18 in addition to larger quantities of radioisotopes specifically listed in the Technical Specifications for use as standards, and for tests, measurements and calibrations *
, 2
Background
As a result of past fuel fabrication activities at NFS' Erwin. Tennessee, facility. plutonium-depleted uranium scrap which has accumulated is being processed. The processing steps at Erwin are limited to scrap dissolution in nitric acid. concentration. and packaging in AEC approved shipping con-tainers. The plutonium nitrate-depleted uranyl nitrate solutions will be shipped to the NFS West Valley site and. at a later date, processed through the reprocessi~g plant for plutonium and uranium separation. purification and recovery. The present application for a change in Technical Speci-fications requests authorization only for receipt and storage of plutoniuo nitrate-uranyl nitrate solutions at West Valley. The safety evaluation for the proposed recovery operations at the West Valley plant and a
. request for changes in Technical Specifications to authorize the.recovery operations will be the subject of a future submission by NFS.
Safety Considerations
- 1. General*,
Operations involved in the receipt Antf Rt.I)TlIIge nf 1'1nt nn i,.11'! nitrate-uranyl nitrate solutions at the West Valley plant have been reviewed and approved by the 1rS plant safety committee. A standard operating procedure has been written and trained personnel will be used for the work. The safety considerations for the receipt and storage of the material are similar to those for the storage and shipment of plant produced plutonium nitrate solutions. Operations involved in receipt and storage of the solutions do not involve manipulation of contr~ls as defined in 10 CFR Part 55 thus licensing of operators is not required. .
- 2. Technical Specification 3.1. Nuclear Fuels .
Category 10. plutonium nitrate-depleted uranyl nitrate. has been added to the list of materials which NFS may receive at the West Valley site. The concentration limit of 250 grams per liter-of fissile plutonium corresponds to the limit placed on the shipping containers under the provisions of 10 CFR Part 71. Section 3.1.3 of the specification has been modified to allow receipt and storage of category 10 material but to prevent transfer of the material froo the ship.ping packages before AEC approval of NFS' proceSSing plan for the material is granted
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CHANGE NO. 15 UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 205~5 September 24. 1971 COp-y Docket No. 50-201 Nuclear Fuel Services. Inc. ATTN: Mr. Robert N. Miller President 6000 Executive Boulevard Suite 600 Rockville. Maryland 20852 and New York Atomic and Space Change No. 15 Development Authority License No. CSF-l ATTN: Mr. James Cline Genera 1 Manager 230 Park Avenue New York. New York 10017 Gentlemen: This is in response to the January 14. 1971 letter from Nuclear Fuel Services. Inc. (NFS). requesting authorization to operate the new low level waste treatment plant. The new plant was described in a Final Safety Analysis Report submitted with the January 14 letter and in Supplement 1 submitted by letter dated April 2. 1971. Based on our review of the information contained in the NFS submittals and discussions with the NFS staff and in accordance with the objective of reducing the quantity and concentrations of radioactivity in liquid effluent from the NFS facility. we have. in connection with the authori-zation sought; revised the Technical Specifications of License No. CSF-l to incorporate Technical Specifications related to operation of the main plant ant to the low level liquid waste treatment plant and to discharge of effluents to the watershed. In connection with the operation of the low level waste treatment plant the following interim reporting requirements shall apply?
- 1. A report every six months giving information on personnel radiation exposure associated with the operation of the new facility.
- 2. A report every six months giving.information on the ruthenium decontamination factors achieved during operation of the new facility, and a description of stUdies or changes made by NFS to improve ruthenium removal or control capability.
COpy
Nuclear Fuel Services, Inc. and New York Atomic and Space CO~y Development Authori~ The time periods for the above listed reports shall start on the effective date of the revised Technical Specifications. On the basis of our review, we have concluded that the changes in the waste treatment system will substantially reduce the quantity and concentrations of radioactivity in liquid effluent from the NFS facility. A copy of the Safety Evaluation by the Division of Materials Licensing of the new low level waste treatment plant is enclosed. Accordingly, pursuant to 10 CFR Parts 2, 20 and 50, Change No. 15 in the Technical Specifications of License No. CSF-l, as set forth on the enclosed pages 15 through 16c, 42a, 44 through 46g, 63 and 72 revising previous Technical Specifications 4.2, 4.14, 5.1, 6.5 and 7.1 shall become effective twenty (20) days from the date of this letter. Until Change No. 15 in the Technical Specifications of License No. CSF-l becomes effective, test operation of the low level waste treatment plant may be conducted in accordance with the presently effective Technical Specifications. Pursuant to the Commission's Rules of Practice in 10 CFR Part 2, you may request a hearing with respect to all or any part of this change in the Technical Specifications within twenty (20) days from the date of this letter. FOR THE ATOMIC ENERGY COMMISSION Richard E. Cunningham Acting Di rector Division of Materials Licensing
Enclosures:
- 1. Change No. 15 including Rev. pp. 15 through 16c, 42a,
- 2. Safe~ Evaluation cc w/encl:
Mr. B. G. Bechhoefer Mr. O. M. Ruebhausen Mr. J. P. DUckworth COP-.Y
-~-.---.,--- ,------------_. -! ----_.------ ----- - "-"15 -
4.2 RADIOACTIVIT!' OONTENT OF RELEASED LIQUID EFFLUENTS APPLICABILITY This i. an interim specification which applies to radioactivity contained in liquid effluents from the site. OBJECTIVE __________________________________________________ To limit the concentrations of rad~activitv in liquid effluents discharged from the site. SPECIFICATION 4.2.1 ALL PROCESS STEAM OONDENSATE SHALL BE OOLLECTED BATcmnsE AND SA."IPLED FOR TOTAL ALPHA AND BETA ACrIVITY. 'nIE CO!'.'DEN-SATE l-IAY BE DISCARDED tnnlOtrr PASSING TIlROUGlI TIlE nrrERCEP-TOR, STORAGE LAGOON OR LO'..T LEVEL WASTE TREATHENT PLA.~ IF IT HAS BEEN DETERmNED TllAT TIlE TarAL ALPHA PLUS BETA ACTIVITY IS LESS nIAN 3.0 X 10- 7 MICROCURIES PER l-IILLILITER (EXCLUDING
'l'RITltn-f)
- 4.2.2 LAUNDRY WASTE SHALL BE OOr..LECIED BATCnUISE AND SA!-!PLED FOR TOTAL ALPHA AND BETA ACTIVITY. mlS WASTE !dAY BE DISCHARGED TO THE LAGOONS DOl*1NSTREAM OF mE Wl" LEVEL WASTE TREATIfENT PLANT II THE TOTAL ALPHA PLUS BETA ACTIVITY IS LESS THAN 1 X 10- MICP~CURIES PER MILLILITER.
4.2.3 A. EXCEPT AS PROVIDED IN 4.2.3 B, ALL OTttER LIQUID WASTES CONTAUllNG RADIOACIIVITY OR lmICH HAVE BEEN IN CDNTACT WITH EQUIPfotENT COl.'TAINING RADIOAcrIVITY SHALL BE OOLLECTED BATCliWISE IN nIE INTERCEPTORS. ANALYZED
- - - - - - - - - - -.- ----... -lOR TarAL ALPHA PLUS BETA RADIOACTIVITY, AND TREATED IN THE IDll LEVEL WASTE TREAT}fENT PLA.-rr.
I. IF THE TOTAL RADIOACTIVITY OF WASTE IN THE INTERCEPTOR IS GREATER THA.'i S.O X 10-3 MICROCURIES PER MILLILITER (EXCLUDING TRITImf), nIE WASTE SHALL BE TP.ANSFERRED _"-- lAC( TO T1lE !-IAIN PLANT lOR FORnIER TREAntENT OR STORAGE.
