ML19284A459

Application for Amend to Licenses DPR-44 & DPR-56, Changing Tech Specs Re Solid Radioactive Wastes,Containment Sys & Auxiliary Electric Sys.Certificate of Svc Encl

ML19284A459
Person / Time
Site:	Peach Bottom
Issue date:	03/01/1979
From:	Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19284A458	List: ML19284A457 ML19284A459
References
NUDOCS 7903060461
Download: ML19284A459 (75)

Text

BEF0FE THE UIIIIED STATES IJUCLEAR REGilLATORY Cot 1 A1ISSIOt1 In tile Matte?: of  :

Docket flos. 50- 277 Pl!ILADELPilI A ELECTRIC CO:1PA'lY  : "0-270 A P P LICA'110tl F OR A:1EIJD:1ht1T Of EACILITY OPERATIt!G LICEt1GF.o DPE-fi4 F. DEE-56 Edward G. Pau ser , Jr.

Eugetie J. Pr,ulley 23 01 tla rket .it it:e t Plailadelphia, P entw ylv a n i.a 19101 Attorneys for Philadelphia Electrie company 79030604Co(' ,

BEFOHL 7HE UtlITED STATES tJUCLEAR HEGULATORY CoriM ISSIOt1 In the Matter of  :

D oc ke t f:o s . 50-277 PilILADELPIIIA ELECTRIC CCMPANY  : 50-278 A PP LICATIOf 3 FOR AMEtJDMEtIT OF FACILITY OPERATI!!G LICEI:Si. i DPF-44 6 EPR-56 By letter dated July 11, 1973, the Division ot~ ot era tinq Ecactors requested Philadelphia Electric Com any, inter alia, to submit a license amendment applicatien to i ncot [, ora t e the applicable specifications of the At[.cndix 1 na2de l T echnical Specifications enclosed with the letter into t.he Appendix "A" Technical Specifications for Peach Bottom Units 2 and J.

Accordingly, Philamlelphia Electric company, Licenueo under Facility Ope rating Licenses DOE-4f1 and DPR-56 tor Peach Pottom Atomic Power Station Unit IIo. 2 and Unit rio. 3 re crec ti vel y,

hereby requests that the 'lechn i ca l Epucificat ionn incorporat"d in Appendix "A" of the Operating Licences be arervitol by t evicinq sections 3.2, 4.2, 3.8, 4.8, 6.0 and associated t:as es by changing pages ii, iii, iv (Unit 2) , iv (Unit 3) , vi, 58, 59, 75, 84, 9 ._

(unit 2) , 92 (Unit 3) , 93, 203-216, 248, 252, 256 a nd 257-250 and by adding pages 216a-216n, 256a, 259a, 259b, 259c, and 263-265.

All changes are indicated by a vertical ha r in t he neargin of the attached revised pages.

Furthermore, since this proposed amendment incorporate.c in Appendix " A" the Technical Specitications applicatale to the environmental radiological troni.tcring program pr e s"n tl y incorporated in Appendix "B", Philadelphia Electric Cory any hereby request.s that the Technical Sp?cifica t ions incorporat ed in Appe ndi x " B" of the Operating Licenses be amended by deleting sections 4. 3, 5. 3, 6.4, 7. 5. 2 a nd a scocia t_ed b ises by changing pages i, ii, 13, 41, 42, 48, and 52 as indicated by a vertical ba r in the margin of the attached revised pages.

The proposed changes conform to the intent of t he me lel Technical Specifications. Ilowe ve r , certain at th" (nodel Technical Speci fica tions a re not applicable to Peach Lot tom Atomic Power Station and are outlined as followa:

1. Solid i;adioactive Waste: The as-built 90 lid F,ad ioac ti ve Waste System is desiqnel to pr ocers w t.

(spent demineralizer resins and stent filter P.aterial) and dry solid wastes. Wet solid wastes are dewatered to preclude f ree water and packaged in otantiud 55 gallon steel drumu. Dry colid wastes at e compactxd to reduce free volume and packageil in ntawlard 55 gallon steel drums or other approved shippinq cont ai ners, as applicable. /\pproved procedures are provided and updated at the station f or opera tien of this nystem in accordance with design. liowever , the an-built c y s t.em does not have the capability for solidif ica ti on as defined in the model Technical Specifications.

Philadelphia Electr ic Com; any ha s been inve<;t iqa t in g the s uitability of va rious propoced solidi fica t. ion systens f or use in Limerick Generating . Station (Decket IJo s . 50- 352 and 50- 353, ccus tr uc t ion Permit f ?os . C P PI- -

106 and CPPR- 107) which is presently being constructed.

Due to the rapidl y changing state-o t-the-art , incimiinq several new methods for solidi.ficat. ion at v.e l l a t. lack of clarity in acceptance criteria, it has not 1.e t a possible at this time to select a n ai p ropria te nyntem f or solidification. It is Philadelphia Electric's intention to continue this invest.iqa tion un t. i l a sa tisfactory solidification syutom can 1" nelected and installed at Peach Botton as well as at L une r ic k ,

2. Liquid IIoldup Tanxs: All outdoor tanks at the station which have the potential for cantaininq radioactiv" liquids are currounded by dikes capible of 1olding the tank contents and have overt lows ani drains connected to the liquid radwast.e t reatment systen.

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J. Cont inuous Liquid Feleases: All routine r adioact ive liquid releases f rom the station are hatch teleasts.

4. Land Use census:

a. Dose ausessment analysis to determine compliance with Appendix I has shown tha t a real residence does exist at the site boundary at maximum dose potential. There is no rea son to conduct an anrutal residence survey because it is not possible for a different residenco to appear at a locatiott with greitter doce potontial,

b. The dose accesarrent analysis has alco shown that the maximum done to man occurs via t h" grasr-cow-milk pathway. The calculated done at the maximum dase real dairy farm is greater than the calcula ted dose at any hypothetical vegrtable garden which could exist. off-site. Since this pathway could never be the limiting pathway, there is no benefit to be gained by pe rtor ming an annual garden census.

The methodology to 1:e need in the calculat icn of otf-sit-doses due to radioacti ve gaseous and liquid et t ] nents, monitor setpoint determinat ion methodology, intd stetails of the environmental radiological troni toring program a re set forth in 3 document titled "oftsite Done Calculation Manual, Peach Pottom Atomic Power Station, Unit.s 2 and 3, Philadelphia E lec tr ic Company," which is filed herewith and i.ncor po ra t t d herein by reference. The contents or the above retot+need document are

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f urthnr describe'l in Attachment I to the document, "Information in Support of the offsito Done caIc ilat ion Manual ( O Dc'4 ) " , which in incorporated herein by referonce.

Pursuant to 10 CPR 170.22 " Schedule of Fons for Facili t y License Amendmants," Iicensee preposes that this Applic stion for Amend men t he consi.dered 3 Class III Amendment for Unit 2 and a Class I Amendment for Unit 3, since the proposel changas in volvo a single environmental issue and do not involve a sinnificant hazard consideration.

The Plant Operation Review committee and th? O pe ra t ion a n.1 .

Safety Review Committee have reviewed these nroposol changan t o the Technical specifications and have concluded tM t the changen do not involve an unreviewed safety question or a nignificant hazard considoration, and will not en:la nger t he hea lth and o,foty o f the public.

Respectf ully n thmi tte 1, PIIIIAD EL Pili A ELECTRIC CD:4P A'r(

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Vi t. o_ P)roudont Y COMMOIT..'E A1/Ill Of Philt.S Y LVA!J 1 A  :

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COU:11 Y OF Pili LAdc L Pill n  :

>. L. Da l t.ro t i, L e iruj firut duly ahorn, deposeu aliJ uays:

Inat he ib Vice Preuiaent of Plailaaelphia t'l e c t r i c coa.pa n y , ta_ A>[licant t herein; that he han read the toregoing Application for nacnomer.t o r bicility Opera tinq Licences and

};now t r.e coastentu titereot ; and that the ctateinent u and in.a t ters cet forth tl.oreir. tre t r u t. and correct to t.l.e be s t of his ra s cu l e ltje , int or:.i a ti on uno 1elief.

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Subucribed and sworti to betore uit. this uay or 10mma

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hfZABETH H. BOYER Notary Public, Phi!a., Phita. Co.

Aty Commason Expiwa Jan. 30,1992

CEETJFICATE OF SEP.VICE I certify that service of the foregoing Application <.a s trade upon the Board of Supervisors, Peach Bottom 'Iownship, York Coun ty, Pennsylvania, by mailing a copy thereof, via first-class mail, to Albert R. Steele, Chairman of the Poard of Sulr rvi cors, R. D. tio . 1, Delta, Pennsylvania 17314; upon t: h e Board of Supervisors, Fulton Township, Lancaster County, Petinsyl van i a , by mailing a copy thereof, via first-class mail, to Geor

rvisors,== I:run. ore Township, Lancaster County, Pen ns ylvan i a , by mailing a copy thereof , via first-class mail, t o Wilmer P. Eolton, Chairman at the Daard of Supervisors, R. D. tio. 1, Ilol t w oo l , ren ns yl va n i . i 17532: all t.h is A8 day of February, 1979. l Eugene J. Er diey Atter ey for Philadelphia 1:loctric Company PDAPS TAPLF OF COfJTENTS (Cont ' d) I..lS G SUT VL ILL AtJCE LIM 17 I!1G CONI;ITIOtJ3 FOR OPEPATIOIJ F EnU I F Ef1 E!J7

3. 6 PRIMARY SYSTEM BOUtJDARY 4.6 143 A. Thermal and Pressurization Limitations A 143 B. Coolant Chemistry B 145 C. Coolant Leakace C 146 D. Saf ety and Felief Valves D 147 E. Jet Pumps E 148 F. Recirculation Pumps r 148 G. Structural Integrity G 149

3. 7 COf1TAItJMEtIT SYSTEMS fl . 7 165 A. Pri ma ry Conta intrent A 105 B. Standby Gau Treatment System B 175 C. Secondary Containrrent C 176 D. Primary containment Isolation Va lvt s D 177 3.8 RADIOACIIVE MATERIALS 4.6 20 3 A. General A 203 H. Liquid Effluents I; 204 C. Gaseous Effluents C 208 D. 40 CFP 190 D 216 E. Radiological Environmental Monitorino E 216a

3. 9 AUXILIARY ELECTRICAL JYSTEMS 4.9 217 A. Auxiliary Electrical Equipment A 217 B. Operation with Inoperable Equipment H 219 C. Emc.?rgency Service Water System C 221 3.10 CORE 4.10 2.) 5 A. Refueling Interlocks A 225 D. Core Monitoring P 227 C. Spent Fuel Pool Water Level C 224 3.11 ADDITIOIIAL SAFEIY RELATED PLAtJI CAPADILITIES 4.11 233 A. flain Control Room Ventilation A 233 B. Alternate Heat Sink Facility B 234

c. Emergency Shutdown Control Panel C 234 D. Seismic Hydraulic Snublers D 234a 3.12 RIVER LEVEL 4.12 237 A. liigh Fiver Kater Level A 237 n - n . % . . .- . , ,

Pl3APS TAPLE CF COf11Et1TS (Con t- ' d) B. Low Eiver Water Level E 237 C. Level Instrumentaticn C 238

3. 13 MISCELLAllEOUS RADIOACTIVE MATERIALS ft . 13 240a

3. l '1 FIEE PPOTECTIO!! 4. 14 240c A. Water Fire Protection System A 140c B. CO2 Fire Protection System B 240c C. Fire Letection C 240i D. Fire Earrier Penet rations D 240j

5. O MAJOR DESIGti FEATURES 2(11

6. 0 ADMIIJISTRATIVE COtJTROLS 243 6.1 Eesponsibility 24.3

6. 2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Peportable Occurrence Action 25J 6.7 Sa fety Limit Violation 253 6.8 Proced ure s 253

6. 9 Reporting Requirements 254 6.10 Record Petention 260 6.11 Radiation Protection Program 201 6.12 Fire Protection Inspecticns 26 1 6.13 liigh Padiation Area 262 6.14 Of fsite Doce Calculation Manual (eDe :) 263 6.15 Major Changes to Radioactive Waste Treatment Systems 2 f> 4 wn na m -, ., + ",

P L'A P S Unit / LIST OF F IG U P ES Fiqure T IT LE Mge 1.1-1 APEM Flow Bian Scram Pela t.ionship I f; 10 Normal Cperating Conditionu 4.4.1 Instrument Test Interval Determina- 55 tion Curves 4.2.2 Probability of system Unavailability 98 Vs. Teut Interval 3.4.1 Fequired Volume and Concentratiori vi 122 Standby Liquid Control System Solut ion 3.4.2 Required Volume and Concentration of 123 Standby Liquid Control System 30]ution 3.5.1.A MAPLilGR Vs. Planar Average Exposure, 142 Un it 2, 7x7 fuel, Type 3 3.5.1.B MAPLilGR Vs. Planar Average Exposuro, 142a Unit 2, 7x7 fuel, Type 2 3.5.1.C. MAPLHGR Vs. Planar Average Exposure, 142h Unit 2, 8x8 Fuel, Type !! - 80 mil f, 100 mil 3.5.1.D MAPLilGR Vs. Planar Average Exposure 142c Unit 2, 8x8 Fuel, Type L

3. 5.1. E K f Factor Vs. Core Flow 1421 3.5.1.F MAPLIIGR Vs. Planar Average Exposure, 142e Unit 2, 8x8 LTA Fuel

3. 6.1 Minimum Terrperature for Pressure 16u Tcsto such as required by Section XI 3.6.2 Minimum Temperature for Mechanical 164a

!!eatup or Cooldown following Nuclea r Sh u td own 3.6.3 Minimum Temperature for Core opera t. ion 1641; (Criticality) 3.6.4 Transition Temperature Shitt vs. 164c Fluence 3.8.1 Site Boundary and Ef fluent Pelease 216h Points 6.2-1 Management organization Chart 2u4 6.2-2 organization f or Conduct at Plant 205 Operations n m o n A - ~o- *n

• FBAP3 Unit 3 LIST OF F IGUR E.7 Fiqure T I'I LE P.m e 1.1- 1 APFM Flow Eias Scram Relat. ions hip 16 To IJormal Operating Conditions 4.4.1 Instrument rest Interval Deter mina- 53 tion Curves 4.2.2 Probability of system Una vailabilit y 9P Vs. Test Interval 3.4.1 tiequired Volume and Concen tra tien of 122 Standby Liquid control System Solu t. ion 3.4.2 Required Temperature vs.concentra ti on 123 for Standby Liquid Control Systen 3.5.1.A NAPLIIGR Vs. Planar I.verage Expocure, 142 Unit 3, 7x7 Fuel, Type 3 3.5.1.b MAPLIIGF Vs. Planar Average Exposurez, 142a Unit 3, 7x7 Fuel, Type 2

3. 5.1. C . f1APLilGR Vs. Planar Average Exposure , 14 2t -

Unit 2, 8x8 Fuel, Type H

3. 5.1. D MAPLilGR Vs. Planar Average Exposur" 142c Unit 3, 8x0 Fuel, Type L 3.5.1.E Kf Factor Vs. Core Flow 14 2d

3. 5.1. F MAPLilGR Vs. Planar Averago Exposure, 142" Unit 3, 8x8 PTA fuel 3.5.1.G [1APLIIGit Vs. Planar Average Expomite 142f Unit 3, 6x8E Fuel 3.6.1 flinimum Temperature for Prenaute 164 Iests such as required by Section .: I 3.6.2 Mininum Temperature for flechanical 104a lleatup or Cooldown following Nuclea r Shutdown 3.6.3 ttinimum Temperature for Core op u a tion 164h (Criricality) 3.6.4 Transition Temperature Shif t vs Fluenco 164c

3. 8.1 Site Foundary 6 Ef fluent Release Points 216h

6. 2- 1 Management Organization chart 244 6.2-2 organ izat icn for conduct of Plant 245 Operations n ,, na.... ,

PPAPS LIST OF FIGUR ES F_igting TifLg -- p.lgg 3.7.1 Primary containmrat Isolation valves 179 3.7.2 Testable Penetrations With Double 1H4 0-Ring Seals 3.7.3 Testable Per.etrations with Testable 194 Pellows 3.7.4 Primary Containment Tes ta ble Isolation 185 Valves 4.6.1 Radioactive Liquid Waste Sarrpling and 2161 Analysis 4.8.2 Radioactive Gasectis Waste Sampling and 216f Analysis 6.12-1 Protection Factors for Pospirators 257 6.9.1 Renorting Levels for Radioactivity 259s Concentrations in Environmental sanglos Amendment No. -vi- P l% P.9 LIMITIIJG CO!!DITIOfis FOR OPER ATIOtt SIIFV EI LI, A f1C M ri EOTI I R NI E7: rti ,_ C. Control Pod Block Actuation C. Con *rol Pol Plock Actuation

1. The limiting conditions of I ns t ru mon ta t ion shall be operation for the instru- functionally roote l, cali-mentation that initiates bra ted and chcckod a s indi-control ro1 blocks are given caFed in Ta bl o fi . 2. c.

in Table 3.2.C.

iystom to< Tic shall be func-t lonally testel as indica-

2. The minimum number of opor- f.ed in Ta bl e fl . 2. C.

ble instrunent channels specified in Tablo 3. 2. C for the Ro-1 Block Monitor may be reducod by one in one of tho trip systemn for ntintenance and/or testin<T, provided that this condi-tion doon not last lonner than 2fl hours in any thirty day period. D. Fadiation fionitoring D. F:1dia' ion Monitoring Systoms - Isolation S  :;vs tems - I s o l a

• i. on T, Tnitiation Functions Initiation runctions Amendment !Io. .

