ML18022A568

Semiannual Radioactive Effluent Release Rept,Jan-June 1987. W/870831 Ltr

ML18022A568
Person / Time
Site:	Harris
Issue date:	06/30/1987
From:	MCDUFFIE J W, POLAND A O, WATSON R A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-579 NUDOCS 8709030467
Download: ML18022A568 (149)

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{{#Wiki_filter:g ACCESSION NBR'AC IL: 50-400~AUTH.NAME POLAND'.Q./AC DUFF I E i J.W.WATSONi R.A.REC IP.NAME REGULATOf'NFORMATION DISTRIBUTION TEM (R IDS)8709'030467 DQC.DATE'7/06/30 NOTARIZED: NO'hearon Hart is Nuclear Power Planti Unit ii Carolina AUTHOR AFFILIATION Caro 1 ina P oeer Sc Li g h t Co.Carolina Power Sc Light Co.Carolina Poeer 5 Light Co.RECIPIENT AFFILIATION DOCKET 0 05000400~lQ/Qo~~e~L O'4'f'UBJECT: "Semiannual Radioactive Effluent Release Rept'an-June 19'87" W/870831 ltr.DISTRIBUTION CODE: IE48D COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.3&a(a)(2)Semiannual Effluent Release Reports NOTES: Application for permit reneeal filed.05000400.RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY'S B INTERNAL: AEOD/DOA ARM TECH ADV N EP/RPB RE('I 01/EPRPB EXTERNAL: BNL TICHLERz J NRC PDR COPIES LTTR ENCL 1 0 1 1 1 1 4 4 1 1 1 1 1 REC IP I ENT ID CODE/NAME PD2-1 PD AEOD/DSP/TP*B NRR/DEST/PSB NRR/PMAS/ILRB RQN2 FILE 02 LPDR COPIES LTTR ENCL 5 5 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REGUIRED: LTTR 22 ENCL 21 C4 I l 4'L Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.0~Box 165 New Hill, North Carolina 27562 AUG 5 3 l987 File Number'SHF/10-13510C Letter Number.HO-870490 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 NRC-579 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen.'n accordance with Technical Specification 6.9.1.4, the Seminannual Radioactive Effluent Release Report is attached for the Shearon Harris Nuclear Power Plant.This report covers the period from initial criticality (January 3, 1987)through June 30, 1987.Very truly yours, z~R.A.Watson Vice President Harris Nuclear Project ONH:skm Attachment cc'Messrs. Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/HO-8704900/1/Osl ~8+8'jt 0 I (Carolina Power h Light Shearon Harris Nuclear Power Plant License No.NPF.-063 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 1987 to JUNE 30, 1987 Prepared by: Project Specialist -Radiation Control Reviewed by: Manager-E ronme al h Radiation Control Approved by: Plant General Manager8709030467 870b30, PDR ADOCK 05000400 R PDR~c/8 (/ II 1>I<K~%It I yNg II q P K t M i I c I'g 0 Table of Contents Introduction Discussion Page No.i Appendix l.2.34 4.5.1.Supplemental Information Regulatory Limits MPC's and dose rates which determine maximum instantaneous rates.Methods for Approximations of Total Radioactivity Batch Releases Unmonitored Releases 1/1 1/2 1/2 1/3 1/3 Appendix 2.Effluent and Waste Disposal Report 1.Lower Limits of Detectability (LLD's)2.Effluents Released 3.Solid Waste Disposal 2/1 2/3 2/10 Appendix 3.Changes to Process Control Program 3/1 Appendix 4.Changes to Offsite Dose Calculation Manual Appendix 5.Changes to Environmental Monitoring Program l.Environmental Monitoring Program 5/1 2.Land Use Census 5/2 Appendix 6.Additional Technical Specification Responsibilities l.Inoperability of Liquid Effluent Monitors 2.Inoperability of Gaseous Effluent Monitors 3.Unprotected Outdoor Tanks Exceeding Limits 4.Gas Storage Tanks Exceeding Limits 6/1 6/3 6/5 6/6 Appendix 7.Major Modifications to Radwaste System 7/1 ~h4>h)f'4 f>'+4)'>y, f J F;Jfl",pi 4 f'f>].JF'.,J ff)<<I,,I J><<>f'"f J<</>>J ir!ft J'., TJ:-.))li)f ffff f)ah-',ilf>fii >'.',C'i" I ,'.f f')JJ'."J)IT V 4~I~y)'f yh),'f>yf>TF r)I y J f>>I J'h)J""')FJ TT>y>"")'h~)>YJ f>>4~JTJ,J'J" V J~f haft J)'J hf)."),))if t, Ii)F.>C.')-),.f r,f>>if..>)>Jr>gal'J '.f>I)>4 ji J 4 (>>I C tfg J)y)J J, f'>fll>g[Vf 0))J j)J Tl)I I)J)iT,I I'f y)III I,'fh, f'>l>it Ig I I II, J I 4 JIF',,)')f F" l>T>f f h>f, 4)'f,l J>TJ)f'f>>4)f f>g,>>)',JJ:~ff-"4,'J<<.i', 4 yTy hiffrf)I)+JT>J)/JI>'IJf$'])Tll,)ll) f I IJT),'f'y if".)>)P>'g)F>)j TIJ hhh JJ4'Kf)J'lh I)t>>f(gl, J'))f)4)fc)<<JJ>>'g'))4>f" f gl.~>4>I>"f)(IF fh>4 r"pfh'<<)>>), Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Introduction This Semiannual Radioactive Effluent Release Report is submitted per Technical Specification 6;9.1.4 to the Shearon Harris Nuclear Power Project (SHNPP)Operating License No.NPF-63.This is the first semiannual release report submitted in fulfillment of the plants Radiological Effluent Technical Specification (RETS).This reporting requirement was effective beginning with initial criticality, which occured on January 3,,1987.However, with one exception discussed under Appendix 6 of the following section, the data in this report actually commences on January 1, 1987.This was done for consistency with future reporting periods and because'the RETS were fully implemented as of that date.Discussion ~A pendices 1 and 2: The information on gaseous and liquid effluents is given in accordance with Regulatory Guide 1.21 (Rev.1)Appendix B format.No solid waste was shipped during this period so no data is reported.Activity concentrations (uCi/ml)and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD)table shows a typical sensitivity level for detection of the nuclide.No activity above background was detected in any potential continuous liquid release pathway.Therefore the summations of liquid effluents are based entirely on nuclide analysis and volume determinations of batch releases.These results are based on methodology in the Offsite Dose Calculation Manual (ODCM).Gaseous effluent activities for Quarter 1 were estimated from results of nuclide analyses of monthly stack gas grab samples and stack flow rate estimates based on design fan flow rates.Problems with the stack flow monitor calibrations and the flow integrator system rendered most of the release rate (uCi/sec)data stored on the RM-21 report processor computer invalid.However, the gas grab sampling and flow rate estimating methods are in accordance with Tech Spec alternative actions and provided suitable estimates of effluent release quantities, especially since the plant was primarily in low power testing modes during this quarter.Although the flow monitor problems persisted through most of Quarter 2, improved data collection of hourly average stack monitor readings (in uCi/ml)was started.This data combined with the stack flow estimates provided more continuous accountability of stack effluents. The gross activity concentrations above background were apportioned into specific nuclide amounts using the relative amounts detected in successive gas grab sample analyses.This methodology, although cumbersome when done manually, as it was during the 2nd Quarter, is identical to the method the 1 HH Nh 4>>I u I"'f ,kr I,'I, fr H hh g tiff kh ik 1,"'v 1" H" Ni Nhf h N I'), Ihvt N VH 4<<<<1<<lf'I jj 4, I)N I)jft~I)y I fhv,, I>>4 I I h H 1" II N~))I<<'It h I P')l'I*>>H'I h h N[f Hhll vf,hf I , 4 4 Ih,j*'I Nil I fh, N',f H'fl fh f k h f h Ntfl fp fhph"N 4 I~'h hlfI h,~frt 4 I h I'I H V fhftkp 4~g flhh, jh,),N,),'f fl II<<)K'v<<f'I, ih 14<<">>i'p f HNV 4<<Hf~")I pf I,jI)hfhih f)P 4 H I Hh<<'4 If I'hfr t>>hhv'hf k)i H fh 1 fl N Nfl'1 I 4'I h ,I~I'1!ir,"!I h It il'f ff I I H NPI" 4 I'l II 4'~1 4 r tjh-h hf hff, P~h rfj I,"<<Nf ff'Ilhgl I')II)'if'!jl,hh">>'N" Nlf'I N;VN H" jl if)!," hfr V I lhv Htl Nf)hv"fr)llf l l","" f hl'I H>>vr"f h I', h I I 1 4 I lf 4 hlf Nff I I'I 5 f"f)f<<f lh'4'f<<l')I'hf 4 k")IN lrh r;4 I 1, h V I N~!Ifh'Ikh f hf V f, II I 4" 4 4 ir~j"Vip,'I 4 ghrI th'N'<<)ll 1 lh I'h HN h h hf I<<"'IH I<<1 I'I VC)$>>N f'ltp rlr p'!INN tf H*t)I IIV'Njjf Nfh" I fk)I 1)~t I N,<<lf I!1!t I, 4 I I 1 h h'I'f h<<hh N Nh'h k I H't<<v Nh 1 hl V H HM-21 computer would have used had the stack flow input to the system been valid.It should be noted that the cuties reported are considered to be significantly overestimated because of the use of design fan flow rates which have consistently been found to be higher than actual flows.For the 2nd Quarter, the use of conservatively low background monitor readings for determining the net activity released also contributed to overestimating the curies released.Appendix 3: No changes to the Process Control Program (PCP)were made during this report period.P2 A endix 4: Changes made to the ODCM during this report period are listed.All changes were reviewed and approved by the Plant Nuclear Safety Committee (PNSC).These changes do not reduce the accuracy or reliability of the dose calculations or monitor setpoint determinations. Appendix 5: No changes were made to the Environmental Monitoring Program during this report period.Changes to the Land Use Census are given based on a May 1987 survey.New census data is provided for distances to nearest special locations and for meat animal types nearest to SHNPP.Appendix 6: All effluent monitor inopexabilities greater than 30 days are given along with a brief explanation. Per prior agreement with the NRC, similar inoperable monitor periods prior to initial criticality and after receipt of the Operating License (October 24, 1986)are also given.No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this report period.Appendix 7: The changes made to the radwaste processing system are described. These changes received the required 10CFR50.59 safety review and will not result in any increased exposure to the general public.Revised quantities of radwaste expected to be generated compared to those given in the FSAR are provided. 'j)IN'tj)f j)1'lf')NN up j t it fp((1 u r 1*j(N~lt II PN jl I'I N<<.NN~,'i p"'fu j Nlt I'P'I)1, 1.u..;),f" f t'N p f" Ii)1')f;')1(" f p('<<",i kp Ng f fy')p 1 N'1 P>>*.'N, Nf II I N tl fp lf"puf)NNI t'fl lfpp(.)'NNI, Npl(N)J tl N N Ni N pit)g f j)(uk)f)N'fu j')), Np(P f N jl)j"N Ip u I)'N l I'" f'i I)N)<)fu)r),-">>f i'I>>'f r-"~1 pt N up f upbp (N'l'lit<Ij C I,p(),pt iI f (N'>>Nj, fu")*It I~II~'"r pfr, f)uu N,up f~~NN I (Np pl 1 u lt N, jl N II.)w Pf j'f<<'."ptj)kt