. 4.2.4 IF DURING OPERATION OF THE WASTE TREATMENT PLANT, THE FLOCCULATION, CLARIFICATION, OR ION EXaIAl'~GE SECTIONS OF (Change No. IS)
\
I _ 16 - THE LOW LEVEL WASTE TREAn*IENT PLANT ARE BYPASSED. THE TREATED WATER SHALL BE RECYCLED TO THE FEED OF THE LOW LEVEL WASTE TREATMENT PLANT. 4.2.5 TREATED WASTE lfAY BE DISCHARGED FRo.'! nm LAGOON SYSTEM PROVIDED THAT THE RADIOACTIVE CESIIJl-1 .A..'iD STRONTIUM CO:~CEN TRATIONS IN TllE WASTE AT THE POINT OF DISCHARGE FROM THE
-- ----..- ------ ---LAGOON SYSTEM -DO NOT'-EXCEED- VALUES-THAl'- SATISFY-THE -SUM OF-----
THE FOLLOWING RATIOS:
- - - - - ' - CCs.;.1l4 -+---. CC-s';'"!37 - -.~+--- ,CSr- 89 --' --+ - CS r;.90 ! 1 9 X 10-6 2 X 10-5 3 X 10-6 3 X 10- 7 . _. ________ . WHERE C
- CONCENTRATION. IN MICROCURIES PER MILLILITER. OF THE INDICATED ISOTOPE IN THE TF~TED WASTE.
IF THE CONCENTRATIONS OF CESItjH .A..'iD STRONTIUH RADIOISOTOPES PElUUTTED BY THIS SPECIFICATION ARE EXCEEDED. THE LICENSEE SHALL: (a) TAKE SUCH ACTION AS IS NECESSARY TO COME INTO PRO}~T COMPLIA.~CE WITH Tl'.E_ TECHNICAL SPECIF'lCATIONS._ __ __. ______ ._ (b) MAKE AN INVESTIGATION TO IDEIITIFY THE CAUSE OR CAUSES FOR SUCH LEVELS OF RADIOACTIVITY. (c) DEFINE AND INITIATE A PROGRAM OF ACTION TO REDUCE SUCH LEVELS. AND (d) REP OR! THESE ACTIONS TO THE co~naSSION ON A TIMELY BASIS. SUBJECT TO TIlE PROVISIONS OF 4.2.6. TRITIUH AND RUTHENIUM 106 MAY EXCEED. AT THE POINT OF DISCHARGE FROM THE LAGOON SYSTEM. THE RESPECTIVE CONCENTRATIONS LISTED FOR THESE NUCLIDES IN APPENDIX B. TABLE II. 10 CFR PART 20. 4.2.6 RADIOACTIVITY IN CATTARAUGUS CREEK RESULTING FROM THE DIS-ClIARGE OF ALL LIQUIDS FROM THE SITE IS DJ-:TERMINED FROM WEEKLY CO~~OSITE SAMPLES TAKEN IN ACCORDANCE WITH SPECIFICATION 5.1.1. IF THE RADIOACTIVITY IN CAITARAUGUS CREEK AS DETERMINED FROM SUCli SA}~LES(S) EXCEEDS: (1) TWENTY PERCENT (20%) OF THE PRORATED CONCENTRA-TIONS LISTED IN APPENDIX B. TABLE II. 10 CFR PART 20 FOR ANY SAl-~LE. OR (Change No. 15)
16a - _(~)' TEN PERCENT (10%) OF THE PRORATED CONc~rrRA-
--- . -------- --.. - --lIONS LISTED n~ APPENDIX B. TABLE II, 10 CFR PARI 20 AVERAGED OVER ~~ QUARTERLY PERIOD.
THE LIC~SEE SHALL: (a) TAKE SUCH ACTION AS IS NECESSARY TO COME INTO
.: PRO~IPT COMPLIAlJCE WITH THE TECHNICAL SPECIFICA-TIONS.
(b) MAKE AN INVESTIGATION TO IDr:~rrIFY THE CAUSE OR CAUSES FOR SUCii LEVELS OF RADIOACTIVITY. (c) DEFWE ~m INITIATE A PROGRAl*I OF ACTION TO REDUCE SUCH LEVELS. A..'lD (d) REPORT THl::SE ACTIO~~S TO TllE cmlHISSIOil O~~ A TUlELY BASIS. BASIS These specifications limit:
---- the- total radioactivity transferred to the storage--Iagoons----- --------
from the main plant. the cesium and strontium radioactivity in the waste dis- _charged from the lagoon systea after treataent in the low level liquid waste treatment plant and the concentration of radioactivity in Cattaraugus Creek. After treatment in the low level liquid waste treatment plant the dominant radioisotopes in the liquid effluent are expected to be ruthenium and tritium. The tritium is -not affected by the treat-ment system and the ruthenium is not effectively removed by the present treatment system. This is an interim specification in that the ultimate objective of liquid waste control is to reduce radioactivity discharges to as low a level as is practicable for all isotopes in liquids at the point of release from the lagoon systems. Additional treatment or other disposal methods may be needed in the future to.meet the obje~tive. 4.2.1 Process steam condensate is normally expected to be free of radioactivity. This effluent may be discharged to the envi-ronment if it has been determined that the total radioactivity content is less than the 10 CFR 20 limit for strontium-90. - (Change No. 15)
'. " _-:-1...-. _.~_ -j
- l6b -
one of the most restrictive isotopes which could be expected to be found in liquid wastes from reprocessing plants. The 10 CFR Part 20 limit for strontium-90 is ten to one hundred times smaller than the limi t for other isotopes which would also be present in the condensate should a contaminating leak occur in a steam heating system. Thus use of the strontium-90 limit assures that the condensate released will always be
---belOli -the-1CLCFR-20 l1mi t.-fo~y-1.aotopeL.Wh:1.c:h--llligh t-b.e. _ _ _ _
present.
~_._~,_2_ .Laundry waste_contains small quantities of radioactivity. It also contains phosphates and complexing agents which may inter-fere with the proper operation of the lu~ level liquid waste treatment plant. This waste, therefore. is discharged down-stream of the low level waste treatment plant.
The quantity of laundry waste is less than 10% of the total current low level liquid waste volume generated, and the activity level is about 5 X 10-5 microcuries per milliliter total beta. Both strontium and cesium are expected to be below their respective Part 20 .~C values in the undiluted waste. Experience indicates that the total beta activity carried by this stream is about 1 millicurie per day. This
---{s"'predominantly ruthenium-106 with cesium-137 and strontium-90 amounting to about 18 and 4 microcuries per day respectively.
Release of this waste without treatment will not substantially increase the total radioactivity release. the laundry waste will be collected batchwise and sampled to assure that it does not exceed 1 X 10- 4 microcuries per milli-liter total alpha plus beta activity. Release of laundry waste at this concentration would result in a whole body exposure to a suitable sample of the population (as shown in the Comadssion Safety Analysis) of 0.033 mrem/year. 4.2.3 Other liquid wastes (including water from the high level solid waste burial ground) which contain or may be suspected to con-tain radioisotopes will be treated in the low level liquid
.>- waste treatment plant. The radioactivity in the feed to the treatment plant (via the interceptors and lagoon system) is limited to prevent excessive radiat10a levels near the lagoons and 1n the waste treatment plant, and to prevent overloading the 1011 level waste treatment facility.
4.2.4 Except as specified in 4.2.2 all waste transferred to the lagoon system will be processed through the waste treatment plant to assure that as much of the radioactivity is removed as is (Change No. 15)
16c - practicable with the installed equipment. For this same
--------------reuon. all process steps in the waste treatment plant 8USt be operating if the effluent is to be released from the lagoon system. During periods of process upsets or failures.
the low level treatment plant effluent will be recycled. 4.2.5 the low level waste treatment plant is designed specifically to rempv.e"~~s_ium_ 811_cLs_;r~~tium.J~_~I!!~he_.!I_q",e"ous _~~_t"e_~ ._"-frEP~r_ __ operation and control of the low-level liquid waste treatment plant. including continuous monitoring for Cs-l37 at the exit of the ion-exchange unit. should assure that the concentrations of strontium and cesium are within specification limits" at the-time of discharge. Analyses for strontium-90 require time delays for the buildup of yttrium. Compliance with Specification 4.2.5 will be based on analytical results obtained after the waste has been released from the lagoon system.