PB Al'G r LIMITIITG CO!!DITIOf1S T'OP OPEPATIOt1 GUP V F I I IA t!C E R FQ'II F EM 'CITS __ 3.2.D. (con t ' d) li . 2 . D l (cont 'd . )

1. Reaetor Ru i Irl i ng I nola tion 1. Hoaetor D u i.1 ii n o Inolation aryl standby Gas Trea tment- an1 neandby Ga n Troa tnont-Eystom gygtom "I h e limiting conditions i nn trumont a t ion chall b5>

t or operation a re given in f unct iona11 y tont el, cali-Table 3.2.D. bra ted and chocke<1 an indi-ca*od in Tabio '8 . 2. D . Gy-t"n logic chall be tunc-tionally tented as indica- & <-l in Tablo II.2. P. E. Drywel1 I.eak Detoction E. Dry ' 1 l _ Loa k Dot och i on The limiting conditions of I ns t rumen t i t ion ~, hall 1o operation for the instru- calil:ra te<1 a nd chocko 1 a r mentation that monitors indicato<l in Ta bl e 't . 2. E. drywell leak detection are niven in Table 3.2.E. Amenduent flo .

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3. 2 PASFS (Cont ' d)

The APRM rod block function is flew bianed and provonts a s ign i. f ica n t reducti.on in MCPR, especially during operation at roduced flow. The APRM provides qross core protoc* ion: i.o., limits the gross core power increase from wit h'lvawal of control rods in the normal withdrawal sequence. Tho tripo aro not no thaF MCPR is maintained greater than 1.07. The RBM rod block function provides local protection of tho coro; i . e. , the prevontion of boiling transition in the local rogion of the core, for a single rod withdrawal error fron a limitino control rod pattern. Tha IPM rod block function provides local ar woll ar grosn core protection. The scaling a rrangement is such that + rip sot tinq is loss than a f actor of 10 above the indicated lovel. The lownscale indication on an APPM or IRM in an i n d i ca t ion i he inntrument has failed or the instrument is not nonsitivo onouqh. In either caso tho instrument will not rospond to changos in t h .' control rod notion and thus, control rod notion is prevented. Th? downscalo trips are set a t- 2.5 indicate:1 on sea l o. The flow comparator and scram d ischargo volume hiqh level components safety. havo only one logic channol and aro not roquired for The flow comparator must be bypassed whon op" rating with ono recirculation water pump. The refueling interlocks also operate ono loqic cha:nol, anl are required for safety only whon thn node noit ch i" it t- ho refueling position. For offectivo omergency coro cooling for vall pi po Ireaks,'tho !!PCI system nust f unc tion si ice reactor pressuro doos not decroase rapidly enough to allow oither core " pray or LPCI to o pera t o in time. The automatic pressure relief function in provided as a backup to the IIPCI in the event t he IIPCI doen not provido this function when necessary and minimir.e npurious o pera t ion. Tho t ri p nettings given in the spocification are adequate to assuto the above criteria are met. The npecification preservos the e f fectiveness o f the system during periode of maintonance, testing, or ca libra tion, and also minimires tho rink of inadvertent operation; i.e., only one instrunont channel out of service. Amendment tio. JF, RP PDAPU 'In i ' 3

3. 2 MEEE (cont' d)

The APRM rod block function is flow hiased and prevonts a significant reduction in MCPR, especially during oporation at reduced flow. The APRM provides gross core protection: i.o. , ilmits the grosn corn powe r increase from with1rawal of control rods in the normal withdrawal noquence. The tripn are ser no that MCPR is maintained greator than 1.07. The PRM rod block function provides local protection of tho corn; i.e., the prevention of boiling transition in the local region of tho core, for a single rod withdrawal erroc f rom a limitint control ro<i pattern. The IPM rod block function provides local as wo l l a r arosn core protection. Tho scaling a rrangemen t is such that

• rip settinq in less *han a factor of 10 above the indicatod lovol.

Tho lownscale indication on an APFM or IPM is an in lica t ion t ha instrument has failed or tho instrument is not ronsitiv" onouch. In either case the instrument will not rospond to ch1nqes in tho control rod motion and thus,, control rod mot i on is prevontoi. The downscale trips are set at 2. 5 indicated on nea lo. The flow comparator a nd scram discharon volumo hioh levol components havo only one logic channel and aro not r guirod for safety. The flow comparator must be bypassed when opora tinq with one recirculati.on water pump. 'Ihe refueling interlocks also operate one logic channol, and are requi. red for sa fety only when the mode swit ch is in tho refuelino po sit ion. For ef foctive emergency core cooling for small pipo breakn, tho IIPCI system must function since reactor pressuro do<s not docrease rapidly enough to allow either corn rpray or LPCI eo operate in time. The automatic prossure relict function is provided as a backup to the IIPCI in the event the !!PCI doos not provide this function when necessary and rinimize npurious opera t ion. The trip settings given in t he spec ificat ion are adequate to assure the above criteria are mot. Tho stecification preserves the effectiveness of the system during porials of maintenance, testing, or calibration, and also minimizon tbo risk of inadvertent oporation; i.e., only one inst rumont channol out of sorvice. Amondment No. M, M PPAPS

3. 2 BASES (Con t ' d)

Pour nots of two radiation monitorn are provido l which initiato the Reactor Building Isolation function and ot oration of tho nta.rlby gan treatment system. Four instrumont channeln monitor the radiation from the refueling area ventilati on oxhaunt ductn and four instrument channoin monitor the building v<nrilation below the refueling floor. Each set- of the inntrument channels i c arranged in a 1 out of 2 twice trip logic. Trip settings of <16 mr/hr for the monitors i n t ho rofueling aroa ventilation oxhaust ducts aro based upon init iat inq normal ventilation i solation and standby gas t rea tment sys tem oporat i.on so that none of the activity releaned durino the ro f uel i nn accidont laaves tho Reactor Building via the normal ventilation path but rather all the activity in proceaned by the nta ndhv q in treatment nyeten. Flow intogratorn are used to record the i nt-eg ra t ed flow ot li piid from tho drywell sumps. The alarm unit in each intoqrat or is not to annunciate before the valuen specified in Speci fice ion 3.6.C. are excendal. !\n air sampling nystem in alno [ rovido:1 t o detoct leakaqe inside the primary cont ainment. For each paramoter monitored, as lintotl in Ta bl e 3 . ? . F, thoro aro two ( 2) channels of instrumentation. Ry comparinq r oa d i nq < betwoen tho two (2) channels, a near contin uous nurvoil lanco of instrument per f orma nce in a vailable. Any dev iat-ion in readinos will initiate an early recalibration, t he rol .y ma int a ininq the quality of the instrument readinqn. The recirculation pump trip has been addod at the nuqqcntion of ACRS an a noans of limiting the consequences of tho u n l ike ly occurrence of a f ai lure to scram du ring a n a n t- i c i pa r o d t ra n n i o n t . The rosponne of tho plant to thi.s postulated evrut fall wit h in the envelopo of study evonto given i n Gener al Klon+ tic company Topical Report, t1EDO-10349, dated March, 1971. Amendment tio . PIIAPU LIMITitJ'; CO!It)I TIOTIS FOR OPERATION _ Sf11N EI LL *dir E R F2'111 I;.M F!!f G

3. 8 Padioact-ive fiatorials f4 . 8 Radioactivo da to ri a in Agnlicability Anolicabilit y Applios to tho radioactive Applies to tho periorlic moni t-effl'Iontn irom the plant. oring ancl r"cordina of radio-active offluonto.

Ohioctive Obiectivo To aseuro that rad ioac tive To ancortain tha*- radioac*ivo material in not released to releasen aro ar low as t he environment in an uncon- rea sonabl y achievabl o and trollod manner and to assure within allowable va luon. that any materia 1 released is kept as low as roanonably achievable and, i.n any event, in within the limits of 10 CFR 20. Speci fication specifica* ion A. General A. G o n o r a_l_ It is expocto<1 that roloases Operat i rl procoduros nhall of radioactivo material in be devolopod and unad, a n r1 effluonts will bo kopt at small oquipment which har boon fractions of the limits speci- i.nntalled to maintain control fied in Section 20.10 6 of 10 ovor tadi oaerivo ma t eria in CFR Part 20 anel as further in gannous and liquid of f luon*r npecified in those Tochnical produced durini normal reactor Specificationn. At the sano oporatione, including expectol time the licensee in permitted oporational occurroncos, eball the flexibility of oporation, be maintain"d and u ad, to keep compatible with considorat i.onn levols of radioactive matorial of haalth and sa f ety, to assuro in offluont, roleased to t h a t- the public is provided a unrestricterl areaa as low as dependablo source of power reasonably achiovable, oven undor unusual operating conditions whi.ch may tom-pararily result in releases higher than such nmall fractions, but ctill within +ho limits specified in Specificationn 3.8.B.1 and 3.8.C.1, and in Section 20.106 of 10 CFR Part

20. It is oxpecterl tha t in using this operational flex-bility under unucual operating Amendmont tio .

-203- PBAPS LIMITItM COtJDTTIOf!S FOR OPERATIOt; SU b'/ E T LI At C" H Wt i l D FM Etil'a cond i.t i on s the licensee will exert his best ef forts to knap levels of radioactive matorial in of f luonts as low as roanonably achieva-ble. 3.8.P Lpluid Effluonto 4.8.P Ligu id Etfluonts

1. Tho concontration of radio- Ia. Facility rocords shall be act ive materia l released f rom mai n*ai n ed of tho radio-tho si.te to unrestricted areas a ct i vo concontrations (see Piqure 3. 8.1) shall be and volomo before 'lilution li mi tod to t-he concontra ti.en of "ach l' arch of l iq u i.d specified in 10 CFR 20 ofLluont re l ea n o:1, a nd of Appendix B, Table II, Co lumn 2 t+ o avorage diluti.on fl ow for radionuclides other than anl longt-h of +- i m o ovor noble gason and 2 X 10-* which each discharlo uCi/nl total activity occurrod.

concentration for all dis- 11<. Prior to release of nach solved or entrained noble bat ch of li luid of fl uen t , gason. Uith the concentration a nimplo rhall bo ta kon ot radioactive matorial f rom that batch and analynod roloaned from the site to for the concontration of unrestricted areas exceeding oach niunificant gamma ou rr qy these limits,immediatoly prak to al omanst ra to com-decreano the roloa se ra te pliance with 3.8.P.1 un inq of radioactivo mat erials t h" ci r cula ting witor and/or increase the dilution flow rat e at tho *in' flow rato to rostorn the of discharan. concentration to wi. thin the limits and provide prompt Ic. Radioac'ive liquid wanto noti f ica t i on to the Commission "ampling and activi & y analynic pursuant to Specif ication shall be por f or me l in 6.9.2.a. accordanco with Table 4.8.1.

2. Tho dose or dose commitmont 2. cornil a

• ivo done contri-to an individual trom radio- but ions nha ll bo de*erminol act-ive materials in lirInid in accord mco wi + h ' he of t -

effluents roloased from sit o Doso Calculat ion Mmua 1 the sito to unrestricted (ODo 1) at least onco per areas (seo Fiqure 3. 8.1) month. shall be limited:

a. Durinq any calendar quarter to 5 3.0 mrem to tho total body and to f 10.0 mrem to any organ, Amendment tio.

-204- PBAPG L I M IT I!!'; C0!!DITIOFG l'OR OPEP ATInti S UR'/ EI LL t t:C F P_F o'1 1 9 U 1 EtIF n and I; . During any calenlar year to 5 6.0 mrem to tho total body and to $ 20.0 mrem to any orqan. Whon the calculate (1 dose from the release of radioactive materia ls in liquid offluonts ex coeds any of the above lin. *s, prepare and submit to tho Commission within 21 working days, pursuant to Specification 6.9.3, a Spoeial Poport which ident-i fion the act-ions to l'o taken to roduce the releases of radioaetive matorials in liquid effluonts during tho subsoquent three calon-dar quartors so that the average dose or dose commitmont to an indiv-idual from such roloanes durinq these four calen-dar quarters is within 6 mrem to tho total body and 20 mrem to any organ. This spocial Report nhall also includo an assessment of the radio-logical impact on tho potentially a f f ected drinking wator supplios with regard to 110 CFF 141, Safe Drinking Wator Act. Hoactor shutdown is not required.

3. During release of ra dioac tivo 3a. The li piid ef fluen+ rad-wastes, the following iation monitor shall be conditions shall e a1ibra red at least once be met: per 18 months with

a. The minimum dilution a known rad i oa c tive water required to sourco positioned in a Amendment Fo,

-205- PPAPS LIMITIMG Cot:DITI4f15 FOR OPPPATION SilP V F i l,I.TdlC F P r o n l i 'cM Errr:, satinfy 3 . 0 . 11 . 1 sLall reprorlucible ononotry be met. with ronp< ot to the non-

b. Tho gronn activity nor and a* ieant enco monitor and flow non- per qua rtor by moar. of a itor on the wa sto eheck nourco. Ad lie iona 1 Ly, offluent lino an i nnt rum en t f unctional t ont nhall bo opo ra- nhall 1e porformo1 at least bio oxcept an specifie:1 once por month anci in 3.8.P.3.d and 3.8.B.3.e, an1 an inntrument check balow. n ha ll bo rerforme1

c. The effluent control at loan t onco te r day monitor nhall be net dut in't reloano.

t o a larm ani! a uto-matically close the wante di.scharqo valve 3 b. Tho l irpti 1 e f fluont- flow prior to exceeding monitor nhall lo cali-

• he limits spocified brato<1 at loast onco in 3.8.B.I alovo, por 18 montha.

d. From and after the Ad lit io n all y , an instru-dat e that tho gross mont check chall to activi ty monitor on performod at leant the wante offluent onco por lay durin<r releone.

line is made or found to bo inoperable for any reason, effluont roloases may continue only during the 3c. Tho liquid of f tur nt. nucceeding 14 dayn, ra lia+ ion monit or rat-unions such monitor pointn chall bo d et. o r-in nooner mada operablo, miriol i n accordance providol that prior to with the O PC'1. initiating a releane:

1. At leact two in-dopondent camplen o f the tank's contents a re analyzed, and

2. At loast two technically qualifiod membera o f tho Facility Staff independently verify tho relea se ra te ca l-culation and liacharge line valving.

If thin requirement cannot be met, suspend release of radioactivo effluents via thin pathway. Amendment r;o . -206- PPAPS b1 MTT1 ?M COMDITIOTIS FOP OPFRATIOfJ SUPVEI LIAflCL protv irmy: 31n

e. From an1 after tho date that the flov monitor on the waste oftlucnt line in made or foun'l to bo inor rablo for any reason, effluent releanon via this pathway may continue only during the maccceding 14 dayn, unlons such monitor in sooner made operable, provide 1 tha t the flow rate in estimated at leant once par 8 hourn during actu cleasen.

4 All liquiln chall be ya. Donen luo to liquid erfl-procenrod through c.ither unnt roloanes to unren-tho wanto collector filter trictod areas nhall bo an 1 deminoralizer, the proj,c&od a+ loant onco por floor drain filter, or t- he month in accordanc? with fuel pool filtor deminer- tbo O D C.'1. alizor as appropriate prior to their dincharge when t-.h" projected dose due 4b. Tho wanto collector to the liquid ef fluent fit'or ani domin"ralizor releases to unrestricted and '- h o f loar dra in filter aroan, when avoragod nhall bo demonntrat~1 over any month, OFrablo e l oa s t- once oxc ?eds 0.12 mrom to tho por quartor, unten-total body or 0.4 mrem to utilizod to procesn any organ. 1iJuid wanto durinu *he with liquid wante boing p revious 13 wor k n , by dincharon't without ana172inq rhe 1i<1ui d treatment as requirod above p ro con n rd through tho a p-prepare and rulmit to the priato oPlipmont to dator-Commission within 21 workinq mino *ha' i t meets the days pursuant to Specifi- ro rnirononto of Spoeification cation 6.9.3, a special 9eport 3 . R . R .1. The fue1 pool filtor which includes the following deminoralizer in exompt fron information:

• hin r o'piir omon t since it ir

a. A description of alter- an attornate treatmont nate oquipment or methods nycten which in not rou-tor troatment of radio- t inoly unod to process active materials. liquiin for dincharge.

b. Lonqt h of timo the above requirements were not 4c. Tho operabi1it y o f tho natisfied. Iaivante diccharTo auto-

c. Volumo and curio con- ma&ic innlation valvo shall Amendment flo .