'fui f)f p, p, N Ipl'N, j p i)jt i Pi f.Ffur)t)u)'N(uf)f (uf(f)ji'l 1")I Jf'l, tjti,"$1(ff u).<ftui"~IN IC N gpu)"~i'1

>.(I, u'I)~)P"'(t 1(f P)f)1 fr~Nfl f(N&~N p" lf", l)fu p pl)1 I'f yu p ulfft iufu lp N,, Nu'1 u, ffp'fiI~k~NNN'f 1 P Nil'I'Puf 1'f'l')(fiJir~jf f ,fy'P, j))r , f/N!1/...,'.>>))p((,)ff ff.u'))p N u<t,ff f jcp f f)N I'(>><'flu~,')pj)ulpu lf~ i Semiannual Radioactive Bffluent Release Report January 1, 1987 to June 30, 1987 Appendix 1: Supplemental Information 1.Regulatory Limits A.Fission and activation gases (1)Calendar Quarter a.5 mrad gamma b.10 mrad beta (2)Calendar Year a.l0 mrad gamma b.20 mrad beta B.I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1)Calendar Quarter a.7.5 mrem to any organ (2)Calendar Year a.15 mrem to any organ C.Liquid effluents (1)Calendar Quarter a.1.5 mrem to total body b.5 mrem to any organ (2)Calendar Year a.3 mrem to total body b.10 mrem to any organ tl I 4 4 i I Il"'t'I II lh",II It Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 1: Supplemental Information 2.Maximum permissible concentrations and dose rates which determine maximum instantaneous rates.A.Fission and activation gases (1)500 mrem/year to total body (2)3000 mrem/year to the skin B.I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.1500 mrem/year to any organ C.Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than noble gases.(1)Tritium: MPC=3.0E-3 uCi/ml;and (2)Dissolved and Entrained gases: MPC=2.0E-4 uCi/ml 3.Measurements and Approximations of Total Radioactivity A.Fission and activation gases Measurements by continuous monitors, analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples times total stack flow.B.Iodines Measurements by continuous monitors and analysis by gamma spectroscopy for specific radionuclides collected on charcoal cartridges times total stack flow.C.Particulates Measurements by continuous monitors, analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides collected on filter papers times total stack flow.D.Liquid Effluents Analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides by.individual releases.1/2 l)r<<<<*>;,)7)r>F)v lr rr,erg(<<'; 1 I)'g'>>l<<>[II>>1)l." I*>l ((<<f le)>>![M<"))),)">>>>~((<<I[~.'I[i>)~<<))ll~I tfl))f I)')"),'1)')[f,<<")'>>!P Ff l)((I'r>I I f t)IF'F.M((i"l(l I I',/)>l'[IF II l>Pf[0 r,m(>>)<<'r.l>)I l"i h)F;I.,F[1 f'7,['I l<<>[I[[lilt M'<<)I"(I I,"I,, I(((~<<"..(<F I,)Ill'[tf.[(([>>>>[M/r"'"'" I I<<f~(f I I 1 r'l I[Fr<>)g.','[r l'1',>1<<., h)rr<<'FF.<<r, I>(th>>F<<l,>,=l,>>(>>(((1'<<h>>" 1<<('I".Mf~I'"I IFI(<<,',)<<MM(lg)I(t (h, I"'>>'"" 1" tj.'"""<<tl>>.(I7;,i (I>I'gr>r 1)l I')(W ()k<<r'",'*'1))Žll,(g,'h(gh " i)f."("""I!l)FFMI=t([">>([...)'>ll'>>1'II<<1f<<)~>I)I((M).I')'II)>!,(')ref)1 tf~h , (([lll>>" I 1 1)['>>(hh>>'>>'(I".'."<<<<'"('I(I I"F)f),',' fil<<l("'<<I)n<<(;F1,>1it,~it l<<1 l<<M',I', r~I[>W<<r> Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 1: Supplemental Information 4.Batch Releases A.Liquid (1)Number of batch releases: (2)Total time period for batch releases: (3)Maximum time for a batch release:{4)Average time for a batch release: (5)Minimum time for a batch release: 5.02 E+02 1.56 E+05 min.8.97 E+02 min.3.12 E+02 min.1.00 E+00 min.{6)Average stream flow during periods of release: 2.12 E+03 gpm B.Gaseous{1)Number of batch releases: (2)Total time period for batch releases.'3) Maximum time for a batch release: (4)Average time for a batch release: (5)Minimum time for a batch release: 1.40 E+Ol 3.18 E+03 min 1.25 E+03 min.2.27 E+02 min.2.30 E+Ol min.5.Abnormal Releases A.Liquid No abnormal liquid releases were made in the period.B.Gaseous No abnormal gaseous releases were made in the period. ,$'f I'a na II t a),Ia(;a I,,~a" Va I')a,',V'ff ~fl ,a aa V , aa 11 ff, g)f ffif*V V/j)g)g-av vl V ff)')')~Vi f.<<))')1)a~VV)fal<<)v'f f.,g ()la,,'VV 1'Ij V V<<lla)'>ra iIV" a)"l fi V')pl V iiCI a"'t aa I~g)'ll If, 1llf aaa 1V'f"g~if ff)g)fl*a)a W),~'V~I.JP l qt>a I g aaf sff i)VIXOnaff))~)tll~Iav),fat a)'vv-<<v<))a I,,'l ()I"~)>>~avll lj Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Naste Disposal Report Enclosure 1: LOWBR LIMITS OF DETECTION (LLD)l.LLD's for Gaseous Effluents NUCLIDE H-3 Ar-41 Cr 51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Kr 85 Kr 85m Kr 87 Kr-88 Sr-89 Sr-90 Nb-95 Mo-99 RQ-103 I-131 Xe-131m I-133 Xe-133 Xe-133m Cs-134 I-135 Xe-135 Xe-135m Cs-137 Xe-138 Ba/La-140 Ce-141 Ce-144 Gross Alpha LLD (uCi/cc)8.47 E-08 5.95 E-08 1.54 E-13 2.35 B-14 1.12 E-14 4.94 E-14 1.58 E-14 3.11 E-14 7.90 E-06 1.93 E-08 4.49 E-08 1.09 B-07 1.00 E-15 1.00 E-15 1.62 B-14 3.44 E-13 8.01 E-15 2.76 E-14 7.30 E-07 5.35 E-13 6.08 E-08 1.77 E-07 8.52 B-15 1.22 E-09 1.03 E-08 1.27 E-07 1.52 E-14 2.60 E-07 7.08 E-14 1.54 E-14 6.77 E-14 2.61 B-15 'rt I" jl"P k)~)I II I'N b I'h h'f k 0 Semiannual Radioactive Bffluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Haste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLD)2.LLD's for Liquid Effluents NUCLIDE H-3 Na-24 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Kr-85m Sr-89 Sr 90 Zr 95 Nb-95 Mo-99 Tc-99m Rh-105 Ru-105 I-131 I-133 Xe-133 Xe-135 Cs-134 Ce-141 Ce-144 H-187 Alpha Gross Cs-137 Ba/La-140 LLD(uCi/ml) 4.64 B-06 3.28 E-08 1.59 E-07 2.14 B-08 2.78 B-08 6.71 E-08 3.85 E-08 1.07 E-07 3.08 E-08 5.48 B-09 3.30 E-09 5.05 E-08 4.89 B-08 2.38 E-07 2.73 E-08 1.16 E-07 8.44 E-08 3.07 E-08 3.35 E-08 8.74 B-08 2.57 E-08 2.68 E-08 3.80 B-08 1.17 E-07 3.87 E-08 2.00 E-07 8.91 E-08 5.85 E-08 (8)g ((W ir,,W W-.(>II P P>>flw, ((<<l (,"W, I" th), Jjihhhp II II I~h W hhll),()~r: II Wh')W F h~p~Wh ff)('()(h ,,'gO)l0 w W()If h}ay,,"<hh (">',(i H~~(Wh W(i)If)"JW ()(.(h P r)h (W'.W., t W',";.l (g-,"WI g,"jj ()'t I I)hl(('will Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table lA GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 Est.Total Error A.Fission h Activation Gase 1.Total Release 2.Avg.Release Hate for Period 3.Percent of Tech.Spec.Limit Ci uCi/sec 1.15E+02 6.33E+02 4.50E+Ol 1.49E+Ol 8.05E+Ol 1.10E-Ol 3.00E-Ol B.Iodines 1.Total I-131 2.Avg.Release Rate for Period 3.Percent of Tech.Spec.Limit Ci uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.00E+Ol C.Particulates 1.Particulates with Tl/2>8 days 2.Avg.Release Rate for Period 3.Percent of Tech.Spec.Limit Ci uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.00E+Ol 4.Gross Alpha Radioactivity Ci 2.14E-06 6.30E-07 D.Tritium 1.Total Release 2.Avg.Release Rate for Period 3.Percent of Tech.Spec.Limit Ci uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.00E+Ol2/3 y Iml>>ffm,>>lllf m,,'lf'(f ft.)I mn m>>;,I"'" I".f I Ilf tl5 I~I"f',hf.F,f),)'I 'f().,",, a, (<<'>>(",~a ffm ((h j~f'>>if il,"m Ii ('~l~I f~'if""hf)<<>();>>ff'(>j'Tm)(),0")f>>>, I f<<), ()",(1 h",((f (.'0<)',f.')().!) ('" f (fS)m('l",'I f'ffa I I f gm),>>, Ih(>>I f'f C))il m r)m,If>>11~',~%l II'f h pl h m I'), I)I fh ()f),i': f.', jjh ff f f"f'"f.If'(f ff~I)fl()f')II)i"')~,f>>,ff, I'l'>><f j, ffll't f fl f I'>>I'*<<Ij~II,~i)off.",~.f f)~',',fq f l'h (I(h~()II)()'f I (" f)<)(,')f)f)4fm ff Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1B: GASEOUS BFFLUENTS-ELEVATED RELEASES All releases at Shearon Harris are made as ground releases.2/4 'W W I N h'lh Jl Il,l', W WW II ll W I~If IW h'I ih h I II IIW' Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Bffluent and Waste Disposal Report Bnclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS-GROUND LEVEL RELEASE Nuclides Released Units Continuous Mode Quarter 1 Quarter 2 Batch Mode Quarter 1 Quarter 2 1.Fission Gases H-3 Ar-41 Kr-85 Kr-85m Ci Ci Ci Ci LLD LLD 1.308-03 2.008-03 LLD I LD 2.108+00 2.V08-02 LLD 1.338-03 LLD LLD NO BATCH RELEASES WERE MADB IN QUARTER 2 Kr-87 Kr-88 Xe-131m Ci Ci Ci LLD LLD LLD V.008-03 3.508-02 LLD LLD LLD LLD Xe-133 Xe-133m Xe-135 Xe-135m Ci Ci Ci 2.808+01 4.468+00 LLD LLD 8.508+01 6.288+02 1.608-02 7.778-03 LLD 9.728-06 LLD Xe-138 Ci LLD LLD LLD Total for Period Ci 1.158+02 6.338+02 9.118-03 2.Iodines I-131 I-133 I-135 Total for Period Ci Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD NO BATCH RELEASES WERE MADE IN QUARTER 2 2/5 'I<<II<<,~l I~hl Il<<Ih f'h ,Ilh(<<UM IU,/(U,.UKllf M Ij"<<II,I M.~l" I'(f)Ill;[$<<I)J)gal~<<l"," (,,>8":,~>'(Ml (l)II<<l h<<>>t<<~I<<'I<<('l I<<h Ih I<<il if l'l>>II()I I)<<CP'I jj I<<U f I li, II l I" I"p<<(hajj-<<r,, I IU jj<<v li., rf h Mjl'I,'i, Z(hl'>>I l i'<<g M<<f jj<<I, CU S f ()h,'i l<<U ()()I, fljj)~'I<<<<]j I U I<<<<<<~>><<la~, I U U.M<<M'I~MM')",'(II'()'<<, (I'I U<<MM m~f.I UM (U~I~I<<I Ml f I~!<<IM II" I(g I)i, M*")Ij i')I l;IJ Ug'fl l<<Il M<<III I'I U~I i Ilh..<<Ii h~I 1 Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C (Continued) GASEOUS EFFLUENTS-GROUND LEVEL RELEASE Nuclides Released Units Continuous Mode Quarter 1 Quarter 2 Batch Mode Quarter 1 Quarter 2 3.Particulates Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Ci Ci Ci Ci Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD NO BATCH RELEASES WERE MADE IN QUARTER 2 Mo-99 Ci LLD LLD LLD s 134 Cs-137 LLD LLD LLD LLD B a/La-140 Ce-141 Ce-144 Gross Alpha Ci Ci Ci Ci LLD LLD LLD 2.14 E-06 LLD LLD LLD 6.30 E-07 LLD LLD LLD LLD Total for Period Ci 2.14 E-06 6.30 E-07<LLD 2/6 <>I ,~r~~I'>I l4I ft ,'I.'t lr'7.,l"1 7.f ff~~~f.".I'I...>I"'>'")V y'I fVT'tT>>'I), TqV f'"P Itf't"'j 1'fT,!f1/T tT-I Nfffff)~7" Uf)" TiI 7 i ff'tl II t l l't e,>fl,~t.~I,/'I I TT'f..a 5)"II't.~~I);f8 r~).II I'1,f tt T T7 ff1 Il j"')tt 7.T>>'qf A f7'3"IIgll lt at r~ll I tt', fll I 71,l t fj 1 f1 I II I f I II I Il ltd~"j, I<f 7tt It i,f.f ll'.)C.'t" tl"I tt,li, I/,ff'p~)tt (f,f Tt, I II,',T.f 77 tT~t't Tf$g"I f1 I'I t'I lt (I i'[f~f~'I$t I I'.IITj 7 j;0,,,tlf~ I f II 4's""tt tl i Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 Est.Total Error A.Fission h Activation Products 1.Total Release (not including tritium, gases, alpha)Ci 3.21 E-02 6.38 E-02 3.50 E+Ol 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit uCi/ml 9.45 E-08 1.51 E+00 6.69 E-08 4.58 E-Ol B.Tritium 1.Total Release Ci 2.45 E+00 5.79 E+Ol 3.50 E+Ol 2.Average Diluted Concentration During Period 3 cent of Applicable Limit uCi/ml 7.19 E-06 6.07 E-05 2.40 E-Ol 2.02 E+00 C.Dissolved and Entrained Gases 1.Total Release (not including tritium, gases, alpha)Ci 1.28 E-03 1.35 E-02 3.50 E+Ol 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit uCi/ml 3.76 E-09 1.42 E-08 1.88 E-03 7.10 E-03 D.Gross Alpha Radioactivity 1.Total Release Ci LLD 2.73 E-04 3.50 E+Ol E.Volume of water released (prior to dilution)F.Volume of dilution water sed during period liters liters 1.54 E+07 2.11 E+07 1.00 E+Ol 3.25 E+08 9.33 E+08 1.00 E+Ol 2/7 I>>v<<I)Ii"<<It J rf<<I.<<1 I hdl 4$<<)3)['"'VI)-'Ili If 1'<<ft,>>i,-.1<<i l')f l" It'I t<<g Ii><><<<<")'<<<<~p 1)<<<<<<h)'<<t 1 I II'<<)lf$~f II ,1~/hrh.