-- 4.2.6 Ruthenium and tritium are isotopes present in significant quantities in the waste transferred from the main plllIlt and which will not be effectively removed by the waste treatment plant. Until additional treatment or other disposal is pro-vided for these isotopes. they will be present in greater
"~han MPC limits in the"lagoon effluents and \dllbe the predominate radioisotopes in Cattaraugus Creek. The con-concentrations of radioactive strontium and cesium in Cattaraugus Creek will be low; about 0.1% of the respective 10 CFR Part 20 limits. The action values given in Specification 4.2.6 are based on the recognition of the limitations of the present waste treatment system. The specification requires prompt action on the part of NFS to investigate releases above the predetermined values and to define and initiate corrective action *
(Change No. "lS)
- 42a -
4.14 EXHAUST FILTER DIFFERENTIAL PRESSURE Applicability This specification applies to the maximum differential pressures that may be maintained across the absolute filters in the exhaust ventilation systems. Objective
- - - --To minimize the probability of filter failure in exhaustventllation systems.
Specification 4.14.1 THE SUSTAU,ED OPERATING PRESSURE DIFFERENTIAL ACROSS Any ABSOLUTE FILTER IN ANY OF THE EXHAUST VENTlLATIOl: SYSTE}!S SHALL NOT EXCEED 85% OF TIlE GREATEST PRESSURE DIFFERENTIAL AT WHICH
- '!HAT FILTER HAS BEEN TESTED.
Basis
.____ High Efficiency (absolute) filters are used in the plant's ventilation systems (Dissolver Off-Gas, Vessel Off-Gas, Main Building, Head End, Waste Tank Fam, DOG-VOG Backup and La\07 Level Waste Treatment Plant).
The absolute filters act as the final containment of radioactivity prior to discharge to the plant stacks. The service of the absolute filters is limited by this specification to minimize the probability of filter failure. Specification 4.14.1 pertains to sustained service of the absolute filter; it is recognized that transient flow variations may cause differential pressure excursions exceeding the 85% limits as - - - - . - - - - end of service life approaches. The specifications for all absolute filters used at NFS include the common strength requirement that the absolute filter withstand a pres-sure drop of at least 10 inches W. G. without tearing or deforming. All absolute filters used at ~~ are tested by the manufacturer to a pressure differential of at least 10 inches W. G* - ________________ . '0. (Olange No. 15)
--- - . 5.1 EFFLUENT A!-."D ENVIRONHENTAL l-KllUTORING Applicability this specification applies to the sampling and analysis of gaseous and liquid plant effluents and to environmental monitoring.
---'Objective .
To establish sampling points, s~ling frequency and sample analyti-cal requirements for gaseous and liquid plant effluents and to establish an environmental monitoring program and reporting requirement. Specification 5.1.1 WHENEVER LIQUID IS DISCHA.1tGED FRO:! THE STORAGE LAGOO~~S, A REPRESENTATIVE SAliPLE SHALL BE WITHDRA~JN BY THE CATTA.~UGUS CREEK CONTINUOUS SA!*!PLER. AT LEAST EVERY SEVEN DAYS, A CO~! POSlTE OF nns SAl-IPLE SHAI.L BE .A:~ALYZED FOR TRITlt.r.i, RUTHENIUU 106, TOTAL ALPHA AND TOTAL BETA RADIOACTIVITY. IF THE CONTINUOUS SMIPLER BECOHES INOPERATIVE, UP TO 2,000.000 _________________ GALLONS llAY BE DISCHARGED FROll THE LAGOONS IN ANY ONE-YEAR PERIOD PROVIDED CATTARAUGUS CREEK SAll'J.ES AIlE COLLECTED NEAR TIlE CONTIlmOUS S~;PLER LOCATION f'OR EACH LAC.om~ DISCHAr..GE OR FOR EACH 100,000 GALW:-lS OF DISCHARGE, "lHICHEVER RESULTS I!~ niE GREATER SA!IPLING Fl'-EQUENCY. SA,'IPLES SO COLLECTED SHALL BE INDIVIDUALLY A.~ALYZED FOR TRITIUH. RUTHENIUH 106. TOTAL ALPHA AND TOTAL BETA RADIOACTIVITY. 5.1.2 THE RADIOACTIVITY IN STACK EFFLUEh~S SHALL BE CONTINUOUSLY SAMPLED. niE SMIPLES SHALL BE ANALYZED AT LEAST EVERY SEVEN DAYS FOR IODINE 131 A,.'qD PARTICULATE RJI.DIOACTIVITY. IF THE STACK SA!-:FLER BECOHES INOPERATIVE, n~lEDIATE REPAIR SHALL BE INSTITUTED TO RETURN THE SAMPLER TO SERVICE. IN ADDITION 1'0 THE WEEKLY S~1PLES OBTAINED FROU THE STACK *
.- THE 1-131, KR-S5 AND PARTICULATE P.ADIOACTIVITY IN THE STACK GAS SlIALL BE CONTINUOUSLY SUBJECT 1'0 DETECTION BY A STACK MONITOR.
* (atange No. 15)
- - THE PERCENT OF 10 cn 20.l06a LnfITS FOP. RADIOACTIVE STRONTIUH AND CESIID1 ISOTOPES IN CATTARAUGUS CREEK AVERAGED FOR EACH RF.5PECTIVE !-tONTH OF TIlE REPORTING QUARTER.
L) qJRIES OF PARTICULATES DISCHARGED VIA THE STACK FOR EACII H>NTH. M) THE PERCENT OF nIE HONniLY TECIINICAL SPECIFICATION LIHIT FOR DISClIARGE OF PARTICULATES VIA niE STACK. N) THE HAXIHUH PERCENT OF THE KIt-85 DAILY TEcn~ICAL SPECIFI-CATION LImT IN TIlE STACK EFFLUENT FOR EACIt MONTlI.
- 0) nIE C!Jl*ruLATIVE PERCENT OF nIE 1-131 YEARLY TECHNICAL SPECIFICATIO~ LIMIT IN THE STACK EFFLUElIT REPORTED ON A HONTULY BASIS.
-Basis Effluent '!onitoring
___________~_amples of_water frot!. Cattaraugus _Creek are taken _with a continuous ______ _ sampler located about one-half mile do~mstream from the confluence of Cattaraugus and Buttermilk Creeks. Portions of each weekly sample are composited to product a sample representative of one month '8 discharge. The ,,,eekly samples are analyzed for gross alpha, gross beta. tritium and ruthenium 106. The composite is analyzed for gross alpha, gross beta strontium 90. strontium 89, cesium 134, cesium 131, ruthenium 106 and tritium. A stream gage located near the sampling station is used to deteroine total flow in Cattaraugus Creek. Flow from the lagoon is determined by a calibrated weir located on the discharge line. The flow ratio 18 used in conjunction with the iodine 129 analysis of lagoon water to calculate the iodine 129 content in Cattaraugus Creek. Caseous plant effluents are sampled in the plant stack. The stack sampler contains a filter to collect particulates and an activated charcoal filter to collect iodine 131. Samples are removed from the stack sampler at least each week and analyzed. The stack monitor is used to continuously determine the particulate, iodine 131 and krypton 85 radioactivity in the stack air and to alert operators if pre-set limits are e~ceeded. The particulate sampler i8 changed every 8 hours and will alarm if the accumulation of particulate radioactivity over an 8-hour period exceeds that which (Olange No. 15 )
I.. * , i - 46. -
- --- -- would occur if particulates were being discharged over the same time -
period at the limit set by Technical Specification 4.1. The iodine 131 monitor. a carbon filler paper absorber. is changed on
- weekly cycle. The instrument is set to alarm if. over a week's ~eriod. the counting rate increa~es 10.000 counts/Dinute. This is far below the increase in count rnte (about 400,000 counts/minute) which would occur if iodine were released for one week at
- rate of 1/52 of the
- - - - ----yearly technical specification limit. The kr)'llton 85 monitor is set-- - - ---
to alarm if the counting rate exceeds five times the background rate. The alarm point is not, in this case~ directly related to allowable release rates. The instrument will alarm only during periods of high krypton 85 discharge, for example during dissolution of high burn-up fuels. 5.1.4 THE LICENSEE SHALL CO:mUCT THE ENVIROmlENTAL HO:UTORI~G PROGRA.."f GIVEN IN TABLE 5.1 AND SHALL REPORT THE RESULTS OBTAINED AT nm END OF EACH SIX-KO:ml PERIOD BECI!::II:~G FRO:*I JANUARY 1, 1971. SUCH REPORTS WILL BE DUE WITllI~r 60 DAYS ,\FTER nIE END OF EACH REPORTING PERIOD. IF QUA:{TITIES OF P.ADIOACTIVE HATE-RIAL RELEASED DURWG THE REPORTING PERIOD ARE mmSUAL FOR NOPJiAL FLA.\"! OPERATIONS, INCLUDING EXPECTED OPER...TIONAL OCCUR-RENCES, nm REPORT SHALL COVER THIS SPECIFICALLY *
.~---
(Change No. 15)
- r, ....