-207- P DA l':1 bl'4ITpfG cot!DITIOMI FOR _ OPEPi\TIOf! SilRVFI LTJ f1CF, RI <y! T P U1ET TPb _,_ t r. n t of tho wa s te d i r,- bo chocke.1 mon *hly. chargod which was not procennod, bu+ which requir*rl proconsing.

d. Action (s) taken to pre-vont a recurrence.

P'.tct or nhut< lown 19 not roquirod. 3.8.c cancoun Ef flisonts 4.8.C G,inoons i:f f l uonto

1. ihe done rat e in unre- la. Padioic+ive gasoons waste, ntricte<1 aroan (sne particulato an<l io: lino Firiure 3. 8.1) duo to nanpli n'i an't a ct i vi ty ra lioactive materials analymin chall be po r t o rno:1 in gaseour o f f luents re- in accar< lance wi t h Tablo loacel I rom t.he sit e chall 4 . R . 2.

Le limirod to the following: lb. Tho dr" ra t e trum

a. Tho dose rate radioact ive mat orialn for noble gases shall in :Ta scoun effluents re-be limited t o i 500 leaned from tho nito nhall nrom/yr to the total body bo detormined in accor-and f 3000 nrom/yr to the danco vi&h &h> Offsit' skin. Doso ca1cul.ition Manual (oncM) at Inant onco por moa t- h

b. The dose rate for all radioio' lines and ra 1io-activo materials in particulate form and radioruclidon c'her than noble gases with half livon ornater than 8 days shall be $ 1500 mren/yr t o any organ.

Whon tho dose rates exceed the abova limits, a ppropria te corrective action shall be initiated to decrease the release rate to comply with the limit and provi<le prompt notification to the comminnion pursuant to speci ficat ion 6. 9. 2.a. 1\mendment 'b. -208- PDAPS LIMITItK1 COf1DITIO!JS FOR OPERATIO!J SUPV FI M, A!IC P RFQ:J I R EM E!'TS __

2. Tho air dose in unrostricted 2. Done cont ribu+ ions shall l'e areas (soe Fiqure 3. 8.1) det ermi ned i n accordance due to noble gases with tho CDCM in gaseous effluents released a '- least once por from tho site shall be month.

limited to the following:

a. During any calendar quarter for gamma radiation: $ 10 mrad.

Du r ing any calendar quartor for beta radiation: $ 20 mrad.

b. During .ny calendar yoar for gamma ra dia tion:

< 20 mrad. During any calendar year for beta radiat ion: < 110 mrad. When the calculated air done from radioactive noblo gases in gaseous effluents exceeds any of the above limits, prepare and submit to the Commis-sion withi.n 21 working days, pursuant to Specification

6. 9. 3. , a Special Report which identifies the causa (s) for exceeding the limi t ( s) and definns tho corrective actions t o be taken to roduco the releases of radioactivo noble Ja se s in casoonn effluonts during the remainler of the current calendar quarter and during the subsequent three cal-endar quarters so that the average dono during these four calendar quartors is within 20 mral for gamma rac'iation and fl0 mrad for beta radiation.

Peactor shutdown is not required. Amendment ?!o . -209- PPAPS ~ LIMITIt!G COtIDI_PIOIIS FOR OPEPATIOtl SUPVFILLAUCE HI' OUI FEMEliT" ._

3. The dose to any organ of an 3. Dose contri.butions shall individual from radio- bo <1etermined in accor-iodines, radioactive danco wi&h tho O DC 1 at least materials in particulate once por month.

form and radionuclides other than noble gases with half-lives grea ter than 8 days in gaseous effluents released from the site to unrestricted areas - (see Piqure 3. 8.1) nhall be limit ed to tho following:

a. During any calendar quarter: _< 15 mrem.

b. During any calendar year: < 30 mrom.

Whan the calculated done from the release of radioiodines, radioactive materials in particulate form, or radio-nucli:les other than noble gases in gaseous effluents exceeds any of the above limits, prepare and submit to the Commission within 21 working days, pursuant to specification 6. 9. 3, a Special Report which identifies the cause(s) for oxceeding the limit (s) and defines the corrective actions to be taken to reduce the reloases of ra lioiodines , radio-active materials in par-ticulate form, and radio-nuclides othor than noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an Amendment tio . -210- 1 PBAPS LT MITI titi CONDITIOtIS FOR OPERATIOf1 SU RVEI LL MICE REQ *fIPF11E:1r: . _ individual from such releases during these four calendar quarters is within 30 mrem to any organ. Reactor shutdown is not required.

4. During release of gaseous 4a. All plant effluent qas wastes *he following con- monitors shall be ca li-ditions shall bo met: brated at least once por

a. The main off gas stack 1P months with a known minimum dilution flow of ra'lioactive source positioned 10,000 cfm shall be ina reproducible maintained. geometry with rospect to

b. One reactor building the sensor, and at least exha us t vont and one onco per - {u a r t e r ly moanF plant stack gross of a chock source.

naseous activity Ad lit io na 11y , an instrument monitor shall be chock nhall be perf orme 1 operable. onco per day. From and after 4b. All plant effluen* qas the dato that both monitor setpoints shall reactor building exha ust be determined in accor-vent or both plant stack dance vi th t ho ODCM. gross ga seous activity 4c. All plant effluent gas monitors are made or found flow rato monitors shall to be inoperable for bo ca librated at- loast any reason, effluent onco por 18 months. releases via their Adlitionally, an inntrumont respective pathway may check shall be porf ornod continue only during tho once per day. nuccoeding 28 days,unless 4d. All plant effluont at least one such moni- ic li no and pa rti cula t e tor 'n sooner made namnler flow rate oporable, providod grab monitors shall bo na mple s are taken at calibrated at leant once least once por 8 hrs. por 18 months. A ddi t iona lly , and theso samples a re an instrument check shall analyzol for gross Ec perfornc1 onco pe r activity within 24 day. hours.

c. One reactor building exhaust vent and one plant stack iodine sampler and one reactor building exha us t vent and one plant stack particulate sattpler with their respective flow rate monitors Amendment tio.

-211- PBAPG I IMITT t!G COIJDITIONS FOR OPERATIOt! SU WFI UAt:CIC R EQ'! IR EM P!I"i shall bo operable. From and a f ter the date t ha t- all iodine samplers or all pa rticulate samplers for either the reactor bui.lding exhaust vent or the plant stack are made or found to be inoparable for-any raason, effluent releases via their respective pathway may continue only during the succeoding 28 days, unless at least one such sampler is sooner made operable, provided samples are continously collected with auxiliary sampling erptipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter tho end of the sampling period.

d. Ono roactor building oxhaust vent and one plant stack flow rate monitor shall be operable. From and after the dato that both reactor building exhaust vent- or both plant stack flow rate moni-tors are made or foun1 to be inoperable for any reason, effluent releases via their respective pathway may continue only during the succeedino 28 days, unless at least one such monitor is sooner made operable, provided the f low ra te is estimated at loast once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Amendmont !10. -212- PDAPS LIMITI!!G cot 1DIT10NS FOR OPERATIOt! SUWEI LLM1Cis RyII?f ME'TTS __

5. Gaseous effluents shall Sa. I!ocos due eo qasoons be processed through offluen* releases to on-the appropriate gaseous rostricted areas shall be waste treatment pro jecretl at least once per system as ironth in accordance wit h described below t be ODC1.

prior to discharge when the pro- S b. The appropriato qaseous 1ected dose due to all radioactive waste systom gaseous effluent releases oquipmnat as described from all release points in spocifica tion 3. 8. C. S to unrestricted areas,when nhall be demonstrated averaged over any month, o po ra bl e a t least once exceeds 0.4 mrad for gamma per quartor, unless radiation, 0.8 mrad for beta utilined to process radiatlon, or 0.6 mrem to gaqoous waste durinq any organ: th" provious 13 weoks,

a. Gases from the Steam Ly analyzing tho qascour Jet Air Ejoctor Dis- vaste procossed throuTh charge shall be the appropriate equip-processed t brough the mont to determine that recombiner, holdup pine, it meets the requimments off-gas filter, and of speci fication 3. 3.C.1 ofE-gas stack.

h. Gasos from the Mechanical Sc. An air sample chali 1e Vacuum Pump and Gland Steam obtainod and analyzed Exhauster discharge f rom all bu i ld in ri aroan shall be processed with a n unmonitoro l through the off gas oyhaust once por month.

stack.

c. Roactor, turbine, radwasto, and recombiner building atmospheres shall be processed throucih permanently or temporarily installed equipment in the appropriato hui 1 ding ventilation system and the Reactor Buildino Ventilation Ex haus t Stack, wi&h the exception of tho followityi unmonitored exhausts:

1. Fecirculation M-G Set and Reactor Uldg. coolina water equipment rooms.

2. Control room utility an:1 Amendment t io .

-213- PIM P.9 LIf11TItf; Col1DITIOt;S FOR OPERATION SUPV EI LL A t!C E_ T3 EOU IU EM Fifr3 __ toilet rooms.

3. Cable spread room.

4. Emergency switchgear rooms.

5. 125/250 VDC Ba ttory rooms and the 250 VDC Battery rooms.

6. Administration building maintenance decontamination area.

With gaseous wante being discha rged without treatment as re-qui. red above, propare and submit to tho Commission within 21 working days pur-suant to specification 6.9.3 a npecial Report which in-cludes the followinq in fo rnia t ion:

a. A description of alter-nate equipmont used fo r treatnont of radioactive matorials

b. Length of time the above requiromonts were not natisfied.

c. Volume and curie content of the waste discharged which was not processed, but which required pro ces s i.ng.

Reactor shutdown is not required. 6a.Except as spec i f ied i.n 3. 8.C. 6a. 7,n i n e, t r u mo n t check of tho 6b bolow, two hydrogen mon- ororating hydrogen moni tors itors downstream of tho cha 11 he performed once recombinern shall be por day. operable during powar oporation. 6b If the abovn n peci fied 6b. T h" hydrogon nonitors and required hydrogen as ;ociated alarms downstroan monitors arn not opera- of t' h o recombiner ble, an ordorly reduction shall be calibrated once per of power shall be month. initiated to bring the hydrogen production Amendment No. -214- P DA PS LIf-1ITIf!'l CO?IDITIOtIS _FOR OPED ATIOIl SURVFILL;tiCE P FO U I P EMETI TS rate to less t ha n 4 % of the off-gas flow rate. 7a .The radioact ivity release ra to 7a. Tho ra lioactivity release rate of noble gases from the of noble gases from the St<'am Jet Air Ejector 9toam Jet Air Ej<>ctor dis-d iacharge as determined cha rqn chall te determined by quantitative analysis of to be within limits i'lentifiable ganna at the following frequencies emitters shall not oxceel by performing a n isotopic 3'40,000 uti/sec. With analysis of a representa-the radioactivity releaso tivo samplo of garns taken rate of noble gases from at the discharue of the steam Jet Air Ejector Steam J"t Ai" Ejector, dischargo exceeding 340,000 uCi/sec 1. At leant onco per month rentoro the radio- untosn the uni

• has activity release rate to been out of servico for within its limit within the "ntiro nonth.

48 hrs. or be in hot  ?. Nithin 4 hrs, followini staniby within the next an increase, if tho 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. o f f-<Tas monitors indicate an incrrase of aroater than 50"' in the

teady state fi ssion na s role.tsu at t er f actorinq ou& increases due to pqWr>r Chancos.

7b one Steam Jet Air Ejector 7b All SMam det Air Ejector radiation monitor shall rali at ion monitors shall bo bo operable during opera- cali bra ted a t least once tion of a main condenrer por Tiar&or and an instru-Steam Jet Air Ejector. men' check shall be Moon loss of both Steam performecl onco per day. Jet Air Ejector ra liation monitors, oither tonpora ry monitors shall bo used or initiate an orderly shutdown and hava the nain steam isola tion valvos closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

9. Tho primary cont ativnent shall not bn purged except through the standby Gas Treatment System.

Amendment tio. -215- pBAPG LIf4ITItM CONDITIO fS FOR OPERATIO7 SURVFI LLMIC" R E(d1 IR FI'E NTS _ - - 3.8.D 40 CFR 190 . 4.8.D 40 CPU l'10 The dose or dose commitment Cumulative dose contrit.utions to a real individtial from shall bo determinod in all uranium f uel cycle accordance with +ha O DCII. sources is limited to 5 25 mrem to the total body or any organ (oxcept the thyroid which is limited to 5 75 mrem) over a period of 12 consecu-tive months. When the calculated dosa from the release of radioactive materials in liquid or ganoons offluento exceeds twico the limits of Specifications 3.8.B.2, 3.8.C.2 or 3.R.C.1 prepare and submit a special Report to the Commission pursuant to Specification 6.9.3 and limit the subsequant roleasos such that +-he dose or dose commitmont to a real individual from all uranium fuel cycle sources is limitod to i 25 mrem to the total body or any organ (except the thyroid wh ich is limited to 5 75 mrom) over 12 consecutive months. This Spocial Report sha ll in-clude an analysis which demon-stratos that radiation exposures to all real individua is from all uranium fuel cycle sources (incluiing all effluent pathways and direct radia tion) are less than tho 40 CFR 190 Standard. Otherwise, a variance from tho Commission Amandment If o. -216- PHAPG LIf41TTI!G CONDITIONS FOR OPERATION SilRV EI I.I, AIICE R Ent I I P Ef t ETI TS to pormit rbleases which oxceed the f40 CFR 190 Standard shall be obtained. 3.8.E. Padiological Environmontal fl . 8. E Pa di o loq ica l Fnvironmcntal Monitoring Monitoring

1. Tho radiologi. cal environ- 1. The ra diologica l environ-mental monitoring prog ra m montal monitorinq namplen shall shall bo conducted as be collocte1 at tho locations doscribed in tho ODCM. and analyzed as specified Deviations are permitted in the ODCM.

from the required sampling Deviat-ions a r e per-schedule if specimens mittod tron the roquire'l are unohtainablo due to nampling nchedule if ha7ardOus Conditions, 9 p"C imons a re unohtain-seasonal unavailability, or a bl o duo to har.ardJus con-mal f unction of automatic d ition s , sea sona l un-samnling e<ptipment. If the a va ilabil i* y, or mal-latter occurs ef fort shall function of automatic bo made to complote cor- sampling "quipmont. If the rect.ive action prior to latt or occurs, effort tho end of the next nhall be ma'le to sampling period. complote corroctivo a ct ion prior to the oni

a. 9 hon the ra d io- of th" nox" samplino logica1 onvironmenta1 pe r i o 1.

monitoring program is not conducted as described in the ODCM propare and submit to the Commission, in the Annual Padiological Environmontal Oporating P? ports, a description of tho reasonc for not con"lucting the prog ram as roquired and the plans for proventing a re-currence.

b. When the level of radioactivity in an environmental sampling medium at one or more of tho loca tions specified in the ODCf f exceeds the limi.ts of Amendmont No. -216a-

PDAPS LIMITI!!G CO!1DITIONS FOR OPER ATION SURVErLLANCF R Eg'11 P FI1 E?iTH _ Tablo 6.9-1 when averagerl over any calondar quarter, pre-pare and nubmit to the commission by the closinq of tho month followiry the end of the affectod calendar quartar, a special Report which includes an evaluation of any release , conditionn, environmenta1 factors or other aspects which caused the limits of Table 6.9-1 to bo oxcoeded. This re po rt is not required if the measured level of radioactivity was not tha re s u l t- of plant effluentn; however, in such an event, the condition shall be reportod and described in the Annual Radio-logical Environmental Operating Report.

c. When tvilk samoles become permanently unavailable f rom any of the samplo locations listed in the ODC:1, locations from which replacement samples are obta inab le must be added to the onvironmental monitoring program.