<<<<)).)1',<<lt<<'<<l->>r 1~If f<<)f'<<I ,I)I II I~1$<<I g gh<<VV)))<<h I)h~ft)h)<<llh)$<<<<,'l t"<<'f V I f (<<<<II Lh<<Il t I>><<<<~'<<1<<1<<'<<,'h 1 dt'h)p j)i')'I~<<"'I'h$~)'.)h'h)11))(t'Jl)>>di f j<<i<<<<,,E)1<<0SII li',.'L'.l lf)"-I<<t f'~t,)<<."I),<<V<<<<, I<<1(t g h'\<<~l 0$I'I Vvi<<I<<1 Ii>>'i,h QP N<<Ill<<<<ihr)<<),'I t<<dt h'I"-4'if)v,)J't V I;'f)f<<III)'<<j<<<<I I'll h)h,<<>>t ti P'.hht)f fr<<)h)r)<<)<<<<<J f fttrftlf, f K'I'm m~)mr m m Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2B (Continued) LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ar-41 Ci LLD LLD Kr-85m Xe-133 Xe-135 Total for Period Ci Ci Ci Ci NO CONTINUOUS RELEASES WERE MADE IN THIS PERIOD LLD 1.75 E-05 1.55 E-04<LLD 1.12 E-03 1.35 E-02 1.28 E-03 1.35 E-02 2/9 W t W W VI IV~ Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 3: Solid Waste Disposal No radioactive waste or irradiated fuel was shipped during this report period.2/10 A l'" g I'+W ,q II e I I rl 4 II Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 3: Changes to Process Control Program (PCP)Technical Specification 6.13 No changes were made to the PCP during this report period. lc tl k I'h h',e)i)1',<, g<>~J V Semiannual Radioactive Effluent Release Report January 1, 1987 to June.30, 1987.Appendix 4:~Changes to the Off-Site Dose Calculation Manual (ODCM)Technical Specification 6.14 The following changes were made to the ODCM during the report period and during earlier plant start-up.Exhibit 1 provides a chronology of ODCM changes.Exhibit 2 provides a cross index of effective page changes.This exhibit identifies change locations in Revision 0.0 vs.Revision 1.0.Exhibit Exhibit 3 provides.a listing of the ODCM changes.I 4 presents the actual'changed 'pages of the ODCM.Change bars identify affected ar'eas,and.a,change,.number is..given-for crossreference'.to those used in this appendix.MEM/ATTACH4/OS2 4/1 EXHIBIT 1'HRONOLOGY OF ODCM CHANGES The ODCM, Version 0.0, was approved by the Plant Nuclear Safety Committee (PNSC)on August 17, 1984.This version was submitted to the NRC on August 31, 1984.On April 4, 1985, the NRC requested four points of information. Three of these points required changes to the ODCM (see Change Items 22, 32, and 45).CPSL responded to the NRC information request on July 1, 1985.Version 0.0 of the manual was approved by the NRC together with the July 1, 1985 response, on May, 30, 1986..Tentative changes to the ODCM were submitted for PNSC revie~on August 8, 1985 and October 16, 1985.These, included Change Items: 1-53.Approval for these changes was requested of the PNSC on September 17, 1986 after.receiving formal approval.of, Version 0.0 from.'the.NRC.,'-'The PNSC=approved=these changes'September 26', 1986.The new version of.the'manual'.was designated'Revision 1.0, Draft 81.The Technical Specifications were issued together with the Low Power Testing License on October 24, 1986.Approval for Change Items 54 and 55 to the ODCM was granted by the PNSC on November 21, 1986.Approval for Change Items 56 through 60 to the ODCM was granted by the PNSC on June 3, 1987.MEM/ATTACH4/OS2 4/2 EXHIBIT 2 CROSS INDEX OF EFFECTIVE PAGE CHANGES REVISION 0.0 VS.REVISION 1.0 CHANGE NUMBER REV IS ION 0.0 PAGE NUMBER REVISION 1.0 PAGE NUMBER 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 1-1 l-l 2-1 2-1 2-1 2-3 2-3 2-3 2-4 2-4 2-4 2-4 2-4 2-4 2-4 2-4 2-5.'2-6 2-7 2-7 2"7 2-7 2-7 2-8 2-10 2-18 2-11 2-12 2-12 2-13 2-18 NEW NEW 3-4 3-4 3-5 3-8 3-8 3-8 3-8 3-9 3" 12 3-15 3-22 3-25 3"27 3-47 3-48 3-49 4-16 4-19 NEW 0-1 2-4 2-5 2-3 2-4 2-4 2-13 2-18 to 4-18 1-1 1-1 2-1 2-1 2-1 t 2-4 2-4 2-5 2-5 2-5 2-5 2-5 2-5 2-6 2-6 2-9 2-10 2-11 2-12 2-12 2-12 2-13 2-14 2-15 2-18 2>>18 2-19 2-19 2-20 2-21 2-26 2-27 2-28 3-4 3-4 3-5 t 3-8 3-8 3-9 t 3-13 3-15 3-18 3-21 3-29 3-32 3-35 3-55 3-56 3-57 4-16 4-19 7-1 D-l 2-'4 2-5 2-4 2-5 2-6 t 2-21 2-26 o 2-3 o 3-6 o 3-13 to 4-18 o 2-9 to 2-14 to 2"15 MEM/ATTACH4/OS2 4/3 , EXHIBIT 3 ODCM CHANGES Page 1-1, Section 1.0, reference to Technical Specification "3.11.3" was deleted as the ODCM does not address Solid Radioactive Wastes.2~Page 1-1,Section 1.0, explicit mention is made for inclusion of"non-routine" releases in cumulative dose accountability to comply with 10CFR50 limits.3~Page 2-1, Section 2.0 now provides explicit discussion on the nature of potential non-routine liquid releases from the plant.4..Page 2-1, Section 2.1.1, the following two sentences have been deleted: "The blowdown flow rate,"B" is determined by the cooling tower basin water level.This water level-,.is adjusted depending, on theconductivity of the basin.water"."The sentences were'deleted due to their-specificity, i.e , other operational parameters also legitimately influence blowdown from the Cooling Tower.5~Page 2-2, Section 2.1.1.la, subsection"a" is new.It is included to comply with footnote 2 of Table 4.11-1, Technical Specification 4.11.1~1~1~6.Page 2-3, Section 2.1.1.lb, Equation 2.1-2, the term"n" has replaced the factor"10", where n is greater than or equal to 2.Using conservatism factors in set point calculations is at the option of the plant (NUREG-0133).Replacing the"hard and fast" factor of 10 with a selectable value provides greater flexibility in radwaste release operations. 7~Page 2-4, Section 2.1.1.lc, at the definition of"B", the phrase"nominally, or estimated available flow rate" has,been added for clarification. 8.Page 2-4,'ection 2.1.l.lc, at the definition of, DFB;the definition has been made consistent with change (6)above.9.Page 2-5, Section 2.1.1.ld, above Equation 2.1-4, the phrase"Determine monitor count rate above background:" has been added for clarification. 10.Page 2-5, Section 2.1.l.d, at the definition of"CR", the dimensions"cps" have been changed to"cpm" to be consistent with Radiation Monitor System (RMS)usage.MEM/ATTACH4/OS2 4/4 Appendix 4: CHANGES (continued) Page 2-5, Section,2.1.l.ld, at, the definition of Em, the dimensions"cps/pCi/ml" have been changed to"cpm/pCi/ml" to be consistent with RMS usage.12.Page 2-5, Section 2.1.1.1d, above Equation 2.1-5, the phrase"Determine monitor set point:" has been added for clarity.13.Page 2-5, Section 2.1.1.1d, Equation 2.1-5 is new and permits calculation of the liquid radiation monitor set point in units of pCi/ml.14.Page 2-6, Section 2.1.1.1d, at the definition of"CR", the dimensions of"cps" are changed to"cpm" to be consistent with RMS usage.15.-Page 2-6, Section 2.1.1.1d, at the definition of"Bkg", the dimensions of"cps" are changed to"cpm" to be , consistent with.RMS,.usage. 16.Page 2-9, Section 2.1.1.1e,,Equation 2.1-6 replaces the term MRR (i.e...Maximum Release Rate)with the term RR (i.e., the anticipated Release Rate)where the RR should not exceed the MRR-see the definition of RR, which is also new.Use of RR permits greater flexibility in radwaste release operations. In addition, the RR term is also included in the denominator. Inclusion of the term is appropriate pursuant to NUREG-0133. 17.Page 2-10, Section 2.1.l.le, at the definition of"B", the phrase"nominally, or, estimated available flow rate" has been added for clarity.18.Page 2-11, Section 2.1.1.2a, at Equation 2.1-8, the term"Vk" (the'k's a subscript), is now included in the denominator. Inclusion of the term is appropriate pursuant.to NUREG-0133. 19.Page 2-12,'Section '2.1.1.2b, a."Note" quotes the 10CFR20 criteria for determination of radioactivity in a sample mixture.20.21.Page 2-12, Section 2.1.2, the word"monthly" has been replaced by the word"weekly" pursuant to the FINAL DRAFT of Technical Specification Table 4.11-1.Page 2-12, Section 2.1.2, the phrase"(see note in Section 2.1.1.2b)" is added for clarification. MEM/ATTACH4/OS2 4/5 Appendix 4: CHANGES (continued) 22.Pages 2-13 and 2-14, Section 2;1.2.1 entitled"Set points for the Normal,.service Water (NSW)Monitors" is new and describes the set point methodologies for these monitors.This methodology was requested by the NRC (reference letter, S.R.Zimmerman to H.R.Denton, July 1, 1985, NLS-85-226). 23.Pages 2-14 and 2-15, Section 2.1.3 entitled"Non-routine Liquid Releases" provides detailed discussion of non-routine liquid effluent release situations at the plant.24.Page 2-15, Section 2.2.1, the phrase"~..and all defined periods of continuous release..." has been added for clarity.25.Page 2-18, a paragraph had been added explaining the conservatism in, including the Lillington Municipal Water Facility as a drinking water pathway for the plant.The paragraph is reproduced below and was in response to a-,technical;-specification:that',did"not become-a part of the final specifications. Because of this, the paragraph was eventually deleted as unnecessary. Inclusion of the drinking water pathway for SHNPP is conservative since the Lillington Municipal Water Facility is located at a point greater than three miles from the plant (see, footnote in Technical Specification 3.11.1.2, Action a).26.Page 2-18, Section 2.2.1, the words"...receptor... ...locale..." have been added for clarity.27.Page 2-19, Section 2.2.1, the sentence beginning with: "This report..." has been corrected grammatically. 28.Page 2-19, Section 2.2.2, Equation 2.2-8 provides the dose projection formula for liquid effluents. 29.Page 2-20, Section 2.2.2, Equations 2.2-9 and 2.2-10 give'the dose projection limits for liquid effluents. 30.Page 2-21, Table 2.1-1,Eductor factors for effluent release tank have been included in the mixing methodology; see Change Item (4)table has also been reformatted for better presentation. Finally,=a 100 gpm value has for REM-3540 recirculation flow rate.liquid support of above.The been added 31.Page 2-26, Figure 2.1-2, the"Settling Basin" is now shown in order to depict the effluent pathway more accurately. MEM/ATTACH4/OS2 4/6 Appendix 4: CHANGES (continued) ,32.Page 2-27, Figure 2.1-3, the Normal Service Water Flow diagram is new and is, in response to a NRC request to have such a diagram included in the ODCM (reference letter S;R.Zimmerman to H.R.Denton, July 1, 1985, NLS-85-226) ~33.Page 2-28, Figure 2.1-4, the"Other Liquid Effluent Pathways" diagram shown in this figure is new and shows the possible non-routine liquid effluent lines from the plant.34.Page 3-4, Section 3.1.1.4, the term"f" is now summed into the denominator. The term is included to account more explicitly for significant addit'ional vent stack flow due to batch releases.Inclusion of the term is conservative inasmuch as it lowers the set point value.35.Page 3-4, Section 3.1.1.4, a"Note" is included that references the, FSAR.chapter, where the design basis, vent*stack'flow;.rates",can'be found.36.Page 3-5, Section 3.1~1.6, a"Note" is included to explain how gaseous effluent monitor set points can be converted to dimensions of pCi/sec.37.Page 3-8, Section 3.1.2.2, same as Item 34 earlier.38.Page 3-8, Section 3.1.2.2, at the definition of"F" the phrase"...or the actual flow rate" is added for clarity and operational flexibility. 39.Pages 3-9 through 3-13, Section 3.1.3, provides an additional alternative set point determination method for batch gaseous releases from the plant.40.Page 3-13, Section 3.1.4, provides the following discussion for effluent monitoring during hogging operations. If the, reactor has been, shut.down for less" than 30 days, the condenser vacuum discharge during initial hogging operations at plant start-up and prior to turbine operation will be routed directly to Turbine Building Vent Stack 3a.In this event, the set point methodologies of Sections 3.1.1 and 3.1.2 for the noble gas monitor located on Vent Stack 3a (see Appendix D)are applicable. MEM/ATTACH4/OS2 4/7 'r N Appendix 4: CHANGES (continued) If the reactor has been shut down for greater than 30 days, the.condenser vacuum pump.discharge'uring.initial hogging operations at plant start-up and,prior to turbine operation may be routed as dual exhaust to (1)the Turbine Vent Stack 3a and (2)the atmosphere directly.In this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).Set point determination in this case depends on knowledge of the flow rates through each of the exhaust pathways.Once these flows are established or estimated, the ratio of the flow through Vent Stack 3a to the flow in the direct exhaust path will be computed..This ratio will be used to reduce the set point on Vent Stack 3a to account for noble gases being exhausted concurrently via dual pathways.[END]The discussion is provided persuant to close out of ,.Safety.Evaluation Report open Item No.9.41'.Page.3-15, Table 3.1-1, typographic correction. The values 9.44E 01 and 2.23E 02 were corrected to 9.44E-01 and 2.23E-02, respectively, at Si column under Containment Purge or Pressure Relief via Vent Stack 1.42.Page 3-18, Section 3.2.1, the sentence: "Table 3.2-2 presents the distances from SHNPP to the nearest area for each of the 16 sectors as well as to the nearest residence, vegetable garden, cow, goat, and meat animal." has been deleted as unnecessary. 43.Page 3-21, Section 3.2.2, a new paragraph was created at"However..." for editorial clarity.This involved no text deletion or addition.44.Page 3-29, Section 3.3.1'.2, Equations 3.3-7 through 3.3-9 give the dose projection formula and dose limits for noble gases in gaseous effluents. 45.;.Page 3-32, Section 3.3.2','at.definition of RiB, typographic correction.,changing the word"vegetable" to meat 46.-Page 3-35, Section 3.3.2.2, Equations 3.3-13 and 3.3-14 provide the dose projection formula and dose limit for particulates and radioiodines in gaseous effluents. MEM/ATTACH4/OS2 4/8 Appendix 4: CHANGES (continued)