-46b -
---------- - ----- - TABLE 5.1-EFFLUENT AND ENVIRONUE~AL HONITORING PROGRA."I A. The licensee shall determine for each month, based on samples taken at the indicated location and other information collected during the
---'---:'lIOiitn~- the-following:
i Total curies of beta radioactivity other than tritium
- ---- released at effluent weir. - - ------ --- --- ---- - - - - - - - - - - -
ii Total curies of alpha radioactivity released at the effluent weir. iii Curies of tritium released at effluent weir. iv Curies of strontium 90 released at effluent weir. v Curies of cesium 134 released at effluent weir. vi Curies of cesium 137 released at effluent weir. vii Curies of ruthenium 106 and rhodium 106 released at effluent weir. viii Volume of water released at effluent weir. 1x Volume of water flow through site in Cattaraugus Creek. x Curies of beta emitting particulates released via the stack. xi Curies of alpha emitting particulates released via the stack. xii Curies of iodine 131 released via the stack. xiii Curies per cubic meter gross beta radioactivity of particulates _-'- -- (average and maximum) collected by each of the 3 site perimeter samplers on filter paper. xiv Curies per cubic meter gross alpha radioactivity of particu-lates (average and maxi~um) collected by each of the 3 site perimeter samplers on filter paper * (Otange No. 15)
* *I
-46c -
B. The licensee shall determine each quarter. based on samples and other information collected during the quarter. the following: 1 Identity of principal radionuclides whose presence can be determined by gamma spectroscopy of a sacple (one per calendar quarter) of Buttermilk Creek bottom silt collected at the Thomas Corner Road bridge. 11 Microcuries per gram total beta radioa-ctivity of a-sample-(one per calendar quarter) af Buttermilk Creek bottom silt collected at the Thomas Corner Road bridge. iii ~acrocuries per gram total alpha radioactivity of a sample (one per calendar quarter) of Butte~ilk Creek bottom silt collected at the Thomas Corner Road bridge. iv ~acrocuries tritium per milliliter of water collected once per quarter at the Butterailk Creek silt sampling location during a normal liquid effluent release from the plant. v Microcuries total beta radioactivity per milliliter.of water collected once per quarter at the Buttermilk Creek silt sampling location during a normal liquid effluent release from the p l a n t . - - - - - - - - ---------- -- ----- vi Microcuries total alpha radioactivity per milliliter of water collected once per quarter at the Buttermilk Creek silt sampling location during a normal effluent release from the plant. vii Curies of stronti~ 89 released at the effluent weir based on an analysts of a composite of the liquid released during the last month of the quarter. viii Curies of zirconium 9S and niobium 9S released at the effluent weir based on an analysis of a composite of the liquid released during the last month of the quarter. Ix Curies of iodine 129 released at effluent weir. x A quantitative analysis of alpha emitting components in a quarterly composite collected at the effluent weir. (Olange No. lS)
-- --"'r--- - .-- -----------.- '" .. --.---
- 46d -
xi The exposure, in megawatts days, of fuel dissolved durins the quarter. xii The curies of krypton 85 released via the stack as determined using the stack monitor. xiii Curies of tritium released via the stack. xiv Curies of iodine 129 released via the stack.
-xv----Curies of -strontium 89 released via the stack.
xvi Curies of strontium 90 released via the stack.
-------- ---- xvii Curies of ruthenium 106 released via the stack.
xviii Curies of cesium 134 released via ~he stack_ xix Curies of cesium 137 released via the stack. xx Microcuries per milliliter tritium (average) in precipitation collected at each of the 3 site perimeter sampling stations_ xxi Milliroentgen of radiation (including background) accrued each quarter at each of the 3 site perimeter sampling stations. xxii The maximum value at ground level offsite in each w/8 sector about the stack of the X/Q integrated for each aeasonal quarter from hourly averages of continuously recorded meteorological data. The X/Q shall be determined using equation 3.144 given on page 113 of Heteorology and Atomic Energ)- (1968) _ Seasonal
----.. --_.. _. ----. "---.-.----. quarters are defined as:
Spring March through May Summer June through August Fall September through November Winter December through February xxiii
---The curie seconds per cubic meter maximum exposure of Y.r-85 integrated for the reported quarter at ground level offsite in each ./8 sector about the stack, computed from meteorological data recorded during emission of the respective increments of Kr-85 that register above background on the Kr-85 stack gas monitor.
(Otange No _ 15)
(' .' 46e -
- c. The licensee shall determine the following information according to the schedule given:
1 If. during any week from April to October, inclusive, the release of iodine 131 from the stack exceeds 30 millicuries, the licensee shall determine the microcuries per milliliter of iodine 131 in samples of milk from farms within 2-1/2
------------1I11es of -the plant in each direction expected to receive the release. One sample shall be collected each week for the four weeks following the release.' Each sample shall be a composite of one day's producticn from cows which are on pasture.
ii During August of each year the licensee shall collect a milk sample from a farm within 2-1/2 miles of the plant in the north-west sector and a milk sample from a fllnn within 2-1/2 miles of the plant in the north-east sector. The samples shall be composites of one day's production from cows which arc on pasture. Each sa~ple shall be analyzed separately to determine: a) Microcuries iodine 129 per ailliliter _______________ b) _ Microcuries strontium 90 per millili_ter __________________ _ e) Microcuries cesium 134 per milliliter d) Microcuries cesium 137 per milliliter iii During the second a~d third quarters of each year, licensee shall take fish samples from Cattaraugus Creek between the Springville hydroelectric dam and the Cattsraugus Crcek-Buttermilk Creek confluence. One sample shall be taken during each of the ~IO quarters. A saaple shall consist of at least 9 fish. each at least six inches long. Each fish in each sample shall be analyzed to determine: a) Median and geometric deviation of cesium 134 micro-curies per kilogram of flesh
- b) Median and geometric deviation of cesium 137 micro-curies per kilogram of flesh.
c) Median and geometric deviation of strontium 90 micro-curies per kilogram of flesh * (Olange No. 15)
I*t ** ' 'f.
- 46f - ------------d)-Median and geometric deviation of strontium 90 micro--
curies per kilogram of skeleton. iv ODce per year the licensee shall determine the following from a deer taken onsite during the hunting season and taken. preferably. north of the plant:
.) l<<crocur1ea-cesiU1ll l31t-pe-r:kUogralll-of-flesh-:-.-------
b) Microcuries cesium 137 per kilogram of flesh. c) Microcuries strontium 90 per kilogram of flesh. d) Microcuries strontium 89 per kilogram of skeleton. e) Microcurie. strontium 90 per kilogram of skeleton. D. The environmental reports to be prepared by the licensee shall contain descriptive material covering the environmental surveys per forced during the reporting period including information on: i The number and types of samples taken; e.g ** air. surface water. soil,- fish. - --------- - - - - ii The number and types of measurements made. iii Locations of the sample points and monitoring stations. 1v The frequency of the surveys. v A summary of survey results. E. If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 3% of those that could result from continuous exposure to the concentration values listed in Appendix B. Table II. Part 20. estimates of the likely resultant exposure to individuals and to population groups. and ASsumptions upon which estimates are based should be provided.