2. A land use census chall bo 2a. TI o land uno census conducted and shall identify chall be conducted the locati.on of the nearest at 1^ast once por cal-milk animal in each of the o n'ia r yea r between t- hn 16 meteorological sectors dat or of Juno I and within a distance of fivo netober 1 by a door-to-miles. door :urvoy, Iy con-

a. When a land use census nultinq local agriculture id ent i fi_ es a new loca- authorition or by seme tion (s) which yields a other olui.valont moans.

calculated dose or dose commitment at least 257 Amendment tio. -216b- .~. '. PDAPS LIMITIt!G COf1DIPIONS l'OR OPERATIOtl SURVEI LLAf;CE _ P EQUIF Ef4E!TTS __ greater than the values currently being cal-culated in Specification 3.8.C.3, prepare and submit to *he Commission within 21 working days, pursuant to Specifi-cation 6.9.3, a Special Report which identifies the new location (s) .

b. When a land use census identifies a location (s) which yields a calcu-lated dose or dose commitment (via the name exposure pathway) at least 25% greator than a location from which samples are currently being obtained in a cco r-dance with Specifica tion

3. 8. E.1, an attempt shall be mado to add the new location to the radiological environ-mental monitoring program within 21 working da ys.

Tha indicator sampling location having the lowest calculat ed dose or dose commirmont (via the same exposure pathway) may be deletod from this monitoring program after Octobor 31 of the year in which this land use census was conducted. A t ie n d me n t, Mo. - 210;c- PBAPS TABLE 4. 8. I hADIOACTIVE LIQUID WASTE S AMPLII;G At1D At1/(LYSI S_ Sa mple (s)(6)(1) Sa n. pie Ag Sample Ptequency Sample Ana lysis _Detecta ble Limit ( 2 ) Waste T a ni, to Each umtch Quantitative SX 10-7 pCi/ml be releucea Analysis or Identifiable Gamma Emit terst 3 ) 1131 1 X 10-6 pCi/ml Proportional Monthly P32 1 X 10-6 pCi/ml Ccmposite of Tritium 1 X 10-5 pCi/ml ca tet.es Gross Alpha 1 X 10-7 uCi/mlC*) Proporticnal Monthl) Sru9 S X 10-8 pCi/ml C om po si tt. or Sr90 5X 10-0 pCi/ml batches One batch Munthly dissolved noble 1 X 10-5 pCi/ml gases t4GT ha

1. Certain a.ixtures of radionuclides may cause intet terence in tne u.easurement or individual radionuclices at their oetectable lia.i t especially if other radionuclides are at much higher concentrations. Under these circuanctances use ut snown ratios or raalonuclides will Le appropriate to calculat e the levels or such radionuclides.

2. 1he utove sample det_ectable limits are applicable to grab samples used to determine liquid waste release levels.

heportea data shall reflect any improvement in detectable litnits as such improvements are achieved.

3. Si gni fic ant. radicnuclides are to be identified and where posuible, quantitative values obtained.

4. Selt absorption will result in a higher detectable limit for d1pha Counting.

5. For certain radionuclides with low gamma yield or low energies, or for certain racionuclide mixtures, it may not be possible to measur e radionuclides in concentrations near Amendment I;a . - 216 d -

PBAPS the sample detec table limit. Under these circumstances, the sanple detectable limit may be increased inversely oroportionally to the magnitude of the gamma yield (i . e. , 5 x 10-7/I, where I is the photon abundance expressed Ts a 1+ c im al fract Lon) , but in no case shall the sample dotectable limit , au calculated in this tranner for a specific radinnuclide, be grea ter than 10% of the MPC valu e specifiett ni iO C FR 20, Appendix B, Table II, Column 2.

6. The principa l ga mma emi.tte rs f or which t he sample detectable limit speci ficat ion will apply are exclusively the f ollowi ng ra lionuclides: Mn-54, Fe- 59, Co-58, Co-60, Zn-65, Ma-99, Cs-134, Cs-137, Ce- 141, and Ce-144. This list doe s not mean that only these nuclides are to be detected and reporte3.

O t h eir p.sar.s wh ich a re naasurable and identifiable, together wit h t he above nuclides, shall also be identified and roported. Nucli les which are below the sample detect able limit for the analyses should not he reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than r quired, the reasons shall be documented in the semi-annual efflur-nt report. The values listed are believed to 1:e attainable. ,\menim-nt No. -216 e - P13APS . table 4.8.2 RADIOACTIVE GASEUUS WASTE S Af@LIIJG AND ANALYSIS FROM i4A IIJ GFF aiAS STACK AIJD hEACTOR EUILLIhG VE!1T EXilAUST STACK Sample (1) (5)(77 Sa.ntl e 'l y p e, Sample Frequency Sample Analysis Detecta ble _Li mit Gran Sa thpi e Monthly (2) Quantitative 1X 10-* pCi/cc(J) Analysis of Identiriable Gamma lunitters otab sample guarterly Tritium 1X 10-6 pCi/cc Charcoal Weekly (4) I-1J1 1X 10-12 pCi/cc(3)(63 F11t u r s W e c i,1 y 1-133 1X 10- o pCi/cc( 3 ) 1urticulate Filters Weexly (4) Quantitative 1X 10-10 pC1/cc( 6) Analys_s of Identiriable Gainma Emitters I- 131 1X 10-12 pCi/cc(3)(6) Particulate F i l t e. r u Monthly Gross Alpha 1X 10- 11 pCi/cc (composite or weer.ly 111t er s) Putticulate Monthly Sr89 1 X 10-11 pCi/cc Filters Sr90 1 X 10-at pCi/cc (CoihpoS1te or Wee).ly 111te: 5) No'I En

1. Ine above sample detectable limits are applicable to grub cumples used to determine or verity airborne waste release levels. Reported data snall rerlect any improvemant in uett_ctable limits as such improvements are acnieved.

2. Analysis shall also be maue rollowing each rerueling outage.

J. Certain mixtures or radionuclices may cause interterence in tt.c measurement or individual radionucliaes at their Amu . a.n c r. t IJo. -216 f - PBAPS det3ctable limit especially if other radionuclides are at much higher concentrations. Under these circumstances use of known ratios of radionuclides will be appropriate to-calculate.the levels of such radionuclides. 4 Analyseu q ha il a tuo 1:e perf ormed at least once per day for at least 3 days until a decreasing treral is evident tollowing each shutdown, sta rt up or similar operational occurrence af ter determination of a significant increase in radioiodine releases. '; . For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possi ble to measure radionuclides in concentrations near the sample detectable limi t. Under these circumstances, the cample detect able limit may be increased inversely proportionally to the nagnitude of the gamma yield (i.e., 1 10-*/I, where I is t he photon abundance expressed as a leciaul t ract ion) , but in no case shall the sample detoctable limit, ar calculated in this nanner for a 3pecific radionuclide, he greater than 10% of the MPc value <:pec i fied in 10 CFil 20, Appendix B, Table II, Column 1.

f. Dane 1 on th- design sample flow rate for one week. When sa mples c )1 Lected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a re analyzed, the co r re s pon ling sample detectable limit may be increasqd by a factor of 10.

7 Th" principal gamma e.ai t t e r s for which the sample detectable limit specification will apply are exclusively thu following ralionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe- 135, and Xe-133 f or qaseous emissions and Mn-54, Fe - 59, co-58, Co-60, 2n-65, Mo-99, Cs-134, es-137, Ce-141, and Ce-144 for pa rticulat e emissions. This list does not mean tha t only these nucli les a re to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclirles, shall also be identified and reported. Nuc li d es which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level for that nuclide. When unusual circumstances result in sample detectable limits higher than required, the reasons shall be documented in the semi-annua l ef flunnt report. n n im nt 'lo. -216 g - [ tt W h (\./$ N ( , _. si. s i }p , ' .[^ ~ ~ ., hI /

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i j$ 7$ ., (-  : PHAPS 3.S.A & 4.8.A Bl.SFS gonoral_ lt is expected that releaue s of radioactive material in eifluents will be kopt at small fractions of the limits specified in w tion 20.106 of 10 CFR, Part 20. At the same time the licensee is permitted the flexibility or operation, compatible with consi.derations ot health and safety, to assure that the public is provi.ded a dependable source of power even under unusual opc rating conditions Nhi.ch may temporarily result in relea ses hiqhar than such small f rac tions, but still within the limits o"cifi ed in Section 20.106 of 10 C FR , Part 20. It is expecte:1 that in using this opera tiona l flexibility under unusual aperating conditions the licensee will exert his best efforts to hem levels of radioactive material in effluents as low as p ra ct i ca bl e. 1 id E S-lbl.! F.!EEi concantration This cpecification is provided to ensure that the concentration oi radioactive materiale released in liquid waste effluents from

• h.

site to unrestricted areas will be within tha concen t ra tion levels specified in 10 CFd, Part 20, Appendix B, Ta ble II. This i n ata nt aneous limitation provides additional assurance that the levels of radioactive ma ter ia ls in bodies of water outside the sit - will result in exposures wit hin (1) the Section II.A design objectives of Appendix I, 10 CFR, Part 50, to an individual and ( 2) the limits of 10 CFa, Part 20.106 (e) to the population. The concentration limit for noble gases is based upon the assumption t h a t- Xe- l 'i S is the controlli.ng radioisotope and its t4PC in air (s ubm or s io n) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (I CR P) Publicat ion 2. Daco '" Sis specification is provided to implement the requirements of Sect. ions II.A, III.A and IV. A o f Appendix I, 10 CPR Pa r t 50. The Limiting Condition for Ope ration implements the guidance set fort h in Sect ion II.A of Appendix I an.1 provides the required operatinq f lexibi li ty to implement the guides set forth in Sect ion IV. A of Appen lix I to assure that the releases of ralicactive mat erial in liquid effluents will be kept "as low a s is rea sonab ly achieva ble" . The Surveillance Requirements i.nulemont the requirements in Section III.A of Appondix I that Is men iment No. -2161- PRArs conformance wi.th the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individua1 through appropriate na thwayn is unlikely to be substantially underestimated. Tho equations are described in the Of fsite Dose Calculation Manual f or ca lcula ting the doses due to tho actual release rates at ra d ioa ct iv o n.tterials in liquid offluents. This Specification a pplies to the rol Tse of liquid effluents from the site. Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, t he relea sos of radioactive materials in liquid effluents. The operability and use of. thir instrumentation is consistent with the requiremonts of ';eneral Dasign Criteria 60, 63 and 6 '4 of Appendix A to 19 CFP, Part 50. System operation The operability of the liquid radwr.ste troatment- svntom ennuros that this system will be avai.lable for uno whonevet liquid effluents require treatment prior to release t o the environment. The requirement that the appropriato portions of this systom in used when specified provides assurance that tho reloases of radioactive materials in liquid effluents will bo kept "ar low as is reasonably achievable. " This specification implonents the requirements of 10 CFR, Part 50.36a, General Denign crieerion 60 of Appendix A to 10 CFR, Pa r t. 50 and doniqn obj oet i vo n o c t-i o n II. D of Appen<lix I to 10 CFP , Part 50. The specified limi t- n governing the use of appropriate portions of *-ho li<piid radwanto treatment system were specified as a suitable f ract ion of t- h " quide not forth in Section II.A of Appondix I, lo crP, Part 50, for liqui.d effluents. Amendment No. -216j - PBAPS 3.8.C E 4.8.C BASE.} Dose This specification is provided to ensure that t.he dose f rom qaseous effluents from the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted aroas. The a n nua l dose limits are the doses associated with the concentrations of 10 CFR Pa rt 20, Appendix B, Table II. These limits provi le reasonable assurance that radioactive material discharged in gasoons effluents will not result in the exposure of an individual in an unrestricted area to annual avorage concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b) ) . The specified limits restrict, at all times, the gamma and beta dose rates above backgrounl to an individual in unrestricted areas to 5 500 mrem / year to tho total body or to 5 3000 mrem / year to the skin. Theso dose ra t e limits also restrict, at all times, the correspon: ling t hyroid dono rato abovo backgroun1 to an infant via the cow-mi Ik-int a nt pa thwa y to 5 1500 mrem / year at t he critical pathway dairy f arm. Doso n tioble Gases This specification is provided to implement tho requiremonts of Sections II.B, III. A and IV. A o f Appondix 1, la CFR Part 50. Tho Limiting Condition for Operation implements the guidance set forth in Section II.n of Appendix I and provi des tho requirel operating floxibility to iraplement the guides sot for&h in Section IV.A of Appendix I to assure that the relea son of radioactivo material in gaseous ef fluents will be kepF "as low as is reasonably achievable". The surveillance Po'piiroment s implenont the requirements in Section III. A of Appondix I tha* conformance with the guidances of Appendix I bo shown by calculational procedures based on models and data such that tho actual exposure of an individual through the a p pro p r ia t o pa

• hwa ys is unlikely to be substantially underestimated. The q uations are described in the Of fsite Dose calculation flanu 11 for calculatino the doses due to the actual releaso ra tos of radioactive noble gases in gaseous effluents.

Dose, Radiciodinan t Radioacti"o Matorial in Particulate Form and Radionuclides other Than tJoble Gasos This specification is provided to implement t bo roquiroments of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. Tho Limiting Condition for Operation implomonts t ho gui d 1nce set forth in Section II.C of Appendix I and provides tho required oporating flexibility to implement the guides set forth in Section IV. A of Appendix I to assure that the reloase, of Amandment !!c . -216 k - PBAPS radioactive materials in gaseous of fluente vill ba kept "as low as is reasonably achievable". The Surveillance Poquiremontn implement the requirements in Section III.A of Appendix I that conformance with the guidance of Appendix I bo shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pa thways in unlikely to be substantially underostimated. The equations are described in the offsite Done Calculation ttanur' f or ca 1culating the doses due to the actual release rates of the subject materials. The dose rate specifications f or radioiodines, radioactive naterial in particulate form and ra d ion uclid es other than noble gases with half lives greater than night days are dependent on the existing ra'lionuclid e pathwa ys to man, in the unrestricted area. The pathways which were examined in the development of these specifications were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequont consumption by man, 3) deposition onto grasny areas whero milk animals and meat producing animals graze with consumption of tho milk and moat by man, and 4) deposition en the ground with subsequont exposure of man. Instrumontatio_n The radioactive gaseous etfluent instrumentation is p ro vi de<1 to monitor and control, as applicable, the reloases at radioactive materials in gaseous effluents. The operability and use of instrumentation in consistent with the requirements of Genoral Design Criteria 60, 63, and 64 of Appendix A to 10 CFP, Pa r t %. Svatem operation The operability of &he gaseous radwaste treatmont system onsurer that this system will be available for use whonever gasoons effluents require treatment prior to release to tho onvironmen*. The requiremont that appropriate portions of this syntom be unod when specified provides reasonable assuranco that the roloases of radioactive mat erials in liquid effluents will ba kep* "as low as is reasonably achievable. " This speci fication implemont s tl e requirements of 10 CFR, Part 50.36a, General Dosion Criterion fn of Appendix A to 10 CPR, Part 50 and design ehjoctivo qcetion II.D of Appendix I to 10 CFR, Part 50. The s peci fied limit, governing the use of appropriate portions of tho gancous ra d wa s t e treatmont system wero specified as a suitablo fraction of the guidance set forth in Sections II.D and II.C of A ppr n-li x I, 10 C FR , Part 50, for caseous effluents. HydroJon Monitors Amendment No. -2161 - PBAPS Specification 3.0.C.6 is to mitigate the consoquoncen of a hydrogen explosion. f4ain Condenser Restricting the gross radioactivity rate of nol,lo gason from the main condensor provides reasonable assurance tha t the total l'oly exposure to an indi.vidual a t the exclusion area bounlary will not oxceerl a small fraction of tho limits of 10 C FR , Part 100 in tho event thin effluent is inarivertently discharged diroctly &o the environment without treatment. This specification i r"plomont s t he requirements of General Design Criteria 60 and 64 of 7ppen'lix A to 10 CFR, Part 50. Containmant Puron Specification 3.8.C.9 require s that the primary containment a*mosphero roceive treatment for the removal of 'H s 'oun iodinn and particulates prior to its release. Amendment tio. -216m - PPAP3 3.8.E E fl.8.E IMSES Mot 1ITORITIG PROGPAtj The radiological monitoring program required l>y thin specificat ion provides measurements of radiat ion and of radioactive materials in those exposure pathways and for thoso radionuclides, which lead to the highest totential r aili a t ion exposuras of individuals resulting from the s ta t ion oporation. This monitoring prog ra m thereby supplement s the ra liological effluent monitoring program by verifying that the moasurablo concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effloant maasurements and modeling of the environmenta 1 oxposure pathways. The monitoring program was develpped utilizing the oxporience of the first tour years of commercial operation. Proaram chances may he initiated basod on the additional oporation 11 ex perience. LAt!D r]SE CEt1GTTS This specification is provided to ensure that s i g ni f i ca n t changes in the use of unrastricted areas are identifie l and that modi f i ca tions to t b monitoring prooram are attemp'ed if warranted by the results of this census. Thin censun satistim the requirements of section IV. B. 3 o f Append ix I Fo 10 CFP Part 50. Amendment tio. - 216n - PDAPS 6.5.1.6 Continund

h. Roview of the Plant security Plan and int >1ementin r procedures and shall submit recommen< lod chancies to the Plan, to tho Chairman of the Operation and Sa fety Review Committee.

i. Poview of the Emergency Plan and implementing procedures and shall submit recommonde'l changes t o the Plan, to tho Chairman of t-h e Or.eration a nd Sa fety Review Committee.