47.Page 3-55, Figure 3.1,;the containment pre-entry purge influent line monitor to the plant vent is now labeled with its identification number.Also, the presence of the Wide Range Gas Monitors is now identified and labelled appropriately.

48.Page 3-56, Figure 3-2, has been improved and corrected. The location of Vent Stack 3a is now in the appropriate position on the Turbine Building.49'age 3-57, Figure 3.3 has, been improved and updated.The diagram now shows the presence of (1)the Wide Range Gas Monitor, (2)the removable blind flange on the hogging line and (3)proper placement of the gland steam condenser influent to Vent Stack 3A.50.Page 4-16.through 4-18, Figures 4.1-2 through 4.1-4 have been improved.51Page'4-19,,Figure 4.1-5,'.has been" corrected with addition of"bottom sediment" and"shoreline sediment" sample designations. 52.Page 7-1, Section 7.0 entitled: "Licensee-Initiated Changes to the ODCM" has been added for explanatory purposes and regulatory reference. 53'age D-l, Appendix D, now lists the non-routine pathway effluent monitors on (1)the outdoor tank area drain transfer monitor line and (2)the turbine building floor drains effluent line.Also, the Normal Service Water (NSW)monitors are listed as well as the Wide Range Gas Monitors (WRGMs)and the Containment Pre-entry Purge line monitor.Most of these monitors are included for information only.54.Page 2-4, Section 2.l.l.lc.For clarity, include the following.'OTE'his method of determining the Maximum Release Rate (MRR)ensures.conformance with the,.test in Section F below.55.Page 2-5, Section 2.1.1.1d, Equation 2.1-5 at the definition of SPc.Previous definition read: SPc=2CR+Bkg.Revision of definition would read: SPc=2 (CR+Bkg).MEM/ATTACH4/OS2 4/9 Appendix 4: CHANGES (continued) Where: SPC=liquid monitor set point;cpm CR=monitor count rate above background given by the summation of the radionuclidic concentration in the tank multiplied by the monitor efficiency', cpm Bkg=monitor background; cpm The revision is because when the CR value is 0.0 cpm, i.e., there is no radioactivity, this would set the liquid monitor set point to background incurring the possibility of spurious alarms due to background fluctuation. The revision would correct for this by doubling the observed background value and allowing this to be used for the.set point.This.".,engineering.factor" is like others used in'the ODCM to prevent similar problems.56.Page 2-4, Section 2.1.1.1c.Change Equation 2.1-3 from: MRR=B to MRR=B (T)2(DFB)~DFB Also include the following definition: Tm=Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway.The Tm sum for the site shall not exceed one (1).And delete the following definition: Engineering factor to prevent spurious alarms caused by deviations in the mixtures of radionuclides which affect the monitor response.The change permits a more flexible determination of the MPC allocation for any given waste stream during concurrent release conditions. 57.Page 2-5, Section 2.1.1.1d, Equation 2.1-5 at the definition of SP.Change the following SP=2(CR+Bkg)to: SP=CR+Bkg+3.3~gk 2T MEM/ATTACH4/OS2 4/10 11',r,~l f ..Appendix 4:..CHANGES (continued) Also, replace the following definition'. 2=Engineering factor to prevent spurious alarms.caused by deviations in the mixture of radionuclides which affect the monitor response (see determination of Equation 2.1-3).With'new definition.'. 3~Bk 2T Statistical variance on the background (Bkg)counting rate quoted at the 99.95X confidence level at a time constant v (min)which is a function of Bkg.This te'rm is included to prevent inadvertent high alarm trips due to."random.;fluctuation:,in the monitor background. This change is made to account for radiation monitor background fluctuations more directly and with a known statistical confidence level.58.Page 2-6 to 2-9, Section 2.1.1.1d.Include the following text providing two alternative methods of calculating the set point for liquid effluent radiation monitors.ALTERNATIVE SET POINT METHOD BASED ON I 131 MPCW This method conservatively assumes: I.All of the radioactivity is due to I-131, which has the lowest Maximum Permissible Concentration (MPC), persuant to 10CFR20.II.Only'the minimum cooling, tower blowdown flow rate is available for dilution.III.The maximum effluent discharge flow rate is utilized.Determine SP , the set point above background in pCi/ml.SPm=MPC I 131 (B+MRR)(Tm)MRR (2.1-5A)MEM/ATTACH4/OS2 4/11 Appendix 4: CHANGES (continued) where.'SP=set point above background (pCi/ml)MRR=Maximum effluent discharge flow rate (gpm)B=Minimum dilution flow rate (gpm)T=Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway..The sum of T for the site shall not exceed one (1).Determine SP , the set point above background in cpm.c'=(m)(m)(2.1-5B)where: SP=set point above background (cpm)SP=set point above background (pCi/ml)E=Monitor efficiency (cpm/pCi/ml) Add the monitor background to either SP or SP to determine the monitor setting for the high alarm set point.ALTERNATIVE SET POINT METHOD BASED ON ANALYSIS OF EFFLUENT PRIOR TO DISCHARGE This method provides a set point using a more precise evaluation which includes the actual cooling to~er dilution flow rate, effluent discharge flow rate and an analysis of the principal gamma emitters in the liquid effluent to be released.Determine SP , the set point above background in pCi/ml.SPm=where: SPm g B set point above background (pCi/ml)(2.1-5C))c g Total radioactivity concentration of gamma-emitting radionuclides in liquid effluent prior to dilution (uCi/ml).Effluent discharge flow rate (gpm)Cooling tower blowdown flow rate (gpm)DFB given previously in equation 2.1-2.MEM/ATTACH4/OS2 4/12 I Appendix 4: CHANGES (continued) Tm=,Fraction of the radioactivity,.from the site that may be released via the monitored pathway to ensure that the site boundary limit is not ,exceeded due to simultaneous releases from more than one pathway.The sum of T for the site shall not exceed one (1).Determine SPc the monitor set point above background in cpm.SP=(SP)(E)(2.1-5D)where: SP=set point above background (cpm)SPm=set point above background (pCi/ml)E=monitor efficiency (cpm/pCi/ml)