- r. If statistically significant variations in offsite environmental concentrations with time are observed. correlation of these results with effluent releases should be provided *
(Olange No. IS)
( ',... ...
- 46g - ---- - - ---- -Basis Environmental Monitoring The environmental survey incorporates measurements to provide background data and measure possible plant effects. Samples collected at poi~ts where concentrations of effluents in the ---------env:1ronment are expected to be greatest* will be compared with - .- -----------
samples collected concurrently at points expected to be essentially unaffected by station effluents. The latter samples will provide background measurements as a basis for distinguishing significant radioactivity introduced into the environment by the operation of the plant from that due to other sources such as nuclear detonations. This schedule will assure that significant changes in the environ-mental radionctivity are sampled most frequently. Those which are less affected by transient changes but show long-tere accumulations are sampled less frequently. The ~onitoring program will be reviewed and re-evaluated periodi-cally after data such as cOr.lposition, quantity and frequency of releases, dilution factors and measured concentrations in food
--- and other organisms (if any are observed) are obtained. -- -----------------------
.-~ ...- .-
_ _(Clange c- No. IS)
~-------------
r , ... I 1-,"
*------*6.5 AIR FILTRATION EQUIPMENT ----. - --.-. -- -- ------------------
Applicability This specification applies to surveillance requirements for the final air filters in the-off-gas and ventilation systems.
------Objective To assure proper performance of the final air filters used in the plant. -- . -- . - ---- -- - - -- --- -.- -- .. --.- ---.-. --- -------- ---.-.---
Specification 6.5.1 IF ANY OF THE FILTERS SUa.r.~ BELOW ARE CHANGED OR HODIFIED, mEY SHALL BE TESTED, PRIOR TO ROUTINE SERVICE, WITH PARTICULATES OF AN APPROPRIATE SIZE TO ESTABLISH 'l1!AT THE INSTALLED FILTERS PROVIDE A COLLECTION EFFICIE1,CY OF AT LEAST 99.95% FOR PARTICULATES 0.3 MICRONS IN DIA:*1ETER OR LARGER. .. - - - --. - -- --- - - --I' -- SYSTEM FILTERS _DISSOLVER OFF-GAS 6T-l, 6T-IA VESSEL-OFF-GAS 6T-2, 6T-2A WASTE TANK OFF GAS 8T-l, 8T-1A MAIN BUILDING 15T-49, lST-49A DOG-VOG BACKUP 6T-3, 6T-3A HEAD END 15T-72, l5T-72A, 15T-73, IST-73A LOW LEVEL WASTE TREATMENT PLANT 479-401-B, 479-402-B 6.5.2 mE DIFFEP~NTIAL PRESSURE ACROSS THE FINAL OPEP~TING ABSOLUTE nLTERS (OR ABSOLUTE nus ROUGHING WHERE THE FILTERS ARE WITHIN TItE SAME FlWIE)' SHALL BE RECORDED BY niSTRtr.-lENTATION. 6.5.3 ALARMS SHALL BE PROVIDED TO A.'tNUNCIATE HIGH DIFFEtmlTIAL PRESSURE ON mE FINAL OPERATING ABSOLUTE FILTERS OF THE HAIN BUILDING, HEAD END, WASTE TANK Fml AND DOG-VOG BACKUP SYSTEMS. mESE ALARHS SHALL BE SET TO Ao'lNUNCIATE AT LESS nIAN 75% OF nIE GREATEST DIFFERENTIAL PRESSURE AT ~IICH ntAT FILTER HAS BEEN TESTED. 6.5.4 AN ALAR."l SHALL BE PROVIDED TO ANNUNICATE LOIol DIFFERENTIAL PRESSURE ON THE FINAL OPERATING ABSOLUTE FILTER IN TIlE MAIN BUILDING. (Change No. 15)
- * ._ ------'7'
* ..,...-.----- 6 ____
- _ . __ *** -- - .~-
-- - --.~ -- .... - -'- . -. , .. _--- -- .... __. - . ,~;~-~-~-,;*,i*- .. --- -,--- ---- .-... - .
7.1.4 DETAILED WRITTEN PROCEDURES. RUN SHEETS. LETTERS OF AUTHORIZATION AND EXTENDED WORK PROCEDURES SHALL BE PROVIDED FOR OPERATIm: OF 'mE PLANT. IN ADDITIO~ t PROCEDURES FOR HAl'.'DLING AB~OR!-jAL OPERATING CONDITIONS AND FOR RADIATION PROTECTIOU SHALL BE PROVIDED. 7.1.5 LOGS AND RECORDS SHALL BE HAI!ITAINED AS REQUIRED BY
- ..--.--------- -----mE--PROVISIONAL- LICENSE-AND* SlrJ\LL- !t;CLt.'DEMIliUTES OF NEETDIGS----
OF 'mE PLIIlIT SAFETY COll:1ITTEE lIS WELL AS DETAILS OF INVESTI-GATIONS AND p.ECO!-lZmNDATIONS IN REGA.1ID TO ABNORHAL OCCUP~'tENCES
. - AND 'ACTIONS T.AKE~: TIlEr-EON *. -
7.1.6 AUDIT OF OPERATIONS. H!lNAGEHE~IT SHALL PROVIDE FOR PERIODIC AUDITS OF THE OPERATImlS TlIROl:GHOUT TIlE ENTIRE
--- ----- .. -.- - -.. - - - FACILITY 'UTH REGARD TO RADIOLOGIC,\L A-'iD NUCLEAR SAFETY.
THESE AUDITS SHALL BE PERFOll}~ED BY COHPETENT CO~!PA:N OR onlER TECHNICAL PEusmiNEL NOT DIRECTLY RESPO:;SIBLE FOR
'mE OPERATIml AUDITED.
7.1.7 IF A,.W TECHNICAL SPECIFICATIO:~ LUIIT IS EXCEEDED, THE FOLLO'..1ING PROCEDt:!'-ES WILL BE OnSE1?VED:
- - - 7.1.7.1-nlHEDIATE STEPS SHALL BE TAKEN IN THE OPERATIOn OF TltE SYSTEM INVOLVED TO RF.?-IOVE THE CAUSE OF EXCEEDING THE SPECIFICATION on TO RELIEVE ITS EFl"ECT t AS APPf.OPRIATE. OPERATION }'AY CO:,TU;"UE IN A "READY CONDITION" TE1'!I'ORARILY UNLESS THEP..E IS A.~OTHER occupnNCE o~ INDICATION OF A.~ or.ClJF.P.F.NCE THAT UOULD FURTHER REDUCE TIlE rtARGIN OF SAFETY IN mUCH EVENT IMMEDIATE SHUTOOl-lN IS REQUIRED.
--- - - - . - --.---.-----.- ---- 7.1.7.2 Il'!MEDIATE STEPS SltALL BE TA-1{EN TO ESTABLISH
'l'HE CAUSE OF mE OCCURRENCE I~t 7.-1. 7.1 BY RESPONSIBLE MANAGEMENT REVIEW.