1 Review of every unplanned releaso report able under

6. 9. 2.b. (5) of radioactive matorial to tho environs; evaluate the event; specify remedia l action to prevent recurronce; and dacnment tho event description, evaluation, and corroctivo action and the disposition of the carroctivo action in the plant records.

Authority 6.5.1.7 The Plant Operation Review Committeo shall:

a. Recommend to tho Station Sut erintendent written approval or disapproval of items considerod unler

6. 5.1.6 (a) through (d) above,

b. Ronder determinations in writing 'eith rega rd to whether or not each item considerol un' lor 6.5.1.6 (a) t hrough (c) above constitutes an un re viewed safety question, as defined in 10 CFR 50.59.

c. Provide immedia te written notifica tion to tho Suporintendent, Generation Division-flucloa r or, in his absonce, the Suporintendent, Generation Di vi s io n-- Fo s si l- Hy dro , and t ho Oporation and Ga fety Review Committee of disagroemont betweon th" POFC and the Station superinton lant; however, tho Station Superintendent shall hav> ren pons ibili t y for rosolution of such disagreem"nta pu ra n a n t- to 6.1.1 above.

Record s 6.5.1.8 The Plant Operation Revicw Committce oh111 mai nt ain written minutes of each moeting and copios shall 1e provided to the suporintendent, Generation Division-tJuclear and Chairman of the Operation and nafety Peview Committee. Amendment ::o. N -248- PBAPS 6.5.2.8 Continued

e. The Facility Emergency Plan and implement inq procedures at least once per two yea rs.

f. The Facility Security Plan and implementing procedures at least once por two years.

q. Ar,y other area of facility operation considorm1 appropriate by the OSSR Committee or tho Vice .,

President, Electric Production.

h. The radiologica1 environmenta1 monitoring proqram and the results thereof at least once per yoar.

1. The Offsite Dose Calculation Manual at least enco per two years.

Au*hority 6.5.2.9 The OSR Committee shall report to and advise t he Vice President, Electric Production on those arear of responsibility specified to Section 6. 5. 2. 7 and 6.5.2.8. Records

6. 5. 2.10 Pecords of OSR Committee activities nha ll bo prepared, approvod, and distributed as indicate 1 holow:

a. '1inutes of each OSR Committee w or inq nha ll be propa red, approved and forwarded to th" 'lico President, Electric Production within la days following each meeting,

b. Feports of reviews encompassed t y Section 6.5.2.7.e,f,q, and h above, shall bo propared, approved and forwarded to the Vice Pres Hen

• Electric Prod uc tion within 14 days tollowino completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 abovo, shall be forwarded to the Vice Pr"nident, E]"ctric Production and to the management positions rosponsible f or the areas audit ed within 30 days after completion of the audit.

Amendmant No. -252- P B A P!1 6.9.2 Continued (7) Conditions arising from natural or ma n-na da evonts that, a s a di rect result of th? event toquiro plant shutdown, operation of safety systoms, or othar protective measures required 1y technical s peci fi ca tion s. (8) Errors discovered in the transi<>n* or accident analyses or in the methods used for such analyson as described in the safety analysis roport or in the bases for the technical specifications that have or could havo permitted reactor operation in a manner loss conservative than assumed in eh" analyses. (9) Perf ormance o f st ruct ures, systoms, or compononts that requires remedit;l acticn or correcti.ve measures to prevent operation in a mannor loss conservative than assumed in tho accident analyser in the safety analysis report or technical specifications ba ses; or discovery during plant life of conditions not spocif ically considered in tho saf ety analysis report or technical speci fications that require remo lial action or corrective measures to prevent t- h o oxistence or development of an unsa f e condit- ion. ?!ote: This item is intended to provida for raportin<r of potentially genoric problenn. (10) occurrence of an unusual or importan* radiolo ica1 ovent that has potential environmontal impact from unit operation, or that has high public jnterest concerning envi.ronmental impact trom unit operation.

b. Thirty Day Writien Reports. The reportable occurrences discussed below shall be the subject o f writ t en ro po rt s to the Director of the appropriate Rogional of fico within thirty days of occurrence of the even'.. The writ ten re po rt shall include, as a mini mum, a complotel copy of a licensee event report form. I n f orma tion provided on the licensee event report form nhall In supplemented, as needed, by additienal narrative material to provide complete explanation of th" circumstances currounding the evont.

Amendment tio . -256- PPAPS (1) Roactor protection system or enginnerod natety feature instrument settings which are foun1 to l'e less conservative than those es tablirhe 1 by th^ technical specifications but which do not prevont the fulfillment of the functional requiremonts of a f fected systems, ( 2) Conditions leading to operation in a degraded mole permitted by a limiting condition for operation or plant shutdown required by a li mi* i nq condition for operation. Note: Poutine sitrveillance testing, instrument ca libra t ion, or preventative maintenance which require system configura tionn as described in items 2.b(1) and 2.b(2) neel not bo reporto1 except where test resultn thomnolvon revnal a degraded mode as described above. Amondment No. -256a- PP,APS 6.9.2 continued (3) Observed inadetuacios in the implementa tion of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection system: or enqineered sa fety feature systois. (4) Abuormal degrelation of systems othor than those specified in item 2.a (3) abov e designod to contain radioacti.ve material resulting from the f ission process. tiote : Seale'l sources or calibration cources are not included under this item. Leakaqo of va lvo packing or gaskets within tho limits for identified leakage set forth in Technical Specifications need not ie roporto1 under this item. ( 5) An unplanned offsite release of 1) moro than 1 curie of radioactive material in liquid ef fl uents,

2) more than 150 curies of noble gas from a roof vent or 15,000 curies of noble gas from the st a ck in qaseous effluents, or 3) moro than 0.05 curios of radioio:line from a roof vent or 9 curies of radiciodine from the stack in qaseous of f luonts.

The report of an unplanned offsito reloase of radioactive material shall inclu lo a do cription of the event and equipmont involved, *be cau s o (s) of the unplanned release, the actions &ahon to pro va nt-recurrence, and the consequences o f tho unplanned release. (6) Measured levels of radioactivity in an environmental sampling medium detormine1 to oxcre'l the reporting level values of Table 6.9-1 when averaged over any calendar quartor sampling period. When more than one of the radionucliles in Sable 6.9-1 are detected in the sampling medium, this report shall be submitted if: conce nt ra tion (1)_ + concentration _R)_ + ...>1.0 limit level (1 ) limi' lovel (2) When radionuclides other than those i.n Ta ble 6. 9- 1 are detected and are the result- of plan" offluonts, this report shall be submitted if the potontia l annual dose to an individual is alual to or qroater than~the calen<lar year limits of speci f ica tions Amendment tio. - 257 - PDAPS 3.8.B.2, 3.8.C.2, and 3.8.C.3. This roport is not re']uired if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall 1e reported and described in the Annual Radiological Environtwnta l Opera ting Report.

6. 9. 3 t]nique Reporting Requirements Special reports shall be submitted to the Diroctor of the appropriate Regional Of fice wit hin tho time period specified for each report. These reports nhall to submitted covering the activities iden t if ind below pursuant to the requirements of the applicable reference specification:

a. Loss of shutdown margin, Speci fica ti on 3. 3. A a nd ll.3.A within its days c f the event.

b. Reactor vesse1 inservice inspect ic n, S poc i fica t io n

3. 6.G and fl. 6.G within 90 days of the comnletion of the reviews.

c. Secondary Containment leak rata testinq, specification it . 7. C upon complotion of tho t. c s t .

d. Primary Conta inment loak rato tentina, Speci fication fl. 7. A upon corr.ple tion o f th > rest.

e. Calcula ted doso f rom release of ra licact ivo effluents, Specification 3.8.D.2, 3 . 8 . 9 . r4 ,

3.8.C.2., 3.8.D., 3.8.C.3. and 3.8.c.6, and land use census, Speci fication 3. 8. E. 2.

f. Realed source leakage in oxcenn of limitr Specification 3.13.J.

g. Elfluent Peleases (1) Annual Radioloqical Environ,gnFal npera tinq Poport Routine radiol ogical environmontal operat irp) reports covering the previour cal andar year shall be submitted prior to Juno 1 of oach year.

The annual radiological envi ronnental operating roports shall include s umma ri os , in te rpre ta tion s, and eva]uationn of the Amendment tio. - 258 - PDAPS results of the radiolortical environm'rntal starveillance activities for the report terio1, including a comparicon with preopora tiorni ntudies or operational con t rols (an appropri at e) , and previous onvironmontal surveillance reports and an assennmont of th" observed impacts of the plant oporation on tho environmant. The annual radiological environmontal operating reports shall i n cl u rle summarized and ta bu la t ed re su lt s o f c.11 required ra diologica 1 environmontal samples takon during the report period. In the event that nome roqui red results are not available for inclusion wi.th the report, the report sha ll be nubm i tt ol noting and explaining tho roa son n for tho missing resultn. Tho missi.ng data chall l'e submitted as roon as possiblo in a nupplementary report. The reports shall also include or rnforence from previous reports the f ol lovi rvi: a nummary description of tho radiolorical environmental monitoring prog ra m incitading sampling nothods for each namolo typa, size and physical characteristicn of each nample ty po , sample preparation nothodn, an1 neasuring equipment used; a map of a ll na mpling locations keyed to a tablo givinq distances and directions fron the miipoint between reactor vents; thn resultn of land une censuses required by the Spocification 3.8.E.2. Amendment t!o. - 259 - PBAPS (2) Semiannual Radioactive Ef f luont roloano P e rn r e and Radiation Dono Ansonnment; 13o n7 r t Routine radioactive effluont release rerorto covering the previous 6 nonths of oporation shall be submitted within 60 dayn after January I and July 1 o f ea ch yea r. The corresporrling radiation done an r onsme nt. reports shall be cubmitted within 120 dayn after January 1 and July 1 of each year. The radioactive of fluont roloano reporte shall include a quarterly summary of the quantition of radioactive liquid and gaseoun effluonto and solid waste reloaned from the st a ti on . The radiation dose assosoment reports chall include a summary of the motocrological conditions during each qua rtor with dat a summarizei on a quarterly banis an doscribed in the ODCt1. The ra licactive ef fluent roleano reports chall include the following informaeion for a11 reportable unplanned of f ni.t e releason of radioactive materials in qaneoun a rvi liquil effluents: (a) A dencription of the ovent and equi pmnnt involved. (b) Cause (s) for the unplannad releane. (c) Act ions taken to provent recurronce. (d) Consequencos of the unplannod releanc. Amendment tio . -259a- PBAPS The radiation dose assoarmen* reports <; hall include an assessment of rarliat ion doson fron the radioactive liquid and ganoous effluonts released from the unit during nach calend tr qua rter ao deceribnd in tha O DC'1. Amendment No. -259b- h- =.m .p.pe . _ . g O

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> E >1 7s e" PBAPS 6.14 of fnit-e Dorg calculatior. Manua1 JoDCM)., 6.14.1 The ODCit chall describe the mothodolo ly and pa rameters to be used in the calculation of offsite donos due to radioactive gaseoun and liquid of fluents and in the calculation of qancoun and liquid effluent moni.toring instrumontation ala rm/t r ip setpointo connintent with the applicablo Lco'n contain"<l in thono Technical Specifications. 6.1 ft . 2 Any changes to the ODCM shall be made by "ither of the following methods:

a. Licensee initiated changos:

1. Shall be submittod to the of f ice o f t he Dirnet or of the Division of Oporating Poactorn (or its nuccensor) , U.S. Nuclear Pegu la tory commi ssion ,

Wanhington, DC 20555, with a copy to tho appropriate Regional Office within '70 dayn of tho date the change (s) was inade o f f oc+ ive anI sha11 conta in:

a. suf ficiently detailod inf orm a tion to totally nupport the rationale for 'ho change without benefit of additional or nupplement al information. In f ormation nubmitted shoul1 consist of a package of thono paqesof 'he ODc'1 to be changed with each page numhoro1 and provided with an approval and dato box, together with appropriato Tnaly e or evaluations justifying tho change (s) ;

b. a determination that the changa will no&

reduce the accuracy or reliabili&y of dopo calculations or setpoint determinations; and

c. documentation of the tact that t he cha nqe ha s been reviewed and found accaptablo by the POPC.

2. Shall become of fective upon a dat." anocifie 1 anii agreed to by the PORC following thoir review and acceptance of tho cha ngo (s) .

B. Commission initiateil changes:

1. Shall be determined by the POFC to lo? applicable to the facility after consideration of facility design.

Amendment Do. - 263 - P DA P3

2. The licensee shall provide the Commi s s ion with written notification of their determina* ion of applicability including any necessary revisions to reflect f acility design.

3. Shall be reviewed by the OC3R Committoo at its noxt roquiarly scheduled moetino.

ii . The change chall become ef fectivo on a date proposed by tile licensee and confirmei by the Commission. 6.15 14AJOR CIIA!IGF3 TO RADIOACTIVE WASTE TP FATf1Eifl' GYSTE"3 6.15.1 The radioactive waste treatment nystoms aro thos. systems described in specifications 3. 8 . " . 3, 3 . 8 . P . f4 ,

3. 8. C. fi and 3. 8.C. 5, which aro used to maintain contro) ovor radioactive materials in gaseour an l l i q u i.d offluonts.

6.15.2 f4ajor chanqes to the radioactive wante syst"ma shall ho made by either of the following metho1s. For the purposo of this spocification ' major changon' is d e f in r"1 in Specification 6.15.3 bolow. A. Liconsee initiated changon:

1) Licencoe initiated changes shall be reported to + ho Commission in accordance with 10 C FD 50.59 on an annual basis.

2) The cha nge shall become ef fective upon review a n1 acceptance by both the PORC and Or,9R committro.

B. Commission initiate'l changes:

1) The appli.cabili.ty of the chango &o the facility shall be determined by tho POPr af*o: consideration of tho facility design.

2) The licen see shall provide the com ni n n i on with written notificat ion of its det ornination of appli.cability including any necen:ary revi.sions to roflect facility desiqn.

3) Tho change chall be reviewed by th" OSSP Committeo at its next requiarly scheduled.meetinq.