Add;,the monitor"background;,to;either",.SP.or SP to,determine-the-monitor, setting.for'.the high alarm set point.If it is determined that f+B the release can be made.If it is determined that f+B DFB f)the release cannot be made.Reevaluate the discharge flow rate prior to dilution and/or the dilution flow rate.The first alternative method (Eq.2.1-5A)bases the set point on (1)the I-131 Maximum Permissible Concentration which is the lowest MPC>found in 10CFR20;(2).theminimum assured dilution flow'rate and (3)the maximum available effluent discharge flow rate.'his method is expected to be useful once SHNPP achieves steady state operating conditions.

The second alternative liquid set point method (Eq.2.1-5C)utilizes the characteristics of each batch liquid release in setting the high alarm set point value.This approach will generate variable high alarm set points depending upon (1)the specific radionuclidic mix in the liquid effluent;(2)the available dilution flow rate and,(3)anticipated discharge flow rate for the release'.The method provides a flexible approach to set point determination that will facilitate optimization of dilution and discharge flow rates.4/13 MEM/ATTACH4/OS2 Appendix 4: CHANGES (continued) 59.Page 2-21, Table 2.1-1, pump capacities for the SWST and TLEHS tanks have been correct'ed. Also the eductor factors have been updated from the pre-startup estimates given earlier to more realistic calculated values.60.Page 2-26, Figure 2.1-2 has been corrected to indicate the separate influent point from the settling basin to the cooling tower blowdown line.MISCELLANEOUS CHANGES In conformance to the final draft of the Technical Specifications references to"site, boundary" were changed to"exclusion boundary". The Table of Contents has been altered to reflect the presence of Chapter 7 and new pagination. MEM/ATTACH4/OS2 4/14 EXHIBIT 4 CHANGED PAGES FROM THE ODCM MEM/ATTACH4/OS2 4/15

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCH)provides the information and meth-odologies to be used by Shearon Harris Nuclear Power Plant, (SHNPP)to ensure compliance with Specifications 3.11.1, 3.11.2, and 3.11.4 of the SHNPP Tech-nical Specifications. These portions are those related to normal liquid and gaseous radiological effluents. They are intended to show compliance with 10CFR20, 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appro-pr i ate monitor ing instrumentation, dose rate, and cumulative, dose l imi-tations.Off-site dose estimates from nonroutine releases, wil 1 al so be included in the cumulative. dose estimates for the plant to comply wi.th Appendix I of IOCFR50.The ODCH is based on"Westinghouse Standard Technical Specifications" (NUREG 0452),"Preparation, of Radiological Effluent Technical Specifications for Nu-.clear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC).Specific plant procedures for implementation of this manual are presented, in the SHNPP Plant Operating Manual and other con-1 trolled documents. These procedures will be utilized by the operating staff of SHNPP to ensure compliance with technical specifications.. The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCH are expected in the future.Any such changes will be properly reviewed and approved as indi-cated in the Administration Control Section Specification 6.14.2 of the SHNPP Technical Specifications. ODCH (SHNPP)Rev.1.0

2.0 LIQUID

EFFLUENT Liquid releases at SHNPP are divided into batch and continuous modes.Each mode is further separated into routine and nonroutine release paths.Routine batch releases are expected via process streams described in Section 2.1.1.Nonroutine batch releases are effluent paths that only have the potential for.containing radioactivity. The outdoor tank'area drain line, the turbine building floor drains effluent line (yard oil separator line), and the efflu-ent from from the secondary waste treatment system (SWTS)are considered as nonroutine batch release points.In the SWTS, this is true only when no radioactivity is detectable due to primary to secondary leakage.These efflu-ent paths are monitored for radioactivity (see Appendix D and Figures 2.1-2 and 2.1-4)and should the setpoint be exceeded, releases are automatically terminated. Further discussion of these effluent lines is provided in Sec-tion 2.1.3.Planned continuous liquid releases containing radioactivity do not presently occur at SHNPP and thus these are considered as nonroutine release pathways.Section 2.1.2 describes continuous releases in greater detail.2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS)2.1.1 Batch Releases A batch release'is the discharge of liquid waste of a discrete volume.Batch releases from the SHNPP liquid vadwaste system may occur from treated laundry and hot shower tanks, secondary waste treatment tank, waste monitor tanks, and waste evaporator condensate tanks.The principal sources'f waste for these tanks are shown in Figure 2.1-1.The liquid radwaste effluent streams are shown in Figure 2.1-2.A batch release represents the emptying of one tank only.No concurrent liquid batch releases (i.e., more than one tank at a time)are made from SHNPP.The liquid radwaste system discharges to the cooling tower blowdown line.Dilution flow depends primarily on the blowdown Flow"B." If liquid effluent is diverted to the waste neutralization basin, some additional dilution may also occur at ODCM (SHNPP)2-1 Rev.1.0