7.1.7.3 NOTWITHSTANDING A,.~ OTHER PROVISION OF THIS LICENSE mE PLA.~T SHALL BE SHUTD(UN A,.~D NORHAL PRO-CESSING OPERATIONS NAY NOT BE REStlHED PRIOR TO AEC REGULATORY CONClJRRENCE WREN SPECIFICATION 4 .1.1 HAS BEEN EXCEEDED * (Change No. 15 )
Safety Evaluation The Division of Haterials Licensing Nuclear Fuel Services, Int:. Docket No. 50-201 LoW Level Waste Treatment Plant
*Authorization Reguested By letter dated January 14, 1971, supplemented by additional information submitted on April 2, 1971, Nuclear Fuel Serv.1ces, Inc. (NFS) submitted their description and safety analysi.s relevant to the design and construc- ~1on of naT facilities for the reduction of radioactivity contained in low level liquid wastes and requested authorization for operation of the new facilities. Authorization for operation of the Low Level Waste Treatl!*ent Plant haa been granted by chanp,es in Technical Specifications 4.2 Radio-activity Content of Released Liquid Efflucnto. 4.14 Exhaust Filter Differential Pressure, 5.1 Effluent and Environmental Monitoring, 6.5 Air Filtration Equipment and 7.1 Administrative Requirements.
Background
Since the plant began operating in April 1966, the concentrations of radio-active materials in Cattaraugus Creek reSUlting from discharges of low level liquid wastes from the site have been higher than were projected in the NFS Final Safety Analysis Report. In a letter to NFS dated Kay 31. 1968, the Commission stated that releases from the NFS plant should be Sig-nificantly reduced. In reply. NFS, by application dated July 9, 1969, requested authorization for deep-well disposal of low-level liquid waste. Questiona related to public bealth and safety raised by the deep_ell disposal ~oncept could not be resolved at that time. therefore, the CO..tSSiOD informed NFS by a letter dated ~ 27, 1970, that NFS should develop an alternate plan to achieve a reduction in quantiti.. and concentrations of radioactivity released in liquid effluents. NFS proposed to use a chemical treatment and ion exchange 8yste. for reduction of radio-activity in effluents (letter dated June 29, 1970). The Commission accepted the proposed treatment plan as a first-atep toward meeting the overall objective which i. ultimately to maintain radioactivity in liquids at the
point of release from the lagoon 8~ or below the levels set forth in Appendix B, Table II of 10 eFR Part 20 (letter dated August 8, 1970). In accepting this first step the observation WItS made in the Commission letter that it "appears to be feasible &nd compatible for use with foll~~-on.systemS for meeting the stated object~ve. but we believe every effort should be made to iileet the objective stated in our Hay 27 letter. at least fQr cesium and strontium within the next six to*nine months." On }!c,.y 4, 1971 pc.mission was I:iven *to NFS for test operation of tile low level waste treatment plant. Description
.The Low Level Was te Treatment Plant cansis ts of flocculation. clarifica-tion and ion exchange steps. In the flocculation step. sodium hydroxide.
ferrous sulfate and clay are added to the waste water feed to the treat-ment plant to precipitate most of the calcium and m~gnesium present as hydroxides and to form a gelatinous precipitate of ferric hydroxide. Cesium. strontium and other radioisotopes ara absorbed on the precipitate and on the clay added to the feed waste water. / Tbe precipitated and absorbed materials are removed from the water in a sludge-blanket clarifier. Feed to the clarifier is introduced through a central well. Purified wat~r overflows from the top of the clarifier' after passing upward through the sludge blanket. Settled sludge is dis-charged continuously from the bottom cone of the clarifier. centrifuged and packaged in dr~s for burial on site. Final traces of suspended solids are removed from the clarifier overflow by pumping the water through a fixed-bed anthracite coal filter. The water is then passed through a fixed-bed ion exchange unit containing a cesium-selective ion exchange resin (such as Duolite ARC-359) in the sodium form. The pH of the effluent from the ion exchange 'mit is adjusted with sulfuric acid to meet New York State water quality limits
.. it fl~ to the lagoon .y.tem before being released to the water shed.
Backwash water from the anthracite filter, .ion excbange regeneration
.olution. and the centrifuge supernatant waste are recycled to the feed of the treatment plant.
Overall operation of the treatment plant i . monitored by the use of inatruments equipped witb alarma in the l14in plant control room. The ion exchange effluent i. continuously moni~ored with an in-line instru-ment .et to detect g.... radiation from cesiua isotopes.
-'3 -
Overall decontamination factors, .. reported.by NFS, are expected to be about 290Q for strontiua, 250 for cesium and 3.6 for rutheni~. The new facility i8 located in a separate structure north of existing Lagoon No.2. Appropriate consideration has been given in the design of the facility to protection of plant operating personnel from direct radiation o~ conta.ination by iRo1ation and sbie1ding of equipment and by ventilation systems. Working Uses, in the facility, AS atated by tlFS, will be limited; the'uoit is expected to require a minimum of attention. Safety Con8ide~~
- 1. General The Low Level Waste Treatment Plant presents no new or U:1usua1 prob-lems for protection of plant operating persanne1 from radiation 07.-
posure. Existing plant procedures and p!'actices will be fo11(lm!d for radio1ogica.l. protection. of personnel. The inventory of activity which could be present in process equip~ent 1. estimated by NFS to be about 40 curie. of beta activity. Our independent evaluation of the / release of the activity under tornado condition. (anri assuming that all the activity is strontium 90) indicates that the maximum grounel level concentration would be equivalcnt to a 50 day exposure at the concen-tration limit for strontium 90 as given in 10 CFR 20, Appendix B, Table II for unrestricted areas. The radioactivity in the plant will be primarily in the form of insoluble materials and no off-site disper8ion would occur UIlder earthquake conditions. Based on the!:e considerations, we do not consider it neceRsary to build the waste trutment .plant to resist tornados or earthquakes. NFS eatimat.. the gros. alpha content of the feed to the plant to be 1.2 x 10-6 llicroc:uri.s per milliliter *. Because of the low concentration of total plutonium and uranium in the feed to the waste treatment plant, there will be no c1.'1tica1ity hazard.
- 2. Efflueet Discharges The radioactivity which v.. present in Cattaraugus' Creek due to effluent discharged from the NFS plant froa 1967 through 1970 ia shown in Table I.
The yearly avera,e per~entase of the 10 CFR Part 20 limits in Cattaraugus
Creek is also given in the table. (1) More complete isoto~ic nnn1yscs are not routinely made, but. some studies have indicated that the gross beta activity (exc1usjve of tritium) is composed of about 75% ruthenium 106, 7% strontiur:t 90, f,~ cesium 134 and 137 with the remainder composed of other i~otor~8 none of which exceed~ 1% of the total beta activity. Because of i~~ low in~i~~dua1 10 CPR Part 20 limit (3 x 10- 7 lIc/ml), stront:iwi! ')f) accounts for about 75:t of the reported percentage of the 10 CF~ ;-:~,..t 21) limit in Cattaraur.u~ 'Creek. Cesium isotopes "are the next most imp,)rtant contributors to the yearly average values. The new 'faste treatment plant ill flpecifica1ly de5i~ned to remove strontium and cesium isotopes from the plant effluents. These isotopes are the most limiting because they can reconcentrate in foods eaten by man. (1) The percentage of the 10 CFR Part 20 lim+/-ts is calculated using the following formula:
/
+** *MPt-**]
" 1 '
x 100 - % 10 eFR 20 Limit Where C , A Cs, C is the concentration in lIc/m1 of radioisotope A, B or l 1 in Cattaraugus Creek. MPC , MPC , MPC is the 10 CPR Part 20 limit for rs(lioisotope A, B or 1 A B 1 in water in unrestricted areas. MPC for gross beta activity, if a separate analysis has been made for Sr-90, is taken as 1 x 10- 5 pc/m1, the value given in 10 CFR 20 Appendix B, Table II, for soluble ruthenium. MPC for gross. alpha activi"ty is taken a8 5 x 10-6 lIc/ml, the value given in 10 CPR 20, Appendix B. Table II for soluble plutonium.
5 - T~t..EJ M.ll~CTlvrTI'--lli9T1:'~j-pr.uS ..9Ji~EK 1967-1970 Curies Yearly Averag~ Concentration in Cattar~u~us Cre~k as % of
!£.~ ~ro..!.!...~ Gr~~Jt !!,-3 S~**90 ._----_._------_
. Limit ..