Amendment tio . - 26:3 - P l!A P S '4 ) The change shall become e f fect ivo on a date proposed by the licensee and conf irne-f by the Commission. 6.15.3 " Major Chanqes" to radioactive wasto nystoms chall inclurle the following: A) Changes in process equipment, com['ona n ts, structures anr1 offluent monitorino inrtrumentation from those described in the Final 'a f oty Anal ysis Report (FSAR) and evaluated in tho staff'n Gafety Evaluat ion Report (SER) ; B) Ch ang es in the design of radwasto troa t ment systons that significantly alter the characteristien and/or quantities of effluents released f rom thoso previously considered in the FSAP anri H ER ; C) Changes in system design which inva1idate tho accident analysis as descril>ed in the S ER : and D) Changes in system design that r es u lt. i n ,2 significant increase in occul at-lonal exposure of opera ting personnel. Amendment IIo. - 205 - PDAPS TliELE OF COf1T Ell'IS "me-

1. 0 De f in i. tions, Ab b re v i.a t. ions and symt'ols_ 1 1.1 Definitions 1

1. 2 Abbreviations 2 1.3 Symbols 3

2. 0 Protec tion 3.0 Monitoring 5 Limits ruquirements 2.1 Therma 1 3.1 n

2. 2 Chemical 3.z Sc 2.2.1 Diocides J . 2.1 Sc 2.2.2 Suspended Solios 3.2.2 7

2. 2. 3 pil 3.z.3 7 2.2.4 l'la n t Chemi. cal Usage 3.2.4 8

2. 3 Noise 3.3 19 4.0 Mpert Levels 5.0 nonitoring 11 11gg u i. r e m" n t s 4.1 Impingeaien t of Fishes 6.I 11

4. 2 Unusual Environmental a . .) 12 Events l

6.0 Environmental Surveillance r, s p ec i .3 1 Stu.ly Programs 6.1 Aquatic 14

a. General Ecological Survey Program 14 6.2 Chemical 39

a. Biocides J9

b. Ileavy fietals 39 6.3 Physical 40

a. Thermal Pluire Mapping 40

h. Erosion 41

7. 0 1 Adminis tra tive Con trols 48

/ 7.1 Organization, Feview and Audit 48

7. 1. 1 Organizaticn US 7.1.2 Review and Audit 48 7.2 Action to w Taken if a Protection or 49 Report Limit is Exceeded or It II.i r m t u l r;t f t c t s De tec ted

7. 3 Unit operating Procedures 50 n , n n a -, ., . , ,

FEAFS TAllLE OF COf4TEtJIS p ___. m__e_

7. 4 Plant Reporting Requirementu 51 7.4.1 Foutine Feports 51 7.4.2 tion-Routine ReportG b1 7.5 Fecords Fetention 52 7.5.1 Pecords Fet. lined for 5 Years 52 n ,, - . i _ . . < . , -

P PDAPS Tills PAGE LEFT If1TENTIOtJALLY I LATIK Amend me nt IJo. 2F/Zff ~ .. PBAPS 6.3.b Erosion obiective To determine the arrount of erosion noar the dis"h irge structure. Specification Detail drawings shall be provided showing survey dat a to define the location and elevations of the ahore line and the river bottom with respect to the discharge structure prior to operation. Bases Post-operational surveys shall be conducted it annual visual inspection reveals excessive erocion, r esulte of theco surveys shall be reported as per section 7 . 'i . Amendtrent tio. ZB/26 - f3 1 - PBAPS 'IllIS PAGE LEF T ItJTE!!TIOIJA LT,Y fila T1F: Amendment No. 2B/26 PBAPS 7.O Administrative controln 7.1 Orqaniation, Review and Audit 7.1.1 Organization_ A. The Plant Superintendent is responsible for the of eration of the facility and to assure that the tacility operales within the limits set forth in the environmental technical specifications. B. In all matters pertaining to operation of the tacilit y and to the environmental technical specificat ions, the Plant Superintendent shall report to, and consult with t he S u pe rin te nden t , Wuclear Section of the Generation Divicion or, in his absence, the Superintendent, Eoscil and liyd to Section ot the Generation Division. The ma na ge:m n t organiza tion is shown in Figure 7.1- 1. 7.1. 2 Feview ad Audit Committees ior review and audit of plant o;eration are described in Section 6. 5 of Appendix A to the opera tinq Licen m . Amendment !!o. AM ~ . PBAPS Environmental Statement. 'I h is requirement does not preclude making changes on short notice that are minor in terms of environmental impact.

2. Changes or additions to permits and certificitro required by Federal, S tate, local and regional authorities for the protection of the environment. When submitt als of changes a re made to the concerned agency, a copy chall be submitted to the 11PC.

3. Pequests for changes in environmental technical specifications.

7. 5 Records Retention

7. 5.1 Decords Fetained for 5 Years Records and/or logs relative to the following items shall be kept in a manner convenient for review and unall be retained f or 5 yea rs , unless a longer period is required by applicable regulations.

1. Records of principal maintenance activities of equipment pertaining to environmental impact.

2. Records ot environmental de via t ions.

3. Records of periodic checks, innpectionu and/or calibrations performed to verify that environmental surveillance requirem'nts are being Iret.

4 Records of any special study programs gecified in secticn 6.0.

5. Records of changes made to operating procedures, equipment, permits and certilteat.es.

Amendment tio. Zf>/2B Of fsite Doce Calculation Manu<il Peach Pottom Atomic Power station Units 2 and 3 Phi ladel p h i.a Elect ric Comt .uw Docket tios. 50- 2 77 r. 50- 2 7 8 F.,b ru ar y 1979 Tablo of contones I. Purnoso II. Instrumont Setpoints III. Liq t t i.d Pathway Dose Calculations A. Surveillance Roqu e t cw nt fl . 8. P. 2 B. Sitrveillance Requirement 4 . 8. B . 4.1 IV. Gasoous Pathway Dose Calculations A. Surveillance Fequirement '4. 8. C. Ib B. Surveillance Requirement 4.8.C.2 C. Surveillance Requirement 4.8.C.3 D. Surveillance Requirement ti . 8. C. 6 a V. 11uclea r Fuel Cycle Dose Ass essment - 4 0 C FP - 19 0 A. Surveillance Requirement 4. 8. D VI. Quarterly Doce Calculations A. Unique Reporting Pequirement- 6.9.3.2 VII. Radiological Environmontal Monitorino P ro i ra m A. 9urveillance Pequirement fl . 8. E VIII. Quarterly Meteorological Data IX. Bases ~ . I. n or_cono Tho purpose ?f the Of f site tone Calculation Manual in to establish mothodologies and proceduron for calcularinq dosos to individuals in unrestricted a rea n duo to radioactive ef fluents from Feach Pot &om Atomic Power Station. The results of these ca lculations a re required to determine compliance with Appendix A to Oporatina Licenses DPR-44 and DPR-56, " Technical Specification a nd Basen for Peach Bottom Atomic Power nta& ion t'n i t n 1:o . 2 and 3". II. Sot 30 int Detormination for Liquid E Ganrous Moni&orn A. Liquid Radwante Activity monitor sorpoint Each tank of radioactive waste is :amplcl prior to release. A small liquid volumn of thin nample in analyzed for gross gamma (well count) acti vi t y. This analysis is performed in a t1 AI woll countar. This wall counter has a counting off icioncy simila r to the liquid radwaste discharon gross activity monitor. The well counter and l i. qui d ra d wa r to discharge gross activity monitor aro calibrated against the same liquid radioactivity nource in the geometry to be used by each detoctor. An efficiency is det ermined for each radvante tank to bo re lea sed . Exceeding the expocto'l ronponno would indicate that an incorrect sample ha d boon obtained for that release and tho reloano in aut omatical ly stopped. S.P. = (tiet CPM /m1 (well) X Ef f W/ P'4) & Eackoround CPS S.P. = Liquid Radwaste gross activi.t y monitor setpoint in CPS tiet CPfi/ml(well) = uross gavna act ivity for thn radwaste camp t n tank dotormined by tho well counter Eff W/PW = conversion f actor b't.woon well countor and 1.iquid radwasto gross activi*y monitor [ CPS (H/t/ monitut) ! O PT1/ml (wol 1) ] Background CPS = Background readiou 01 eho liquid radwaste uronn a ct ivi t y monitor (C PS) The alarm and trip pot sotpoints for the liquid radwaste activity monitor are dot 'rmined f rom a calibration curve for the alarm pot a nd t rip pot. The ala rm ro t ce tt i.nq includen a f actor of 1. 2 5 t o allow ior analysis error, por so* t ing error, instrument error and calibrat ion e rror. Tho trip pot setting includes a factor of 1.35 to allow for analyni s error, pot setting erroi , instrumont error and calibration error. The flow rato determination includes a margin of assurance which includes consideration of these errors such that the instantaneous release limit of 10 CPP 20 is not exceeded. B. Liquid Radwasto Release Flow rate dotormination The flow rate of liquid radwaste released from tho site to unrestricted areas chall be nuch that the concentration of radioactive ma torial a f ter dilution shall be limited to tho concentration specified in 10 CFR 20 Appendiv B, Table II, column 2, for radionuclides other than noble gason and 2 X 10-* uCi/ml total activity concentra tion for all noble gases as specified in Technical Spocification 3.8.P.1. Each tank of radioactive waste is nampled prior to release and is quantitatively analyzod for identifiable gamma emitters as npecified in Table

4. 8.1. From this gamma isotopic analysis tho release flow rate is determined an follows:

Determine a Dilution Factor bn Dilution Factor = { ci/ml MPC1 i i pci/mi i = the activity of cach id en+ if in 1 gamma emitter in nCi/ml MPCi = The MFC specified in 10 CFR 20, Appendix B, Table II, Column 2 for rarlionuclidcs other than noble canot or ? X 10-* p.ci/ml for noble gases. Determine the Rolease Rate with t his D i lu t ion Factor by: Relea se Pate (g pm) =A X 2.0 x los BX Dilution Fac&or A = The number of circulating wa*or pumps runnini whi.ch will provide dilution 2.0 X 105 = the flow rato in gem for each circulating water pump running B = margin of annurance which incit: den consideration of the maximum orror in tho acti.vity setroint, t he max i n,im o rror i n tho flow netpoint, and possible losn of 5 on* of thn 6 possible circulatinr water pumps durinq a r"leaso. The value used for B is 10.0. C. Liqui <l rtarlwaste Releaso Fl owr aM_J ot po i n t Detormination The trip pot sotpoint for the liqui <1 radwaste relaane flowrato is determined by mul+iplying tha liquid radwaste flowrate determine'l abovo hy 1. 2 and using this value on the appropriato calibration curve for the discharge flow metor to he usod. The Peach Bottom radwaste system ha s two f low moni t ors ( high flow (5 to 3 00 gptr) and low flow (0. 8 to 15 qpm) ]. The factor of 1.2 a llows for pot settinu error a n:1 instrument error. The flow rato determination includes a margin of assutance which includes concideration of this error such that the instantaneous releaso limit of 10 CPR 20 is not exceede1. D. fiet poin t Determination for Ganogy Radwasto The high and hi.gh-high alarm sotpoints for the min stack radia tion monitor, Uni t 2 roof vent radiation monitor and Unit 3 roof vent radiation monitor are d eto rmineri as follows: High Alarm - the high alarm setpoint is sot at approximately 3 X eho nor n.a 1 ronitor reading. Hiuh-Hiuh Alarm - t he high-high ala rm setpoint is sot at a r e loa t ' rate fton this vent of approximately 3 0 ci t he instant aneous release limit of 10 CFP 20 as nnoci fied in Technical :1 pacification 3.8.C.1.a for tbo most restrictivo ca se {ssin or total body) on an unident iCied basi n. To detcrmino th"ne sotpoints solve tho gaseous effluent donc rate oquation" in noc' ion IV.A. of ""~ ODCh to ele te r min o what mala stack roloaso rato and rcof vent roloaso rato will produce rate of 150 mrom/yr and a dose rato of 900 mrom/yr to the skin (303 of Pho limit of 3000 mrom/yr) f rom each r eloa se point. Using i ho smallert (mo s t restrictivo) raloaso rate for 3- each releano point dotermino monitor renponse require 1 to produce thin relnav rato assuming a no r m 1 vent flow rate and [re<suro cor roct ion factor, net the high-hiqh alarm for approximately thin monitor ronronso. III. Liquid Pathway Dose Caleulations A. surveillance Roquiremont 4. 0. E. ? Doce contributions f rom liquid ef flurnts relaaned to unrestrictod areas shall be calculated using the equation below. This dose calculat ion unon only three radionuclides - P-32, Cn-134, and es-137. Theno radionuclides account for over 99 porcent of the + otal body dose and bone dose from liquid effluonen. ~ ni Dr = (C F) r [. i Ay - i. [ 1 - 1 4t 1 C il F 1-where: Dy = the cumulative dose commitment to the *ct al body or any organ, r, from liquid effluentn for t- h o tota l time period m , in m r o,i 2 1= 1 ot 1 (CF)r = the dose correction factor to account for tho uro of the radionucliden listed in "ahlo IT [ . A.1 in lieu ot all radionuclides identi find in liquid offlunntn. (C F) fer total body = 1.01 (CF) for bone = 1.00 & = the length of the Ith timo Jrriol ovor which C and 1 F are avoraaed for the lignid r e loa no , in 11. 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. C = tho avarage c.oncent ra tion o f t riionnel lie, i, in il undiluted liquid ef fluent durinq time poriol A t from any liquid reloase, (1'tormined by the efflurnt sampling and analysis prog ra m , Pochn ical spo ci fi ca t ion Table 4. 0.1) , in pCi/m]. Ay = the cite rola ted ingestion don ' commitment tactor to i the total body or orqan, r, f or nach ra lianuclido 1isted in Table II1.A.1, in mrom-m1 per br-p"i See Site Specific Dat a, !!oto 1. F = the nea r fiold average dilut-i.on tactor for C 1 lurin i il any liquid effluont release. Dofinod as tho ratio of the maximum tandiluted li<pt i:1 wa s te f lo'.' ilu ri n: roloano to the average flow f rom tho dischargo structurn to Conowincio Pon<l. Tablo II'.A.1 Liquid Effluont Ingertion Doon "actorr (Decay correctod) A y- Dose Factor (mrom-ml por br- ci) Radionuclide i Total Pody Pono 6 1 n-32 2.76 x 10 7.17 x 10 5 5 Co-134 1.49 x 10 4.30 x 10 5 5 C9-137 8.49 x 10 6.01 x 10 NOTE: The listed dose factors are for radienticlides that na'/ ba detected in liquid offluents and have significant dono consequences. The three radionucli ies listed above contribute over 997; of the total bo<ly dos <' and 1one dose. These factors are decayed for onn < lay to account for the timo between offluent reloano ariel inqan tion of fish by the maximum exposed individual. III.H. Surveillanco Re<1uiremont 4. 8. P.fla Projectod dose contributions from liquirl offluontn cha11 bo calculated using the met hodoloqy dencr i bed in rection III.A. IV. gascoun Pathway Dose caIcuIationn A. Surveillance Pequirement 4.8.c.Ib The dono rate in unrestricted areas duo to radioactive materials releared in qaseous ettluents shall be determined by the ext ronnionn l'olow:

1. Moble ganon:

The doce rate from radioactive noirle gan releases nhall be determine 1 by ei*her of two me tho.l s . tiethod (a) , tho Grons Beleano Methoi, assumes that all nobio qaros relaanod are the most limiting nuclide - Kr-89 for total body doco and Kr-87 for skin done. f4e tho'1 (b) , the Isotopic Analysis Motho1, utilizes the rcaults of nol:l o <1a n ana lyson required by specifica tion 't . 8 . c . l a . For normal operations, it ir ex poet e 1 that me tho 1 (a) will Le used. Ilowevo r , if n ol l o gan roleases are close to tho linirn as calculate <1 by method (a) , motho<l (1:) can h t> used to allow more operat inq f1:2xibili&y by using da ta tha t moro accurately roflock actual releases,

a. Gross Felease f4ethol D = VO + K (X/G) O TB !TS V M"

- - - - - = D = (L (X/g) + 1.1 B) O e (L + 1. 1 T1) ( X/ 0) O n s ':S TIV where: The location is the site boun lary, 1097m SSF from the vents. This location resu1&n in the hinhast calculated dose to an i n<li v i+ 1a 1 trom noble o,u, r el eas es . D = total boly dose rato, in mrom/yr. TB 7- ~ . D = skin 4000 rabo rato, in n-om/yr. s -4 V = 4.7 2 x 10 mrom/y r por p(fi / soc; +bo con sta nt for K -89 accounting for tho gamma radia tion f rom t he elevated finito p l a rre. Thic constant was doveloped using MARE p;"niram wi&h plant s peci fic inputs for'PBAPS. b = the gross release rate of noble gases from tho IIS stack determined by gross acti.vity stach monit or s averaged over one hour, i n pCi/ soc. 4 3 K = 1.47 x 10 mren/y r per pCi/m ; tho total body dose factor due to gamna omi ssions f or E r- A H. -7 3 (X/0) = 5.33 x 10 sec/m ; i hn highast calcula

• e 1 annual v a ve ra ge rolative concentration for any aroa at or beyond the unrostricted aret bounda ry f or all vent re le a s e s'.