thi s point.For the purpose of cal cul ation, the assumed value of B i s 16.5 cfs (7.4E3 GPM)as presented in the SHNPP FSAR, Section 11.2.3.This value is presently interpreted as the average blowdown flow rate but may be variable.If B is less than 16.5 cfs, then the measured flow rate should be used The sampling and analysis frequency and the type of analyses required by the SHNPP Technical Specifications are given in Table 4.11-'1 of the specifica-tions.All applicable radiation monitoring instrument numbers are listed in Appendix D.2.1.1.1 Prerelease The.radioactive content of each batch release will be determined prior to release in accordance with Table 4.11-1 of the SHNPP Technical Specifica-tions.Compliance with 10CFR20 will be shown in the following manner: a.Mixing Method for Isolated Liquid Effluent Tanks Prior to Sam-pling for Radioactivity Analyses Equation 2.1-0 below provides an acceptable method for ensuring a well-mixed tank so that a representative sample can be taken for radioactivity or'ther appropriate analyses.The method addresses the requirement found in Foot-note 2, Table 4.11-1, of Technical Specification 4.11.1.1.1..(V)(E)(n)(P)(60)(2.1-0)where:-Estimated.mixing time, hr Tank volume, gal Eductor factor Pump recirculation flow rate, gpm ODCM (SHNPP)2-2 Rev.1.0 Number of tank volumes for turnover;this will be typically two or more-60 60 min/hr Table 2.1-1 lists the volumes, eductor factors, and pump recirculation flow rates for individual liquid effluent release tanks.b.Minimum acceptable dilution factor: DFo where: C.Z MPC, l,l (2.1-1)DFo Minimum acceptable dilution factor determined from a gamma isotopic analysis of liquid effluent to be released Ci Concentration of radionu'elide"i" in the batch to be released, pCi/ml MPC Maximum permissible concentration of radio-nuclide"i" from Appendix B, Table II, Col-umn 2, of 10CFR20, pCi/ml DFB n (DFo)(2.1-2)where: DFB Conservative dilution factor used by SHNPP to calculate maximum release rate prior to re-lease in order to ensure compliance with 10CFR20 ODCM (SHNPP)2-3 Rev.1.0 A factor of>2;10CFR20 limits as specified in Appendix 8, Table II, Column 2.This factor represents one layer of conservatism for all releases at SHNPP DFo Minimum acceptable dilution factor per Equa-tion 2.1-1 c.Maximum release rate: MRR B~OV~Tm~B (2.1-3)where: MRR Maximum release rate of the batch to be re-leased, gpm Cooling tower blowdown flow rate, gpm 7.4 E3 gpm nominally or estimated available flow rate Tm Fraction of the radioactivity from'the site'that may-be released via monitored pathway to ensure that the site boundary limit's not exceeded due to simultaneous releases from more than one pathway.The T sum for the site shall.not exceed one (1)DFB Minimum acceptable dilution factor (DFo)made conservative by a factor of"n" per Equation!OS'.1-2 Note: This method of determining the Maximum Release Rate (MRR)Q+~ensures conformance with the test in Section F below.ODCM (SHNPP)2-4 Rev.1.0 d.Monitor Alarm/Trip Setpoint: Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2, for radio-nuclides other than dissolved or entrained noble gases.An MPC of 2 E-4 pCi/ml been established for noble gases dissolved or entrained in liquid effluents, based on the assumption that xenon-135 is the controlling radionuclide. Determine monitor count rate above background: CR (E C)E 1 1'(2.1-4)where: CR Calculated monitor count rate above back-Oo ground, cpm Ci Concentration of radionuclide"i" in the.batch to be released, yCi/ml Em The monitor ef f i ci ency f or the mixture of radionuclides in the liquid effluent prior to dilution, cpm/uCi/ml Determine monitor setpoint: SP SPm where: c E*m (2.1-5)SPm Monitor alarm/trip setpoint, qCi/ml ODCM (SHNPP)2-5 Rev.1.0 SPc Bkg 3%3 2T Bkg CR+Bkg+3.3 2T Statistical variance on the background (Bkg)counting rate quoted at the 99.95K confidence level at a time constant<(min)which is a function of Bkg.This term is included to prevent inadvertent high alarm trips due to random fluctuation in the monitor background. CR Calculated monitor count rate per Equa-tion 2.1-4, cpm I~Bkg Background count rate due to internal contami-nation and the radiation levels in the area in which the monitor is installed when the de-tector sample chamber is filled with an uncon-taminated fluid, cpm I is I CAUTION: This setpoint must be evaluated as conforming to the test of"Section f" below.ALTERNATIVE SETPOINT METHOD BASED ON I-131 MPCw This method conservatively assumes: (1)All of the radioactivity is due to I-131, which has the lowest Maximum Permissible Concentration (MPCw), persuant to 10CFR20.(2)Only the minimum cooling tower blowdown flow rate is avail-able for dilution.(3)The maximum effluent discharge flow rate is utilized.Determine SPm, the setpoint above background in pCi/ml.ODCM (SHNPP)2-6 Rev.1.0 S'm B+MRR 1-131 MRR m (2.1-5A)where: SPm Setpoint above background (qCi/ml)MRR Maximum effluent discharge flow rate (gpm)Minimum dilution flow rate (gpm)Fraction of the radioactivity from the site that may be released.via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway.,The sum of T for the site shall not exceed one (1).Determine SPc, the setpoint above background in cpm.SP (SP.)(E.)(2.1-5B)where: SPc Setpoint above background (cpm)SPm Setpoint above background (pCi/ml)Monitor eff iciency (cpm/pCi/ml) Add the monitor background to either SPm or SPc to determine the monitor setting for the high alarm setpoint.ALTERNATIVE SETPOINT METHOD BASED ON ANALYSIS OF EFFLUENT PRIOR TO DISCHARGE ODCM (SHNPP)2-7 Rev.1.0 This method provides a setpoint using a more precise evaluation which includes the actual cooling tower dilution flow rate, effluent dis-charge flow rate, and an analysis of the principal gamma emitters in the liquid effluent to the released.Determine SPm, the setpoint above background in yCi/ml.SPm z C (f+B))(T)g (DF)(f)m (2.1-5C)where: SPm Setpoint above background (pCi/ml)cg Total radioactivity concentration of gamma-emitting radionuclides in liquid effluent prior to dilution (pCi/ml).Effluent discharge flow rate (gpm)Cooling tower blowdown flow rate (gpm)DFB Given previously in Equation 2.1-2.Tm Fraction of the radioactivity from the site that may be released via the monitored pathway~to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway.The sum of Tm for the site shall not exceed one (1).Determine SPc, the monitor setpoint above background in cpm.SP (SP)(E)(2.1-5D)where: ODCM (SHNPP)2-8 Rev.1.0 SPc Setpoint above background (cpm)S'm Setpoint above background (uCi/ml)'m Monitor efficiency (cpm/pCi/ml) Add.the monitor background ,to either SPm or SPc to determine the monitor setting for the high alarm setpoint.If it is determined that f+B)1 (DF)(f)B the release can be.made.If it is determined that f+B (1 (DFB)(f)the release cannot be made.Reevaluate the discharge flow rate prior to dilution and/or the dilution flow rate.'.Calculated concentration at unrestricted area: (C.)(RR)Conci RR+B (2.1-6)where: Conc.Calculated concentration of radionucl-ide"i" at the unrestricted area, yCi/ml Ci Concentration of radionuclide"i" in the batch to be released, uCi/ml ODCM (SHNPP)2-9 Rev.1.0 RR Anticipated release rate of the batch that should not exceed the MRR as per Equation 2.1-3e gpm Cooling tower blowdown flow rate, gpm 7.4 E3 gpm nominally, or estimated available C~flow rate f.10CFR20 Prerelease Compliance Check: Before initiating the batch release, perform one final check for compliance with 10CFR20.If the sum of the ratio of.liquid'con-centration to MPC for all radionuclides-at the unrestricted area is less than or equal to 1, then 10CFR Part 20 limits have been met.The following equation must be true: z Conc./MPC. (1 i 1 1 where: Conc>Calculated concentration of radionuclide"i" at the unrestricted area per Equation 2.1-6,.uCi/ml Maximum permi ssibl e concentration of radi o-nuclide"i" from Appendix B, Table II, Column 2, of 10CFR20, yCi/ml 2.1.1.2 Postrel ease The actual concentration of each radionucl'ide following a batch release from a tank will be calculated to show final compliance with 10CFR20 as follows: a.Actual concentration at unrestricted area: ODCM (SHNPP)2-10 Rev.1.0 Concik (C.)(V)V+V (2.1-8)where: Conc;>The actual concentration of radionuclide"i" at the unrestricted area during release"k," pCi/ml Ci Concentration of radionuclide"i" in the batch released, gCi/ml Actual volume of 1 i qui d ef fluent re 1 eased during release"k," gal (see Table 2.1-1 for waste tank volumes and pump capacities). Vd Actual volume of dilution water during release"k," gal (B)(tk)where: Cooling tower blowdown flow rate, gpm Dur'ation of release"k," min b.10CFR20 Postrel ease Compliance Check: To show final compliance with 10CFR20, the following relationship ~must hold:~'~z (Concik/HPC.1 where: ODCH (SHNPP)2-11 Rev.1.0 Concik The actual concentration of radionuclide"i" during release"k" (from Equation 2.1-8), gCi/ml MPCi Maximum permissible concentration of radio-, nuclide"i" from Appendix B, Table IZ, Column 2, of 10CFR20, uCi/ml Note: Pursuant to 10CFR20 Appendix 8, Note 5,"...a radionuclide may be considered as not present in a mixture if (a)the ratio of the concentration of that radionuclide in the mixture (CA)to the concentration limit for that radionuclide specified in Table II of Appendix"B" (MPCA)does not exceed 1'/10 (i.e., CA/MPCA<1/10)and (b)the sum of such ratios for all the radionuclides considered as not present in the mixture does not exceed 1/4, i.e., CA/MPCA+CB/MPCB...+<1/4." 2.1.2 Continuous Releases A continuous release is the discharge of liquid wastes of a nondiscrete vol-ume;e.g., from a volume or system that has an input flow during the contin-uous release.Planned continuous releases do not presently occur at SHNPP, although the potential does exist in the Normal Service Water (NSW)System and Emergency Service Water (ESW)System.The returns from the NSW System to the Circulating-Water System are monitored by installed radiation monitors which are covered by Technical Specification 3.3.3.10.In addition, a weekly com-posite sample is collected and analyzed in accordance with Technical Specifi-cation Table 4.11-1.If radioactivity is detected in either system,.it will be eventually diluted by flow from the Circulating Water System.Thus, dilu-ted effluent concentrations can be either computed with knowledge-of the circulating water flow and/or monitored by periodic sampling of the Cooling Tower Basin.In the event radioactivity is detected in the Emergency Service Water System, then ESW flow, the Cooling Tower Basin, and the return flow to the auxiliary reservoir wil,l be periodically sampled.To show compliance with 10CFR20, the sum of the concentration of radionuclide"i" in the unrestricted area due to both continuous and batch releases divided by that isotope's MPC must again be less than 1 (see note in Section 2.1.1.2b).IC~P ODCM (SHNPP)2-12 Rev.1.0

2.1.2.1 Setpoints for the Normal Service Water (NSW)Monitors C Figure 2.1-3 is a diagram of the NSW system.A radiation monitor is located on each of the NSW returns to the circulating water system and they are indi-cated in the diagram.Either of two methods may be used to determine the setpoints for the NSW radiation monitors.Method 1: Use Equation 2.1-10 below: MOC=2 CPM bkg 2T Sensitivity (2.1-10)where: MDC Minimum detectable concentration for a given isotope or isotopic mix (pCi/ml)cpmbkg Ambient cpm+(mR/hrbk*cpm/mR/hr) bkg Time constant of signal processor (min).This is a function of cpmbkg sensitivity =For selected isotope or isotopic mix (cpm/.pCi/ml)Method 2: Use Equation 2.1-11 below: SPm SP c E (2.1-11)where: SPm Setpoint, pCi/ml 0OCM (SWPP)2-13 Rev.1.0 SPc (2)(bkg);cpm Engineering factor to account for spurious.alarms Em The monitor efficiency for the mixture of radionuclides in the liquid effluent (cpm/gCi/ml)bkg Background count rate due to internal radia-tion levels in the area in which the monitor is installed when the detector views an uncon-taminated fluid (cpm)Method 2 is acceptable from an effluent release standpoint because HSW is not discharged directly to the environment and it undergoes significant dilution in the cooling tower basin.2.1.3 Nonroutine Liquid Releases 2.1.3.1 Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rainwater collected in the outdoor tank area to the storm drain system and from there to the cooling tower blowdown line for release to the environment. The line is monitored for radioactivity and is capable of automatic termination of effluent release.Because no radioactivity is normally.expected in this line, the monitor set-point can be-determined with either Equation 2.1-10 or 2.1-11.If'the set-point is exceeded, the release is automatically terminated. Effluent can then be diverted to the floor drain system for processing and eventual release via the waste monitor tanks (see Figures 2.1-1 and 2.1-2).2.1.3.2 Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the w yard oil separator for release to the environment via the waste neutralization ODCM (SHNPP)2-14 Rev.1.0 system and then to the cooling tower blowdown line.Because no radioactivity is normally expected in this path, the setpoint for the radioactivity can be determined with either Equation 2.1-10 or 2.1-11.Should the setpoint be exceeded, the release is automatically terminated. Effluent can then be diverted to the secondary waste treatment system for processing and eventual release via the secondary waste treatment tank (see Figures 2.1.1 and 2.1-2).2.1.3.'3 Secondary Waste Treatment System (SWTS)When no radioactivity is detectable due to primary to secondary leakage, effluent from the SWTS may be released directly to the environment. In this event, the setpoint for the radioactivity monitor can be determined with either Equation 2.1.10 or 2.1.11.Should the setpoint be exceeded, the re-lease is automatically terminated.