1970 0.105 87.0 4516 14.2 21.9 1969 0.376 136.2 5975 10.07 19.7 1968 0.139 46.7 2662 5.09 9.1 1967 0.056 38.7 4204 9.0!)(1) 15.51
~
(l)For period Mar~h through December.
The effects of future discharges of strnntium and cesium isotorE'!S from tile NFS plant on radioactiv1 ty in Cattnrau~ua Creek can be estimated based on technical sl"cdficl'ltion limits and the capacity of the low level treatment plant. The action value for rcleRscs of strontium and eesium isntores, RS given in speeification 4.2.5, is defined by the following etfm~ ~';.on:
+ ~C..s-I1.L + + ~C:~r-2Q _ .. 1 2 x 10- 5 3 x 10- 7 (Where C
- concentr~tion, in microcuries per milliliter, of the indicated isotope in the treated ,~astc)
Auuminr, that the effluent discharr.,e iA 20('1, noo gallons per day (the capacity of the WaEte tre'll"i~ent plant) fOl 0:: full year, at TM.xiT'1u~ allowable concentrations and aSRll:il1.1"f: th.1t ench isotope contributes equally to the total action valup., i.e. ehat. the rat.io of the cnn-centration of each radioisotope to it~ Part 20 limit is 0.25, the total releases would be 0.63 curi(:s of cesitir.l 134, 1.38 curies of cesium 137, 0.2 curies of strontium 89 and 0.02 curies of stronth~~
- 90. At these release levels the concentrati':>il of c(!si\l::\ and strontiuT:I radioisotClpes in Cattl'lraugus Creek on an ann'Jlll averar.e basis would be about O.l.% of 10 crn Part 20 U.li!its as compared to about. 15% of 10 CFR Part 20 limits in 1969 and 1970.
Tritium will not be removed by the new waste treatment plant and ruthenium removal viII be low. Releases of these isotopes, which in the future will ~e the predominnnt radioisotopes in Cl'lttarnugus Creek, are controlled by Technical Specification 4.2.6 which sets an action value of 10% of 10 CFR Part 20 limits for all rAdioisotopes in Cattaraugus Creek. Although it is highly unlikely to occur, an u~per level for release of tritium or ruthenium radio~sotopes can be pro-jeeted by assuming that the eoncentration of the individual isotore in Cattarau~s Creek, on an annual average bASis, is at the 10% action value. Based on these assumptions the projected release would amount 00 95,000 curies of tritium or 320 curies of ruthenium 106 released to Cat taraugus Creek' eaeh year. Actual releases wUl be below the . maximum values listed because both isotopes will be present and the technieal specification limit applies to all radioisotores present. Realistie estimates of future actual tritium and ruthenium releases cannot be made at present beeause of uneertainties such as (15 the fate of tritium in reactor fuels (particularly Zircaloy clad fuels,-
(2) the rutheniUII decontamination fActor in the \-7aste treatment plant (3) future plant processing capacity, (4) bum-uT' of future fuels ann (5) the effectiveness of future plant lIIodifications to be mAde to improve ruthenium removal. The significance of the projected f'ltl1re releases of radioisotnpes in liquid effluents from the NFS plnl'lt. in terr.lS of population exposures, is di!lcussed in the fol::'t,".dll:; sections of this nnaiysis.
<a> Basis for Estimates Popu1aticn e}:posures fror.l discharr,o:,:.; of liquid effluents frOM the NFS site result primarily from in:~estion of fish and venison.
The.Public IIea1th Service of the U.S. f)eJ"ilrtr.l~nt of Health, Ec!ucation and Welfare has studied F.pulatic:>n* exposure nroll:1d the NFS site(l) and effluent d1r;ch"t'ges frot:! the site(2). and the results of these studies can he mied as a basis for e!;ti.~'1ting future population exposures. The steps involved in establishing 3 basis for estirr.ating future population exposure are: I> Establish the re1ationship'between consumntion of srecified quantities of fish and venison containing known quantities of radioactivity and the personnel exposures received.
- 2) Establish* the relationshi!, between the amount of radio-activity in fish and venison and the quantity of activity discharged from the site.
- 3) Combining 1) and 2) and relating exposures throur,h ingestion of fish and venison to the activity in plant effluents and expressing the results as the organ dose per curie discharged for each important radioisotope.
Estimates made by th~ Public Health Service of the intake of radioisotopes by individuals in the population near NFS in 1968 by eating fish and venison and the resulting 50 year dose commitment to members of that population are shown in Table II.
-(l)BRH/NERHL 70~l, "An Estimate of Radiation Doses Received by Individuals Living in the Vicinity of a Nuclear Fuel Reprocessing Plant in 1968."
(2)BRH/NElUIL 70-2, ilLiquid Waste Effluents from a Nuclear Fuel Reprocessing Plant,"
- s-Table II shows that tha 50 year dose C(>T!'IIIi.tment of an averaj;!;l!
individual in the ~or~lation r.roup eatin~ fish and venison in 1968 is about 2.2 mrem to tha whole boc;ly from cesiuM 134, cesi~n 137 and tritium; 17.6 mrem to bone fro~ strontium 90; and 0.96 mrem to the G. I. track* from ruthenium 106 and cob~lt 60. We estimate the population exposed through cons~~tion of fish and venison to be between 100 and*l,OOO people. In order to relat~ population e:.:ro~ure in 1968 to rel('!!nes of activity from the NFS site. it is neCeRI'ary to estlmate the 1968 curie discharges of specific isotopes. In 196:1, NFS report!!d that liquid effluent!! contained 2,662 curies nf tritiUl'l. 5.09 curi.,.s (>f strontium 90 and 41.6 curiC'3 of other beta ncti vi ty. !*fore* det.1il-:d isotoric analysis of 1968 rJ.~ilt effluents llre not I!vilU.,b1e. In 1969, the Public Health S!!rvice evaluated the isotopi.c content of N!"S liquid effluent:! in gre:1tcr detail durin" the peri.od !illY throur,h October. A"IstIrninr, th? t the ,"sotor! c co~~<,!,j t j. t:'n (exc1 I!', i w' of tritium and strontium 90. for which sc;pnr.ltc an,,,lyses ~re r.v,lil** able) of the effluent in 1968 is the sa~r. as in.19('9. the 41.~ curies of unidentified beta activi ty rclpnscd in 19(',S lIOUJ.d cr;:jt~in 1.12 curies of c(;!r.i.um 134, 4.56 curies of ccsi\L":! 137, :'1).1\ curic~ of ruthenium 106, and 0.112 curies of cobalt (,0. t:si.n~; these aRsumed releases, in conjunction with Tabl!! II eXl'Ost:.-C5. the maximum organ dose per curie discharged f(lr each jl':'T'ort,~'1t r;1(: ,('- isotope can be estimated. Results of the5C calcuL1tions arc r,i.vcn in Table III. (b) Future Maximum Exposure Estimates The organ dose per curie discharr,ed. derived a5 shown in Table III, can be used in conjunction with estimates of future f;1<lxil1lum releases of radioisotopes to make an upper level e~tin~te of future population exposures. In Section 2 of this analysis, the following estimates for future releases of important radioisotopes were given. Curies/Year Sr-90 0."2 H-3 95,000 Cs':'U4 0.63 Cs-1l7 1.38 Ru-l06 320
TAI:LE II 1968 Lxposure Es tiJ:w.tcs for Persons l~atinB Fish and Venison , Annual Averar,e In~ake Dose Commitment llCi/yr Factor (mrem 50 Year. Fish, 5.5 kc/yr(3) " .