Q = the gross release rate or noble gasen in gasrous IN effluents from vont reloases determined by grose activity vent monitorr avoraqed over ono hour, in pCi/sec. 3 ' L = 9.73 x 10 mrem /yr por pei/m ; tho ekin doc" factor due to beta omissions f or Hi-8 7 -8 3 (X/Q) = 9.97 x 10 sec/m ; tho highont calcula + ed s annual average relativo cone"n* ration from tho stack releases for any a roa a' or beyond tho unrestricted area boundary. -y B = 1.74 x 10 mrad /yr po r pei/ soc; tho co n s ta nt for Kr-87 accounting for 'So q1mma radiation f rom the elevated finite plume. This constant was developed using MARE prtira m wi+.h plant s peci f i c inputs for PBAPS. 3 3 M = 6.17 x 10 mrad /yr pc r pCi/m ; t ho air do,o factor due to camma omissions Ior Vr-37. 0- ~ .

b. Isotopi e Analysis Metho<l D (X/0)

TB = $t (V i O is + K v O ) i iv =$ D (X/0) n (L + 1.1 P ) O + (L + 1.1 M) (X/U) O 1 - i s 1 in i i V i where: The location is the site tonnelary, 10 97m 3:iF from the vents. This location results in the hittont calculated dose to an indiv idua l from nol.le gas releases. D = Total body dono ra+o, in mram/yr. TB D = Skin dose, in mron/yr. S V = Tho constant for each ident it 1o:1 noble gan i radionuclide for the gamma radiation fr om the elevated finite plumn. 'Ibe constants were developed uning the ' vim prooran wit h plant specific i n put s f or PBArri. Valuen aro 1isted on Tablo IV.A., in nrem/yr por pei/sec. O = The release rate ut noble can ra dion u cl id o, is i, in gasmus of f Joe ntn fron the ntack determined by isotopic a:nlysis aver a red over one hour, in pei/ soc. K = Tho total body done f actor due t o g a m:na i emissions for each idont ified noble gas radionuclido. Valuen a ro li ste d on Table IV.A, in rrom/yr ner pei/m3 -7 3 (X/Q) 5.33 x 10 nec/m ; *:he hiqhest calculated v annual average relat ive concantra tion f or any a rea at- or Loyon1 tho un ros trict ed area boundary for all vont releases. Q = Tho release rate of nobl" gas radionuclide, iv i, in gasecun effluentn from all vent releases determinod by isotopic arnl ysis averaoed over one hour, in pCi/ soc. 9_ L = The chin done factor duo to Ir* a winnionn i for each ident ifin 1 noble un raJianuel ido. Valuon are linted on Ta bi n T '1. A . , in 3 mrem /yr per sc i/m . -R 3 (X/0) = 9.97 x 10 sec/m ; the hig hes t calculated 9 annual average re la t ive concentra tion f rom tho stack relearon for any aroa at or beyond the unrestricted area boundary. B = The constant for nach idont ified noble gar i radionuclide account ing for the gamma radlation from the elovatod finito pluno. The constants were devnlopnd unimi MAPF program wit-h plant npaci.fic _. n p u + n for PDAPS. Values are linto'l on Table IV.A, in mrad /yr per pCi/nec. M = Tho air dose fact or due to ganna om i nci on n i f or each ident i fio.' noble aan ra d io n u cl id e. Values are lintrd on Tablo TV.A, i n mrad /yr 3 per p Ci/m . 1.1 = Unit conversion, conv< rta ai r dono to nkin donn, mrem / mrad. Table IV.A - Conntanin for Inotopic Inal vnin Mot hod (corrected for decay during t ra n si t) Total Plumo-Pody Skin Gamma Peta Air Po'ly Plume-Air Dore Dose Air Dono Dono Done Done Fac to r Factor Fa ct o r Fa ct.o r Fact o r Fact or B K L .' 1 M V i i i i i. i (mrad /yr (mrem /yr (mram/yr (n ra.1/ v r (mrad /yr (mrem /yr pe r pe r per nor por por Radionuclide n ci/ nec}_ p e i/ m 3) A ci /m 3) 1. C l /n ')_ tCi/m i j,c i / n e c)_ Kr-87 1. 7 t1E-0 4 5.92E+03 9.73E+03 6.17 r + 0 3 1.03E+04 1. M> E- 0 4 Kr-88 3.15E-04 1.47E*04 2.37E+03 1. % ? 'l

• 0 4 2.93E+03 4.72E-04 Xe-133 1.19 E-0 5 2. 9 fl E + 0 2 3.06F+02 1. "> 3 7 + 0 2 1.05E+03 1.11F-05 Xe-133 m 1.09E-05 2. 51E+ 0 2 9.94E+02 1. 2 7 P + 0 2 1.40Et03 1.01E-05 Xo-135 6.37E-05 1.81E+03 1.85E+03 1.92F+03 2.46E*03 5. 9 5 E- 05 Xo-138 1.52E-04 7.33E+03 3. ti3 E + 03 7 . 9 ri E t 0 3 3.94"+03 1.46E-04

2. Radiciodinen and radioact ive mat orla 1r in pa r t i cu la t o torn, other than nobin qa n m, with half-livo<, q ro a t. c r than eight da yn:

D = (CF) P W O +W O T I -S IS V IVI where: The Location in the critical nathway dairy 2103m n9W from vents. D = dono rate to the thyroid, in mrom/yr. T CF = 1.09; the correction factor accountin1 for t h .' use of Lodine -131 in li.eu of all radionucliden reloased in qaceoun ettlu~nts. 11 2 P = 0.62 x 10 m mrrm/yr per pei/nec; tho anne I parameter for I-131 in food and grouni pa t hwa ys. The done fac'or in banod on tho critical individual organ, thytoiI, a n 1 mont restrictive age qroup, infan'. le o nito Speci fic Data, l'ot" 2. - 10 -2 W = 4.95 x 10 matern  ; tho hi,jh- t calculated S onnual averago dicpersion paramotor f or ntack releason to the cri ti ca l nathva y dai ry. O = the release rate of io lino -131 in nanomus Is effluonto from tho etack do'"* mi n'<1 by the cfi1u"nt ca mpl ing and analysin program (Technical Specification Table 't . 8. 2) in pri/non. -9 -2 W = 1.14 < 10 motorn  ; th" hith at calcula+ed v annual average dinpornion pa ramo te r f o r vr nt relea ro n to the c r i t- i c i l pat hway dairy. Q = the releano rate of iodino - 131 in qanenun IV effluento from all vont rolearon, determinol by the effluent campling and analysin proqram (Technical Speci fication Tabln 4. n. 2) in pri/noc. 11 - IV.B. Surveillance !!"quirement fl . P . C. ? The air done in unrentricted a rca n duo +o notlo ganen releaned in gannoun etiluen*n nha11 io determined by tho expronniorn briow. The air dose chall be deterninod by ei+ hor of two nothods. Method (a), tho Gronn Peleano M e t ho'1, annumon that all noble qanec roleaned aro tho mont limiting nuclile - Vr-88 for gamma radiation and Kr-87 for beta radiation. Methol (b) , the Iro+opic l\na lysin tie tho l, utilizes the resultn of noble gan analyses required by npecificat ion t4 . 8 . r . 1. o . For normal operations, it in expocted that- f*ethod (a) will be uned. Ilowe ve r , if noble gan reloanen are clone to the limito an calculatod by *tethol - (a) , Method (b) can be used to allow more operatina flexibility by using data tha t- roro accura tel y re flect actua l releason.

1. for gamma radiation:

a) Gronn Release Mothod -8 - D, = 3.17 x 10 M (x/0) 0 + av u y y , whore: The location in the site boun1iry 1997 n S g r' fron tho vonts. This location renuler .i n &ho hiqhont calculated gamma air done frem noble gar roleanon. Dr = qanna ai r doso, i n n ra 1. -8 3.17 x 10 = yearn per necond. il 3 M = 1.52 x 10 mrad /yr rer pri/n ; tho air done factor duo t o ca n tra ominnions f or Kr-88. __ -7 3 (X/Q) = 'i 33 x 10 noc/m ; tho h iq ho n t V calculated annual avoraqo relativo concentration from vont roleaner for any area at or beyond the un ren t rict ed a rea boundary. ~ - U = the grons reloano of noblo gar v radionuclides in qaneoun of f. luente from all vents, determinod by gross ac'i.vity vont monitors, in p Ci. Feleases shall be cumulative over the ca l en'la r quartor or year an appropriate. -4 B = 3.15 x 10 mrad /your per pCi/sec; the constant for Kr-88 accounting for tho gamma radiation from the elevated finite plume. The constant was developed using the MAPE program with plitnt specific inputs for PPA P9 ~ Q = the gross releano of nobla Jas S radionuclides in gannoun releasen from the stack determined by qross activity ntack monitorn in p Ci. Releasos nhall bo cumulative over the calendar quarter or yoa r an appropriate. b) Isotopic Analysis tiothod -8 - - Dr = 3.17 x 10 [i L '1 i (X/0) V q iv +n i O i s-where: The location in the ni+ o boun h ry, 1007m SSE from tho vents. This location resultr in the hiqhort calculated gamma air done f r om not to gan reloan <n. Dy = gamma air done, in rnrad. -8 3.17 x 10 = yearn per second. M = The air dose factor duo to gamma omincions f or each

i. idont ified noH o gas ra 1ionucli le. Valuen are listed on Table IV.A, in irr rl/ yr por aci/n3

-7 (X/Q) = 5.,33 x 10 sec/m3; rho hiqho't calculaeo1 annual V avorage relative concontra tion from vont relcaron fo any area at or beyonr1 *ho unrnntricto1 area boundary ~ Q = The release of nolle qan ra lionucli leo, i, in ganeour iV effluentn from all vents an dotornined I;y isotopic analysis, in Ci. Rolearan shall be cumulativo over the calonr'ar quarter or yoa r, a n a ppropria te. ~ . B = The conntant for nach 1lentified noble gas i radionuclide accountinct for the gamma ra 'iat ion f ror the elevated finite pl u mo. Tho con s ta n t s wrro d e ve lo pod using the MM" proiram wi*h plant np<cifir inputs for PBAPS. Valuon are lirted on Table IV.A, in mrad /yr per nci/ soc. U = The release of noblo gas ra lionuclidos, i, in gaseour is effluonto from the stack detormined by isotopic analysis, in pCi. Foleasos shall be cumulative over the calendar quart <r or year, as appropriate.

2. for beta ra dia tion:

a) Gross Release Method -8 - Dp = 3.17 X 10 M (X/0) 0 * (X/0) 0 v v n n where: The location is the site boundary 1997 n SSE from &hr vents. This location results in tho hiche t calculatod gamna air dose from noble gan reloano . Pp = beta air done, in nrad. -8 3.17 x 10 = years por seconi. 4 3 11 = 1.03 x 10 mra d/ v r po r p ei/ n ; the air done factor due to be*a omi ssions f or Kr-87. -7  ? (X/Q) = 5.33 x 10 sec/m : tho hithest calculated v annual average relative cone:entra tion t rom rent re leas on for any area at or leyond the unrestrictr>d ar"a bou n la ry. 6 = the gross relearr- or noble gas v rarlionucliden in nam'ous effluen*n from a ll vents deterini.iv' 1 1 y gros s act ivi ty vont monitors, in uci. "oloasen nhall be cumulative over t h- ca lon<'a r qua rto r or yoar as appropriato. ~ . -8 1 (X/Q) = 9.97 x 10 sec/m ; the hiqhost calcula te'l s annual average rela

• ivo concontration from the stack relea son f or any a r"a a* or Imyond tho unrestricted area bourrlary.

U = the gross releaso of noble gan s radionuclides in ga secun relea sos f ron the stack determined I;y 'Tross activity stack monitors, in o.Ci. Peleanos shall be cumulative over tho calendar quarter or year as a pprop ria te. b) Isotopic Analysis Method -8 - D p = 3.17 x 10 $N 1 - 1 (X/0) V o 1V + (X / C) n V , in where: The location is the sito bouniary 1097 n GSE from tho vonts. This location rosults in the hiqhest calculated l' eta air doso f rom noble gas releasen. D(3 = Bota air done, in mra d. -8 3.17 x 10 = Yoars per soconi. N = The air lone factor due to beta i emission- for each identi fied noble gar radionucli.le. Va l uer aro listed on 'rable I V . *, , in mrad /yr per pCi./m3 _7 (X/0) = 5.33 x 10 nec/m3; the hinhost v calculato1 annual averaqo relativo concent ra tion f rom vont relea ses for any area at or beyond tho unrcstricted aroa bouniary. Q = The relolre of noblo qan radionuclides, iv i, in aasoour offluonts from all vents as detc rmined by isotopic analysir, in aci. P"leaso1 nhall bo cumulative ovet +he calendar quartor or voa r, an appropriaen. ~ * -R (X/0) = 9. 9 7 x 10 a cc/m 2 ; t he highest n calculato1 annual averaqo rela t iv o conce nt ra t ion from tho stack releases for any area at or beyonel tho unrentt ict od a rea boundary. U = The r el oa n o of noble gas radionuclide, is i, in qannous ef f luonts from the stack as dotorminod by isotopic a na lysi s, in pCi. Releacon shall be cumulative over the calendar quarter or year, as a ppro pria t e. IV.C. Surveillance Requirement 11. 8. C. 3 The dose to an individual from ra d i ciod ino s , radioactive materials in pa rticulate form and radionuclides other than noblo gasen with half-lives areater than eight dayn in gasoons effluonts released to unrestricted aroas shall be dotormined by the following expression: -8 - - n = 3.17 x 10 (CF) (0. 5) P Wg & WO '- S TG v Im where: Location is the critical pa thway dai ry 2103 m nqN from vonts D = critical organ dose, thyroid, f ron a ll pathways, in nrem. -8 3.17 x 10 = years per second. CF = 1.09; the correction factor a c c o u n'- i n a for the une of Iodine - 131 in lieu et all radionucliden released in gaseous efflurnts.

0. 5 =

Fraction of iodine roloane" which aro nonelomontal. 11 2 R = 2.67 x 10 m (mrem /yr) Fr ci/noc; tho doco factor for Iodine - 131. Th" lone factor in based on the critical individua1 orqan, thyroi1, and most restrictive age group, infant. Sco sit o Spocific Data, Note 3. -10 -2 W = ti. 9 5 x 10 meters  ; (D/0) for the fooi pathway s for stack releasos. U = the release of Iodino -131 from 'ho stack determined by Is the effluont sampling a nd a nalynis proaram (Techni cal Specification Table 4. 8. 2) , in pei. Peloasen shall be cumulative over the calenda r quartor or yoar as a ppropria te . -9 -2 W = 1.1 f4 x 10 meters  ; (D/Q) for the food psthway for v stack releases. U = the releaso of Iodine - 131 determin~1 by the ef fluent IV sampling and analysis program (Technical 7pecification Table 4. 8. 2) , in pCi. Feleases shall be cumula tive over the calendar quarter or yea r a s appropriate. IV.D. Surveillance Pequirement 4.8.C.ta i The projected doses from releasen of gaseous effluents to unrestricted aroas shall be calculated in accordance with the following soctions of thin manual:

a. gamma air dose - IV.B.1

b. beta air dose - IV.B.2

c. organ dose - IV.C V.A. Survoi11ance Raquirement 4.8.D If tho doses as calculated by the equation, in this manual do not exceed the limits given i. n Technical Specifications 3.8.B.2, 3.8.C.2, or 3.8.c.3 by moro than two times, the conditions of Technical Specification

3. 8. D havo been met.

If the doses aa calculated by the oquations in this manual exceed the limits given in Technical S peci fica tions 3. 8.13. 2, 3.8.C.2, or 3.8.C.3 by more than two times, the. maximum dose or dose commi t ma nt to a real individual shall be determined utilizi.ng the methodology provided in Regulatory Guide 1.109, "calcu lati.on of Annual Doses to Man from Routine Feleasos of Peactor Effluents for the Purpose of Evaluating compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977. Any deviations f rom the methodology provided in Rogula tory Guide 1.109 shall be documented in tho Special Report to be prepared in accordance wi*h Technica1 Specification 3. 8. D. VI.A. Uniaue Reporting Rejuiremont 6.9.3.q.R ),Done glculations for the Radiation Dose Assassment Ponort The assesamont of ra'liation dosen for the radiation dono assessment report shall be performed utilizing tho methodology provide <l in Fegulatory Gui.de 1.109, " Calculation of Annual Doces to t1a n f ro:n Routine Releases of Roactor Ef fluents for tho Purpose of Evaluating Complianco with 10 CFP Part 50, Appendix I", Revision 1, October 1977. Any deviations from tho methodology provided in Regulatory Gui.de 1.109 chall be documented in the radiation dose assessment re po r t. The quarterly average meteorological con <litions f or each quarter covered by the report shal] be usml as input to thc= dose model. VII.A. Surveillance Req ui re me nt 4. 8. E The radiological environmental monit oring samples shall be collected pursuant to Table VII.A.1 from tho locations shown on Figures VII.A.1 an1 VII.A.2 an1 shall be analyzed pursuant to the requiroments o f 'la bles VII.A.1 and VII.A.2. TABLE VII.A.1 P ADIOLOGICAL EtiVIPONMENTAL Mot!ITORI TI; PhoqHA" Number o f samples and Samplino and Typn and Exposure Pathway Sample Collection Fro']uency of and/or Sample Locations ** Frequoney*** _ Analysis

1. AI R BOR N E Five Continuous Particulato samplor.

PARTICULATES locations operation of Analyze for qross sampler with "ota radioactivity 1A, 1B, 2, samplo af&er 24 hou rs 3A, 12D collection aF f o l lowi ng fi lt e r least weekly. chango. Perform gammi isotopic analysis on each na rrplo whnn qross beta activity is groater than 10 tiros tho trean of control "amples. Po rt arm qamma isotopic analysis on composito (by locat ion) nample a' 1m st quarterly. ~ .

2. DIRECT E i.qht At loart Gamma dose at least RADIATIOf1 locations monthly. mon *hly.

1A, 1D, IC, or or 1D, IE, 2, 3A, 12B At lea n t Samma done at least quartarly. Iuarterly.