2.2 COMPLIANCE

WITH 10CFR50 2.2.1 Cumulation of Doses The dose contribution from the release of liquid effluents will be calculated at least once every 31 days (monthly), and a cumulative summation of these total body and any organ doses will be maintained for each calendar quarter.The dose contribution for batch releases and all defined periods of continuous release will be calculated using the following equation: 0-z,.t lv k ik k))(2.2-1).k i where: D The cumulative dose commitment to the total.body or any organ~, from the liquid effluents releases, mrem: ODCM (SHNPP)2-15 Rev.1.0 730 Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109)Rev.1, liters/yr. Dw Dilution factor from the near-field area within one-quarter, mile of the release point to the potab1 e water intake f or the adul t water consumption 13.95 for uptake at the municipal water faci 1-ity at Lillington BF Bioaccumulation factor-for radionuclide"i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev..1), pCi/kg per pCi/1 DF Dose convers i on f actor f or radi onucl i de"i" for adults for a particular organ~(from Table E-11 of Regulatory Guide 1.109, Rev,.1), mrem/pCi I Table 2.2-1 presents the Ai values f or an adul t receptor in the SHHPP locale.Values of exp (-x.t)are presented in Table 2.2-2 for each radio-1 p nuclide"i." The sum of the cumulative dose from all batch and any continuous releases for a quarter:is compared to one-half the design objectives for total body and any organ.The sum of.the cumulative doses from all releases for a-calendar year is compared to,the design objective doses.The following rela-tionships should hold for the SHHPP to show compliance with Technical Specifi-cation 3.11.1.2.For the calendar quarter: D 1.5 mrem total body (2.2-4)D 5 mrem any organ (2.2-5)ODCM (SHNPP)2-18 Rev.1.0

For the calendar year: D 3 mrem total body (2.2-6)D 10 mrem any organ (2.2-7)where: D Cumulative total dose to any organ or the total body from all releases, mrem: The quarterly limits given above represent one-half the annual design objec-tive of 10CFR50, Appendix I, Section II.A.If any of-the limitsin Expres-sions'.2-4 through 2.2-'7 are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC.This report com-plies with Section IV.A of Appendix I, 10CFR50.2.2.2 Pro'ection of Doses I Dose projections for this section.are required at least once per 31 days (monthly)in Technical Specification 4.11.1.3.The doses will be projected using Equation 2.2-1.When the operational condi-tions for the projected month are to be the same as for the current month, the source-term"inputs into the equation for the projection can be taken directly from the current month's data..Where possible, credit for expected opera-tional evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.)should be taken in the dose projections. This may be ac-complished by using the source-term data from similar historical. operating experiences where practical. This may also be accomplished by using the projected Percent Power-Reactor Days for the unit as in the following expres-sion:-D D-=-i.e.,'2 D P D2=-(2.2-8)ODCM (SHNPP)2-19 Rev.1.0 where: Past month's dose to total body or any organ, mrem Projected month's dose to total body or any.organ, mrem For past month: (Average X power)x (Reactor~days of operation) P2 For projected month: (Estimated average power)x (Estimated reactor days of operation) To show compliance -with Technical Specification 3.11.1.3, the projected month's dose should be compared as in the following: D<0.06 mrem for total body (2.2-9)and D<0.2 mrem for any organ (2.2-10)If the projections exceed either Expressions 2.2-9 or 2.2-10, then the appro-priate portions of the liquid radwaste treatment system shall be used to reduce releases of radioactivity.. ODCM (SHNPP)2-20 Rev.1.0

TABLE 2.1-1 LI(UID EFFLUENT RELEASE TANKS AND PUMPS Tank(2)No.of Tanks PUMP CAPACITY (pm)Recirculation Process Eductor Factor Tank Volume (oal.)Radiation Effluent Monitor ID SWST TLIIHS 35 35 100 0 2 I 0 0 25 0 25 25,000 10,000 25,000 25,000.REM-3542 REM-3541 REM-3541 REM-3540 Reference SHNPP FSAR Tables ll 5'-1 and 11,2.1-7 SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TLIIHS: Treated Laundry and Hot Shower Tank ODCM (SHNPP)2-21 Rev.1.0 Flffult 2.1.2 LEOUIO EF FLUENT FLOW STTEEAM TEIAOTEAM 4 fhEAIED LAUIIIINY 1 Naf thaeth tANK thEAI ED EJlIPIDNY~Ilaf tllatlth lANK O'E tt htf4 ItfL ttla tfaaNDAht tIAtf t SANtLE'IANK tIAII E MONIIOh tAHK WAtf t uCWIlah fANK htN-tftf tatt t NAff t HEUINALIEAI ION SAEEN tlEN~t f I LINO tAIIN ht&tftfL ttt I IIAEf I EVAIOIIAIOh COHOEHIAf t'f AllK tfAEI t EVAtahhfah CONDENIAft fAtlK LEOENDg 1 tANK OK tAlIN NAOIAIION tttLUENE tKINffah 0 NAhhl~LA K t FIGURE I 1 3 NORMAL SERVICE WATER F LOW DIAGRAM R LACTOA AUIILIAtt Y I MILO tttC NEAT LOADS O C 0 EM 5500 NEAT LDAO5 WASTE MOCESSINC 5 UILO INC~fM 5500 MAIN CONDENSER G Z TVRSINE SUILO INC CIRCULATINC WATER t UMtS LEGEND REM RADIATION EltSLUEIIT MONITOR NSW NORMAL SERVICE WATER OO CODLING TOleER SASIN C el el~.'C NOTE:~eeteetet Itive~et Settee Ie etet Seetettt tetet to SSAR HARRIS LAgE CDOLING TOWEA SLOWDOteN ODCM (SHHPP)2-27 Rev.1.0 C)C7 n FIphe 2, I 0 OIIIEII llOUID EFFI.UENl PA1IIICAYS IUhtlkl CUIlblkO SLOONODALkl tllLUCNI LINC IIINCIIit rtba I LOON ONAINI CVMCC Mhb OIL CCSAhA ION wilt t NlllfhiLIlA IION CA SIN Stlltlkh SASIH~~OUI SIDC IANK ANIA ONAIN CIILUIHI UNC OUI Ilhl TANK AhlA OhAIN SIOhM OD AIM Sr l'I t M IM'AN SE DIVChf CP 10 CtCONOAhr WAll t lhtAIMlNI crsl CM"CANCI PIVINICDIO LIOUIONAOWACIC lhtAlutkl CrtftN"'lhl INILVLNI COINS ID lht COOLINO IOrllh CLOwbOwN LINC Il lhl CAINE INI LULNI tOIIII INOICAICD IN I IOUDC I.I l NAhhll LAIC IP 3, l.i.4 Determine Cm, the maximum accePtable total radioactivity concentra-tion of all noble oas radionuclides in the gaseous effluent t33Ci/cci. (2.12 E-3).0 Cm F~f NOTE:.1lse the'lower of the O values obtained in Sections 3.1.1.2 and 3.1.1.3.This will protect both the skin and total body from being exposed to the limit.where: Use the actual.effluent flow rate or the maximum effluent flow rate at the point of release (cfm)based on design flow rates given below: 22,t350 cfm (Turbine Bldg.Vent Stack 3A).207,000 cfm (Waste Processing Bldg.Vent Stack 5).103,500 cfm (Waste Processing Bldg.Vent Stack 5A).'390,000 cfm (Plant Vent Stack 1).When contain-ment preentry purge occurs, this should include an additional 33,700 cfm.Release flow rate for batch releases, if applicable (cfm),.2.12 E-3=Unit conversion factor to convert uCi/sec/cfm to gCi/cc.NOT.:: The F values were taken from the FSAR, Chapter 3,Amendment 15, Table 9.4.0-2.-3.1.1.3 Deterfiine CR, the calculated monitor count rate above background attributed to the noble gas radionuclides tcpmj by: CR QDCM (SHHPP)3-4 Rev.1.0 m Obtained from the applicable effluent monitor ef f i ci ency (cpm/uCi/cc) .3 1.1.6 Determine the HSP, the moni tor high-alarm setpoint including back-ground fcpm)by: HSP TmCR+Bkg (3.1-5)where: m Fraction of the radioactivity from the site'that may be released.via the monitored path~ay to en-sure that the exclusion boundary limit is not exceeded due to simultaneous releases from several pathways.0.03 for Turbine Bldg.Vent Stack 3A.0.29 for Waste Processing Bldg.'ent Stack 5.0.14 for Waste Processing Bldg.Vent Stack 5A.0.54 for Plant Vent Stack l.Bkg The background count rate (cpm)due to internal contamination and the radiation levels in the area in which the monitor is ins alled when the detec-tor sample chamber is filled with uncontaminated ail~Hote: The vent stack monitors are designed such that the high-alarm setpoint can be input.as uCi/sec or uCi/cc.The monitor setpoint in uCi/sec can be obtained by multi-plying the lowest q value (obtained from Sections ODCM (SHNPP)3-5 Rev.1.0 3.1.1.2 and 3.1.1.3)by the T value found in Section 3.1.1.6.The uCi/cc setpoint can be obtained by dividing the uCi/sec setpoint by the design or process flow rate in cc/sec.The equations for calculating the setpoint in cpm are included for completeness and may be used if desired.3.1.2 Alternative Setooint Determination Method Based on Gaseous Effluent Analysis Prior to Release The following method applies to setpoint determinations. from plant vent stacks during the operational conditions listed below and when the gaseous effluent's sampled prior to release:~Batch mode release of containment pressure relief.Batch release of waste gas decay tanks.3.1.2.1 Determine the maximum allowable discharge flow rate prior to dilu-tion..a.Determine f,'the maximum acceptable, gaseous flow rate from con-tainment or from the waste gas decay tanks (cfm), based upon the whole body exposure limit by: 0.848 T where: Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the exclusion boundary limit is not exceeded due to simultaneous releases from several pathways (see Section 3.1.1.6 earlier).ODCM (SHHPP)3-6 Rev.1.0 5.09 A combined conversion factor consisting of the skin dose limit of 3000 mrem/yr, times a conversion. constant of 2.12 E-3 to convert cc/sec to cfm, times 0.80, an engineering factor to prevent spurious alarms.c.The rate at which the noble gas, activity is released from the containment during purging or pressure relief or from the waste gas decay tanks shall not exceed the smaller of the two"f" val-ues calculated in Steps..a and b above..3.1.2.2 Determine the monitor setpoint equivalent to the maximum allowable discharge flow rate: Determine Cm, Che maximum-radi oacti vi ty concentration of al 1 noble gas radionuclides to be released during containment purge or pressure relief via Plant Vent Stack 1 or waste gas decay tanks discharge via the Waste Processing Bldg Vent Stack 5 after'ilution by other discharges in the respective stacks (uCi/cc): I C F+f where: Ct The total radioactivity concentration of all noble gas radionuclides in the gas to be discharged from the containment or waste gas decay tanks prior to dilution (uCi/cc).The maximum acceptable gaseous-flow rate'rom containment 'r-from the waste gas decay tanks (cfm).The maximum design vent stack flow rate (see Section 3.1.1.4 earlier or the actual flow rate).3E.I ODCH (SHHPP)3-8 Rev.1.0 Determine CR, the calculated monitor count rate above background attributed to tne radionuclides [cpm).CR is obtained by using the applicable effluent monitor effic iency"Em" (cpm/qCi/cc): CR{Cm)(Em)(3.1-9)c.Determine HSP, the monitor high-alarm setpoint including back-"'round[cpm]by: HSP CR+Bkg(3.1-10)where: Bkg Monitor background (cpm)I d..The monitor HSP shall be set at or below the calculated. value during containment purges or, releases from the waste gas decay tanks.If containment pur ges or pressure re 1 i ef or waste gas decay tanks releases are made while other sources of noble gas activity are being released from their respective stacks, the monitor HSP shall not exceed the calculated value determined in Section 3.1.1.3.1.3 Alternative Setooint Determination Based on Gaseous Effluent'Analysis Prior to Release and Estimates of Maximum Acceptable Flow Rate The following method applies to gaseous releases when the maximum acceptable effluent flow rate at the point of release is given and the associated high-alarm setpoint based on this flow rate is de-sired.The method is applicable during the following operational conditions: ODCM (SHHPP)3-9 Rev.1.0 ~Batch release of containment purge via Plant Vent Stack l.Batch release of containment pressure relief via Plan'.Vent Stack 1.Batch release of waste gas decay tanks via Waste Processing Building Vent Stack 5.3.1.3.1 Determine G;, the noble gas release rate for radionuclide"i,"))Ci/sec Gi 472 (C'i (F (3.1-11.)where: 472=472 cc/sec/cfm Ci The radioactivity concentration of noble gas radio-nuclide"i" in the gaseous effluent from the analysis of the gaseous effluent to be released,)2Ci/cc F=The maximum acceptable effluent flow rate at the point of relea.se, cfm.30 for one condenser vacuum pump 33,700 for one containment purge pump 2.26 66 (-)(-)2730 14.7 T for containment pressure relief t ODCH (SHHPP)3-10 Rev.1.0 t 273o coo(-){-)14.7 T t for a waste gas decay tank release where: 2.26 E6 and 600 are the volumes in ft of the containment and decay 3 tank, respectively, and T , Tt, n Pc, and A Pt are the estimated, respective temperature and change in pressure (psig)following the release of the containment and decay tank;and, 14.7=lb/in2, i.e., 1 atmosphere pressure Length of release, min 273'K-0 C Tt'c 273 K+C 3.1.3.2 Determine the monitor alarm setpoint based on total body dose rate: a.Determine'Q (the monitor count rate per mrem/yr, total body)CR C (Xlq)z.K.G.(3.1-12)where: C=The count rate of the monitor corresponding. to the radioactivity concentration in the analyzed sample (C[Ci])the monitor efficiency]) The highest calculated annual average relative disper-X/g sion factor for any area at or beyond the exclusion boundary for all sectors (sec/m)from Appendix A.3 ODCH (SHNPP)3-11 Rev.1.0 2.06 E-6 sec/m from Table A-1, Appendix A 3 V,.=The total whole.body dose factor due to gamma emissions 1 from noble gas radionuclide"i" mrem/yr/~Ci/m from Table 3.1-2 b.Determine St, the count rate of the gaseous effluent noble gas monitor at the alarm setpoint based on total body dose rate,, cpm: S=ISF T~D~CR I+Bkg t m t t (3.1-13)'here: SF An engineering factor used to provide a margin of safety for cumulative uncertainties of measurements. -0.5 Dt.'.500 mrem/yr, the total body dose rate'limit Tm Fraction of the radioactivity from the site that may be released via the monitored pathway to ensurethat the exclusion boundary limit is not exceeded due to simul-taneous releases from several pathways (see Section 3.1.1.6 earl ier)Bkg=The background count rate due to internal contamination and the radiation levels in the area in which the moni-tor is installed when the detector sample chamber is f'illed with uncontaminated air, cpm 3.1.3.3 Determine the monitor alarm setpoint based on the skin dose rate: a.Determine CRs (the monitor count rate per mrem/yr, skin): ODCM (SHHPP), 3-12 Rev.1.0 CRs where:-z.(L.+1.1 M.)(G.)x/Q i i , i i (3.1-14)+1.1 Ni The total skin dose factor due to emissions from 3'oble gas.radionuclde"i" (mrem/yr/uCi/m )from Table 3.1-2 b.Determine S, the count rate of the gaseous effluent noble gas monitor at the alarm setpoint based on the dose rate to the skin, cpm S=[SF-T D~CR'+Bkg s m s s (3.1-15)where: Bkg='The background count rate due to internal contamination and the radiation levels in the area in which the moni-tor is installed when the detector sample chamber is f'illed with uncontaminated air,cpm.Ds ,.=3000 mrem/yr, the dose rate to the skin limit 3.1.3.4 Determine the actual gaseous monitor setpoint: The respective monitor setpoints, based on the dose rate limits to the tota1 body (St)and to the skin (Ss), are compared and the lesser value is'used as-the monitor HSP;i.e., high-alarm setpoint.If containment purges or pressure re1ief or'aste gas decay tanks re-leases are made while other sources of noble gas activity are being released from their respective stacks, the monitor HSP sha'11 not exceed the calculated value determined in Section 3.1.1 3.1.4 Effluent Honitorina During Hoooino Operations ODCM (SHHPP)3-13 Rev.1.0