,(:n_lson~ 2
- I{[j / vr (3) From Fish per 50 years Dose Comeit-
. i~uclide llCi/klj (2) . \lCi llCi/k~2 . \lCi + Venison per lICi intake) ment mrem Organ
-4 -3 -4 -4 -3 8400. (5) 17.6 (5)
Sr-90 3.4 x 10 1.87 x 10 1.1 x 10 2.2 x 10 2.09 x 10 Bone il-3 1.2 x 10
-2 6.6 I
x 1v- 2 3 x 10
-2 6 x 10~2 1. 26 x 10
-1
.13 .016 ~o1e Body
-3 -3 x 10- 3
.Cs-134 -------- -------- 2.6 x 10 ~.l x 10 5.2 80 .416 Whole Body
. -4 -3 -2 -2 -2 Cs-1~7 6.3 x 10 3.47 x 10 1.3 x 10 2.6 x 10 2.95 x 10 60 1.768 Whole Body
-4 -3 - -3
?u-1J6 8.5 x 10 4.65 x 1) -------- --':"'----- 4.68 x 10 195 .912 G.l. tract
-4 -3 -3 Co-GJ 2.1 x 10 1.16 x 10 -------- -------- 1.68 x 10 40 .046 G.l. tract
- 1. :lased 011 IJmi/NERilL 70-1 d;l~n.
- 2. Ibid. p. S, Table 3.
J. lilid. p. o. Table 2.
- 4. Ibid. p.5. Tllb1e 1.
- 5. The first year do!;e for "5r-90 ingestion is about 7% of the 50 year dose commitment or 1.2 mrem. For other radionuclidcs listed, tLc first year dose is >907. of the 50' year dose commitment.
~li.JIl ORGAN DOS!: PER CURIE DlSCllAAGED FOR PERSO}!S EATI:1G FISlI AND vElaso~;
*1968 50 Year DORe Curies SO Year Dose Cornrni tmcnt .
Discharged Commitment mrern per Ci l'iuclide in 1968 mrern Dis ch"lr[:ed .Orr~ 5r-90 5.09 17.5 3.43 Jlone 11-3 2,662 .016 6 x 10- 6 Whole to tiy Cs-134 1.12
- 416 ~
.37 \*Jholc toey CS-137 4.5.6 1. 768 .39 "'hole Hotly Ru-l06 29.6 .912 .03 C.!. traet Co-60 .112 .046 .41 G.!. tract
The curie discharge esttmat~~ for strontium anJ cesium radio-isotopes were based on dls~harge of a mixture of radioisotopes. If only individual radioisotcpes were present. the curie din-
. charge lilllit for each Tlld1cf.i;otope could increase by a factor
. of four without exceedino; tc(~hn1.cal Gpecification 4.2.5. The following est1lllatea of the up~er level of future population exposures were based on rl!J.C£lf.'eS of individual radioisotopes even though i t was recogni ,..*,,,i th:lt resulting exposures would be overstated.
In Table IV the future maximu", d~9ChaT'lZ.es of indivitlual radio-is~topcs and the correspondin~ upper liMits of future population exposures are ~iven. Haximut1 first YC'2r bone and ~~hole body eXpOB\I:es are less than 2% of the Flh: guidance lim! tq for II suitable s8lllple or the population~ 'flwre is no specific F~,C guid-ance for G. I. tract exposure; howeve=. the calcul~ted exposure of 9.6 mram/year is low compared to ~lC FRC whole body guicl~nce li~it of 170 mrem per year. The expoaures estimated above sr.e overstated. Future population exposures will actually be substantially lower for the folloving reasons:
- 1. The above estimates are basp-d on releases of isotopes at maximum individual release levels. In actual plant opera-tion. mixtures of isotopes will be present and no individual isotope will be at its limit
- 2.
The estimates are based on discharges over a full year period at maxima. permissible concentrations and at maximum volume flows. and
- 3. Actual releases of rutheniUIII will be lower than those estimated because the waste treatlllent plant is expected to have a rutheniu. decont&lllination factor of about four and future plant .odifications are planned which should impTOve in-plant rutheniUli retention.
Radioiaotopes other than tritiUli. rutheniua. cesiUIII and strontiUIII which are present in plant wa.tes are not expected to add signifi-cantly to population exposure. No radioiaotope other than tritium. rutheniu.. cesium and strontiua will occur in plant effluent at the
TABLE IV MAXii:ruf.TiSTItIATED AVERAGE E)'J'OSlIlU:: LHlIT OF PERSONS EATiNG FISH & VENISON Fraction of 50 Year Dose Appendix B COIIIII:l tlllen t pe r Table II. Col. 2 Possible Year of Plant Concentration Ci./yr Operation Nuclide limit Di.charse mem Organ Sr-90 1.0(1) 0.08 0.3(3) (4) Bone H-3 0.1(2) 95,000 0.57 Whole Body Cs-134 1.0(1) 2.49
- 0.92 Whole Body Cs-137 1.0(1) 5.52
.. 2.15 Whole Body Ru-l06 0.1(2) ,.- 320. --- -9.6 --G.I.- Tract (1) At point of discharge from lagoon system.
(2) ~ Cattaraugus Creek (3) The dose accrued in the first year for Sr-90 is about 0.02 millirem.
*First year dose accruals for other radioisotopes and >90% of the 50 year doee commitment.
(4) *Other dose commitment .ode1& could be used. For example. a dose . collllllitmeDt af 2000 mremAl*cc intake can be derived by relating continuous consumption of water CODtaining the maximum permissible concentration of Sr-90 (3 x 10-7 II c/m!) to the resulting PRe estimated exposure of SOO arem/year to bone. On this baais. the SO year-dose commitment per year of plant operation for Sr-90 would be 1us than 0.1 arem.
t TABU:: V LIMIT OF FISH & VENT;,ON EATING CROUP EXPOSURE r.ONTI*;T*iuTABLE BY
-OOREATEPw/;STf." S1ru:AMS SteAm Laundry Condensate Effluent Annual Flow. 111(1) 3.2 x 1011 Gross Activity Limit. pc/ml 3 x 10-7 Gross Release Limit. Ci/yr .096 .69 Ratio of Releabe limit to 1969 release. * .002 Bone Exposure. mrem/yr .0025 .018 Whole Body Exposun. wrem/yr .0044 .033 G.I. Tract Exposure. mrem/yr .0019 .014 (1) Based on boiler.capacity of 80.000 pounds per hour and no condensAte recycle and the NFS reported value for laundry wastes of 19.000 liters per day average.
- ll. -
lasoon outfAll above ~hQir individual 10 CFR Part 20 limits. The total concentration of all radioisotopes, exclusive of tritium, ruthenium. cesium and strontiUM, after dilution in Cattaraugus Creek and assuming no removal in the treatment plant should not exceed about 0.1% of 10 CFR Part 20 limits. The effect.of two other streav~ discharged. to the environment should be considered. These are the steam conden~3te and laundry discharges. SteaD condensate, lIccoTding to specification 4.2.1, may be discharged to the environment if it has been detercined that the 8TOSS alph!7plus beta activity (eT-clusive of tdUm:!) is less than 3 x 10 microcur:!.es per rnillil1ter. I.aundry t-.'1!ste (specification 4.2.2) may b(~ transferTed to the lngC'lon system dovnstream of the waste tre:-.tl'1cnt glant if the gross alpha pJuc; beta activity is less than 1 x 10- microcuries per milliliter. The total curie releases in these streams And expo5ures calculil-ted according to the organ dc~e per ourie release concept described atovc is shovn in Table V which sho~s that dischar~e of these effluents have negligible effects on population exposure. Conclusion Based on our review of the Low Level Waste Treatment Plant design and operation. we conclude that it does not present significant hazard considerations not described or implicit in the NFS "Final Safety AnaJysis Report" and that there is reasonable assurance that the health and safety of the public will not be endangered by the operation of the new facility. We further conclude that cesium and strontium radioactivity in liquid effluents discharged from the site will be substantially. reduced when the waate treatment plant ia placed in operation. Approval of the attached Technical Specifications relating to operation of the Low Level Waste Treatment Plant is recommended. Signed: 1/"(/. ?~
- w. A. Nixon Irradiated Fuels Branch Division of Material. Licensing Approved:
b,~ .'./"!?~/ ;, / '"~ i, r~~jj1',' ( .......;;.;o-~ .....~ R. B. 'thi6l00cl. Chief Irradiated Fuels Branch Division of Materials Licensing}}