3. LIATERBORIIE

a. Surface Two Compositet Gamma i. sot opic locations sample analysis of nach collected composite cample, ILL, IMM monthly. Tritium analysis of composite sample at loast qutrterly.

b. Drinking One Compositet Gross beta and gamma location sample isotopic analysis of 4L collected each composite monthly. nample. Tritium analysis of composite namplo at leant quartorly.

c. Sedimont one At least qamma isotopic from location semi-annually. analysin or 13 4, 137Cs shorelino 4J by chemica1 s maration of each nample.

4. IIJGESTIOt1

a. Milk Four A t- least la m"1a isotopic locations biweekly when a na lysi s or 13 't ,

animals aro on 137Cs by chomi. cal Three pasture; at n e pa ra t ion indicator least monthly quarterly. 1-131 one contro l at other analysi s 01 each times. camplo. ~ * ~ .

b. Fish Two One sample a t Ga mma i so topic locations least semi- analysis.

annually of ti , 6 each of tho followinq species if available:

1. khite Crappie

2. Channel Catfish

• Composite samples shall be collected l'y collectinti an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• • Fixed sample loca tions are shown on Figures VII.A.1 and VII.A.2.

Stations 12 B and 12 D are in Philadelphia.

• • • Sample collection f requencies are def ined as follows:

Weekly: 7 calendar days 1 3 days Biweekly: 1li calenlar days 1 6 < lays Monthly: a calendi c month 1 15 days Quarterly: a three month calenda r period bnginniti<7 January 1, April 1, July 1, or October 1 + IIS davr. S emi- an nua lly : a six month calendar period beginning Janu1ry 1 or July 1 1 90 days. TABLE VII.A.2 M A X I'40'4 VALilES FOlt MItJIMtJT4 D ETECTA BLE LEVELn OF ArTIVI TY_jilDL) a Airborne r i.r h sediment Mater Particulate (pCi / kg , Milk ( PC i / kri , Analysis jeci/lL_ _Jpci/m3) wer _ Joci/ Q dryL gross beta 1. 6 .000 31I 1600 S ti Mn 12 100 59 Fe 23 200 58,60 co 10 100 65 Zn 23 200 95 Zr-tib 12 1311 0.8 134, 137 Cs 12,1 f4 0.008 100 12 120 l il 0 Ba-La 12 12 TABLE NOTATION a - Analyses shall be performed in such a manner that the stated MDLS will be achieved under routine conditions. Occasionally, background fluctuations, unavoi la bly sm ll sample sizos, the precence of intorforino nuctiles or other uncontrollablo circumstances c:a k " 'hona 'iDI r unachievabla. MDb is the minimum <1et ectable level (a n pci ne r unit mass or volume) ba sed on two standar<1 clavi at ions of t h <: net counting rate VIII. guarterly Meteorological Data ~ - The radiological dooo astessment repore -Sall include -join t frequoney distributions of wind speed and wind direction by atmospheric stability catogory .uul Brookhaven Turbulence Classification for each quarterly effluent release period covered by the repor*. 'I b e n distributions shall ha presented for tha !1icrowavn Towar 75' and 320' elevation wind sensors in a f o rma t simi la r to that presented in Appendix B to Poquiatory Guide 1.21, "Measurinq, Eva lua ti ng , and Fe[urting I?adioactivity in Solid Wastes and Peleases of Radioactive Materials in Liquid and Gaseous 7fLluonts From LightWater-Cooled t!uclear Power Plants", Revision 1, June 197f4 IX BASES Gite Specific Data elote 1. Lirplid dose factors, A , for section III.T wore dovoloped using ir the following site specific dat a. The mximum exposed individual is a child. A 7 = (U /D F U x BF ) K x DF x l' C i w w F i 0 i D =

5. 4 ; average annual dilut ion at ronowingo intako w

RC =

1. 16; reconcentration from PBAPS li scharge back throuqh PBAPS intake Thes e dat a were derived f rom da+ a published in Peach Bottom Atomic Power Station Un i t s ? and 3 (Docket tio s. 50-277 and 50278) g l i.o a c t- i v o Fffluont Dosa Assessment t Enclosure A t copt embor 30, 1976.

All other data were used as given in F. . 1.109, 11evisio n 1, October 1977. tioto 2. To develop constant P for soction IV.A.2, tbe following sito I specific datum was used: 0 = 40 Kg/ day; cow's consumption ra to F 0 was publishad in Poach Do* t om ;tomi e Power 3ta tion Units 2 F and 3 (Docket !Ios. 50-277 and 50-278) Padioactive Effluent Dose Ass essment, Enc]onure A ,_ s"ptembor 30, 1976. All othor dat a were used as given in R.G. 1.109, Revision 1, Octobor 1977. ~ - tiote 3. To dovelop constant R for section IV.C, rho followimi site speci.fic data were used: Q = 40 Kg/ day; cow's consumptien ra t e P f = 0.6; the fraction of tho y ea r the cow is on pasture p (average of all f a rms) = f 0.484; the fraction of cow. feed that is stored feed while a the cow is on pasture (a ve ra g o of all f a rms) . These data were derived f rom data published in Poach Pottom Atomic Power Stati on Units ? and 3 (Docket tios. 50-277 and 50-278) Ra licacFi ve Effluent Doso Assessment, Enclosu re A,, Soptembor 30, 1976. All other data were used a s oi.ven in R.G. 1.109, Revision 1, October 1977. survoillance Req ui re me nt 4.8.B.2 Liqu i.d Pat hvay Dono Calculation _s_ The eIuations tor calculating the donos duo 'o _ th-actual release ratos of radioactive ma+ oriale in liquid effluents were developed f rom the methodology provided in Pegulatory Guido 1.109, " Calculation of Annual Dosos to Man from Routine Releases of Ro ac t-o r Et t luon t? for the Purpose of Evaluating Compliance wi th 10 CFR Pa rt 50, Appond ix I", Revirion 1, October 1977 an1 !JUPEG-0133 " Preparation of Radiological Effluont Technical Specifications for tiuclear Power Plants", Oc"ober 1970. Surovillance Reguirement 4.8.C.1h Doso IJoble Gases he e:juations for calculating the dosos due to tho actual release rates of radioact-ive nol . l o gat"s in qaceous effluents w"re developed fron the mahodology provided in Regulatory Guide 1.109, "Caleula+ ion of Annual Doses to Man from Poutine Pal ea s on of peact or Effluents for the Purpose of Fvaluating Complianco with 10 CFR Part 50, Appendix I", Revision 1, October 1977, t10 REG-01J3 " Preparation of Padiologicil Effluont Technical specifications for tJuclear Power Pla n ts", August 1978, and the atmospheric disp"rsion nodel presented in Inf orma tion Requested in rnclosuro ? to lottor from George Lear to E. G. Daii r datJ T 5 tfu F v & 19h September 30, 1976. The npocified equations provide for determining the air docan in un ron t rict ml areas based upon tho his torical average armouphoric conditions. Dono t Radici odinen , Radioact ive f u ter i a l in Pa r t i cu la t e Form t and Radionuclides Othor Than Moble Ganen The equations for calculating the dosan due to tho actual release ra tos of radioiodinen, rmli oa ct- ivo material in particulate form, and radionuclidos othor than noble gases with half-lives greater than n dayn were developed using the methodology provide 1 in Regulatory Guide 1.109, " Calculation of Annual Donos to Man from Routine Peleases of Peactor Ef fluentn for tho Purpose of Evaluating Compliance wit h 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133, "Prepa ration of Radiological Ef f luen t Tochnical specificationn for Nuclear Power Pla ntn", October 1978, and the atmospheric dispersion molel presented in Information Requested in Enclosure 2 to Lotter from George Lea r to E. G. Bauer dated Fobruary 17 c 19 7 f; , Septomber 30, 1976. These equations provi.de for determining the actual doses based upon the his torica l average atmospheric conditions. Surveillance Requiromont fl . 8. E fjonitori.ng Program The minimum detectable levels specified in Tabla '/ I I . A . 2 aro based on dose impac t a nd sta te-o f-t he-a rt methodology for routine environmontal moasurements 1y commercial laboratories. These va luer when multipliol 1ya factor of 1.28 result in corrrroonling lowor limi ts of detection which are the smallost concontration of radioactive material in a sample that will bo detecte1 with 907. probability, with only 107 probabilit y of falsely concluding i ts presence. 'th o corrns ron ling lower limit of detection of I-131 in milk in approximately equal to the concentrati.ons resultinu in onequarter of the 10 CFR 50 Appendix I design doro ob jective per reactor of 15 mrem /yoar to *ho critical organ and individual from atronpheric reloason. Tho MDLs are based on twa standard deviat i.one o f t- h e n o t count rate in order to provido continuity of tho data f or comparison with previous data. - 2 t1 - PB APS A tt. E 43 t* a C3 t . . E2 == {e 801 La b tas 7 saJ e

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,; q, ,x( 7, t '~, ,4 f-I - .1 ~,N - , x t ( \ .e~,,.. e r ,,,,'c y / '\' 6 'x\ 5 MILE f / .c - ' .. S. / ,/ .\ s / t/ /,' , 'g f' /f\ J , l- / l' c ~ ~ j N_' j( 1 \ .' / 7 ,A x . .._f,. ', [ , l . ~.. . . t :' . " * . ./' i_ e ' J .L .2~/ f ,/' fKV ' ;A L,/\. b ~ =;- %.% ,/ / \ yy , \ 1 w/d / - ., s 7 { }  ?- .- /, -/ .1 H.- u.- / . " w -,\ . ,/ s - g, \ g , .[. CIO MIL F.' , T ' ~ l(i}[, , / { - 5- ',, 'k. ... t N/ / 1 y' .}s NjN /N .te ) \ / . '> ,, a 3A DELTA, PA- SUBSTATION 4L CONOWINGO DW 4 CON 0WINGO POND 41 CC'10AINGO POND 6 HOLTn000 POND NE AR E'JPMINS FUN RADIOLCGICAL ENVIRON", ENTAL MCNITORING SAMPLE LOCATIONS FICt'Rl' VII.A.2 ,w, _. .; , e .m 4 . . - AT TACilMEtrI I Information in Support of the OMaite Dose Calculation Ma n ualjODCri) Several assumptions have been trade in or:lo r to simpli f y the dose calculations and make them more manageable trom a p ra ctica l point of view. Ibese assumptions with justification a re outlined below:

1. The surveillance requirement for liqui.d releases in tle model Technical Speci fications requires that tho release limit be based on the summa tion of the critical pa thwa y dose trom each nuclide released. For the purpose of showing corrpliance with the Limitino Condition for Operation (LCO), the dose tram liq u id releases will be determined by summing the dose d m to fish consumption from three nuclide:, - P-32, Cs- 13 4, and Cs-137. These three nuclides account fot over 997 of the total dose both to the total bo;1y and the critical organ (hone) . The value calculated, therefore, is increased by one per cent to accoun t for the dose from all other nucliden.

2. In order to assure that 10 CF P. 20 J imi ts a re not exceeded, dose rates from noble gas r e lea sed as determined by the gross monitors will Le ca lcula t. ::(i by one o f two methods. The first i. s a ve r y con serva tive approach and assumes all noble gases t o be Rt-88 for total body dose anl Kr-87 for skin done. Er-88 was chosen as the most conservative n ucli< h v. hen total body dose factor and decay f rom point of release are taken into account. Kr- 8 9 and Kr- 90 both ha ve higher oamma

Page 2 al.r doce f actors, but their half lives are much shutter than that o f K r- 8 8 (3.16 tr.inute s a n.1 32.3 c<conds versus 2. 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) . Therefore, Fr- 8 8 results in t.l.o most limiting dose at the receptor point in the dato calculati.on. This trethod will be used' when tha calculated dose rates are not near t he limitinq conditions. The second method is a more accurate nat burdensome approach. It utilizes the mixture at radionuclides deterrrined by isotopic analysis of the gaseous ef fluents and the individual doce facter for each nuclide. This method will be used if ef fluent releases are such that the calculated done rat"s by the conservative first trethod approach the Lim i. t i n o Condition f or Operation.

3. The model Technical Specification 1/:0 Lor all radionuclides and radioactive mat erials in particulate form and radionuclides other tinn noble- gases re q uires that the instantaneous dose rate Le lcos th in the equivalent of 1500 trrem per ye nr. For the turpoce of calculating this instantaneous dos" r a te, thyroid dos" from iodine- 131 through the milk pithway wili be used.

The thyroid dose from iodine-131 accounts tot 92 per cent of the total thyroid dose, based on the dose assessment analysis for Appendix 1. since the opera ting history to date indicat es that io line- 131 releases have had tl:e majer dose impact, this apr to ich is appropriate. T he value calcula t mi is increased by P iqe 4 nine per cent to account for the thyroid done from all other nuclides.

4. Compliance with 10 CFR 50 noble gas dose (i.e. Er 88 4 Kr 87) limits will he determined using the came conservative assumptions or actual isotopic brcakdown described above for 10 CFR 2 0 doses. 'i h e c alcula tiori equa tions include long term releases only (qreater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year). Any short term releases ha ve ieen shown to he random occurrences, therefort, ion :1 tern meteorology is applicable.

5. Compliance with the 10 CFR 50 limits for radiciodinou, radioactive materials in particulat o form and radionuclides other than noble ga ses with hal C lives greater than eight days is to be determincd Ly calculating the thyroid dose f rom io li ne- 131 releason.

Since the iodine- 131 dose accounts for 92 per cent of the total dose to the thyroid, the value calculated is increased by 9 per cent to account tor the doce t to'n ~ a ll other nuclides. Certain analyses listed in the radiological environmontal monitoring section of the model Technical Specit tea tions are not a ppropria te to Feach Dottom Atomic Power Stat ion for the following reasons:

a. AIRPolitJE RADIGICDIf1E - Iodine is much more e f f ectively monitored in milk than in air due to tho concentrating effects that occur in the milk pathway. At Peach

f Pa g e 4 Bottom, milk is monitored very near the site at the critical dairy f a rm location. Ex[ erience during the first four years of operation of Unitr 2 and 3 involving I- 131 concentration in milh has indicated that iodine concentrations would not be detectable in air. The maximum concentration of I-131 measured in milk and attributed to Peach Botton operation v.o uld eq ua te to only 20 % of the lower limit of detection tor I-131 in air required by the mo3el Technical S peci f ica tions. It is highly unlikely that 1- 131 trom Peach Bottom would ever he detectable in air.

b. GROUT 1D WATER - The Franch Technical Position (' larch 1978) on radiological environmenta l moni.toring states that ground water must be monitor ed only it likoly to be affected. There are nc ground wa te r sources that are likely to be affected by Peach Fot. tom because.the ground water flow at the site is towa rd Conchinco Pond and no wells exist between the plant and the ;ond.

c. DRI t1KI!1G WATER, I- 131 - The Branch '!echnica l Position recommends analysis f or I-131 in drinking water only it the calculated dose is greater than 1 nrem/yr. ILe ma ximum calculated dose to an indiv id ua l from I-131 in drinking water is only 0. 28 mre.n/yr.

d. MILK, GAMMA SPECTPCMETFY - Experience oftained during four years of operation of Peach nottom indicates that nuclides other than I-131 from Peach bottom Icleases are not detectable in milk. T he done assessment

Page 9 ana lysis for Appendix 1 indicates that ces ium- 137 and 134 might have a minor dose impa c t a s a re s ul t of long-term buildup in soil with subsequent t rans fe r to grass and milk. Quarterly garrma spectrome try or cesium isotopic analyses on milk are adequate to detect and evaluate the occurrence of any such ef fects.

e. FOOD PRODUCTS 1 GAMMA SPECTROMETRY - flo crops grown in the vicinity of Peach Bottom a re irrigated with water in which liquid plant wastes have Leen discharged.

f. GREET 1 LEAFY VEGETATIOt1, 1-131 - The milk pathway, which results in a greater maximum dose to man t_han the vegetation pathway, is Ironitored a t loca tions nea r the sit'e and is a better indicator than veqctation samplec.

The Branch Technical Position requi.ros this anal ysis only if milk sarrpling is not performed. g. MITTIMUM DETECTABLE LEVEL _(MD Q 1ABLL - ihe values for lower limits o f detection as presented in the redel Technical Speci. fica ti.ons have been r e <iuced by a factor of 1.28 to change the basis of ca lcula tion trom the HASL-300 me thodology (lower limit o[ d e t ec t io n- LI.D) to two standard deviations of the not count rate (*1DL) . Si.nce the change in values correspond s to the difference in methodologies, there are no effective ditterences in the limits presented. The reporting of MDL's as proposed will permit comta ricons of future da ta with t. hose collected during t he pre-operational e, Page (, innd initial operation phases of the Peach Bottom Station. .