If the reactor has been shut down for less than 30 days, the conden-ser vacuum discharge during initial hogging operations at plant start-up and prior to turbine operation will be routed directly to Turbine Building Vent Stack 3a.In this event, the setpoint methodo-logies of Sections 3.1.1 and 3.1.2 for the noble gas monitor located on Vent Stack 3a (see Appendix D)are applicable. the reactor has been shut down for greater than 30 days, the condenser vacuum pump discharge during initial hogging operations at plant start-up and prior to turbine operation may be routed as dual exhaust to (1)the Turbine Vent Stack 3a and (2).the atmosphere directly.En this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).Setpoint determination in this case depends on knowledge of the flow rates through each of the exhaust pathways.Once these flows are established or estimated, the ratio of the flow through Vent Stack 3a to the flow in the direct exhaust path will be computed.This ratio 0 will be used to reduce the setpoint on Vent Stack 3a to account for noble gases being exhausted concurrently via,dual pathways.ODC~(SH~pp)3-14 Rev.1.0 .TABLE 3.1-1 GASEOUS SOURCE TERHS*Plant Vent Release via Vent Stack 1 Rad l onuc 1 i de A l (C l/yr)S i Condenser Air Vacuum via" Vent Stack 3A Al (Cl/yr)Containment Purge.~or Presure Relief via Gas Decay Tanks via Vent Stack 1 Vent Stack 5 Al (Ci/yr)Sl Al (Ci/yr)S l Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m XB-133 Xe-135m Xe-135 Xe-137 XQ-138 TOTAL O.OOE 00 3.0E 00 O.OOE 00 1.QE 00 5.5%OO O.OOE 00 O.OOE 00 2.0E 00 1.2E 02 0.00E 00 7.0E 00 O.OOE 00 1.OE OO 1.39E 02 O.OOE 00 2.16E-02 O.OOE 00 7.19E-03 3.60E-02-O.OOE 00 O.OOE 00 1.44E-02 8.63E-01 O.OOE 00 5.04E-02 O.OOE 00 7.19E-03 O.OOE 00 2.0E 00 O.OOE 00 O.OOE 00 3.0E 00 O.OOE 00 O.OOE 00).OE 00 7.2E 01 O.OOE 00 4.0E 00 O.OOE 00 O.OOE OO 8.20E 01 O.OOE 00 2.44E-02 O.OOE 00 O.OOE 00 3.66E-02 O.OOE 00 O.OOE 00 1.22E-02 8.78E-01 O.OOE 00 4.88E-02 O.OOE 00 O.OOE 00 1.0E 00 1.2E 01.4.0E 00 Z.OE 00 1.6E 01 0.00E 00 1.0E 01 4.3E 01 2.5E 03 O.OE 00 5.9E 01 O.OOE 00 O.OOE 00 2.64E 03 3,78E-04 4.53E-03 1.51E-03 7.56E-04 6.05E-03 O.OOE 00 3.78E-03 1.62E-02 9.44E-01 O.OOE-01 2.23E-02 O.OOE 01 O.OOE 01 O.OOE 00 O.OOE 00 2.1E 02 O.OOE 00 O.OOE 00 O.OOE 00 3.0E 00'.00E 00 1.0E 00 O.OOE 00 0.00E 00 O.OOE 00 O.OOE 00 2.14E 02 O.OOE 00 0.00E 00 9.81E-01 O.OOE 00 O.OOE 00 O.OOE 00 1:40E-02 0.00E 00 4.67E-03 0.00E'00 O.OOE 00 O.OOE 00 O.OOE 00 Source terms are based upon GALE Code (see SilHPP FSAR Table 11.3.3-1)and not actual releases.These values only apply to routine releases and should not be taken as a complete inventory of noble gases ln an emergency s l tuat ion.

Li The skin dose factor due to beta emissions for noble gas radionuclide"i," mrem/year per gCi/m.The air dose factor due to gamma emissions for noble gas radionuclide"i," mrad/year per gCi/m.The ratio of the tissue to air absorption coeffi-cients over the energy range of the photon of interest, mrem/mrad (Reference NUREG-0133). The release, rate of noble gas radionuclide"i" in gaseous ef f luents f rom al l plant vent stacks.(uCi/sec). The determination of limiting location for implementation of 10CFR20 for noble gases is a function of the radionuclide mix, isotopic release rate, and the meteorology. The radionuclide mix was based upon source terms calculated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1.They are reproduced in Table 3.2-1 as a function of release point.The X/g values utilized in the equations for implementation of 10CFRZO are based upon the maximum long-term annual average (X/g)in the unrestricted area.Long-term annual average{X/Q)values for the SHNPP release points to the special locations in Table 3.2-2 are presented in Appendix A.A descrip-tion of their derivation is also provided in this appendix.To select the limiting location, the highest annual average X/g value for ground-level releases is the'ontrolling factor.Long-term annual average{X/g)values were calculated 'assuming no decay, undepleted transport to the exclusion. boundary, and are given in, Table A-l, Append x ndix A.The maximum exclusion boundary X/g for ground-level releases occurs at the NNE and SSW sectors.However, the limiting location for implementation of 10CFR20 for noble gases is considered to be the exclusion boundary (1.33 miles)in the NNE sector due to the generally greater population density in this direction. OOCM (SHNPP)3-1S Rev.1.0 again ase up n b s d upon the source terms calculated using the GALE Code.The mix and the source erms terms are presented in Table.3.2-1 as a function of release point.The determina ion o d t'ion of the controlling exclusion boundary location was based upon the ig es e th h hest exclusion boundary 0/g value.The determination of actual receptor hami ing o t 1 iting location was based upon the milk pathway 0/g value and the P'alue for the respective milk path~ay;Values for P;were calculated for an infant for various radionuclides for the.inhalation, ground plane, cow milk, and goat milk pathways using the, methodology of HUREG-0133. The P;values are presented in Table 3.2-4.A description of the methodology used in calculating the Pi values is presented in Appendix B.The values of P;re-flect, for each radionuclide, the maximum P;value for any organ for.each individual pathway of exposure.The goat milk pathway is present near SHNPP, as is the cow milk pathway.\However, the cow milk pathway Pi values were utilized in the determination of the controlling location because the product of the maximum cow milk pathway 0/g and P-values were greater than those for the goat.For the case of an 1 infant being present at the site at the exclusion boundary.-or

at the real path~ay location, the ground plane pathway is not considered as a reasonable exposure pathway (i.e., Pi 0).However, P;values are presented in Table lG 3.2-4 for completeness.

The annual average[0/qJ values at the special locations, which will be uti-lized in Equation 3.2-3, are obtained from the tables.presented in Appen-dix A.The[X/g]values which will be utilized in Equation 3.2-3 are also obtained from the tables presented in Appendix A.A description of the deri-vation'f the X/g and 0/g values is provided in Appendix A.ODCM{SHNPP)3-21 Rev.1.0 power levels, major planned liquid releases, etc.)should be:aken in the dose projections. This may be accomplished by using source-term data from similar.historical operating experiences where practical. This may also be.accom-h d b using the projected percent power-Reactor Days for the unit as in.plishe y usin the following expression. 'g P1, P i.e-0 1 2 P (3.3-7)where: Past month's dose to total body or any organ,.mrem D2 Projected month's dose to total body or any organ, mrem PI For past month: (Average" power)x (Reactor days of operation) P2 For projected.month: (Estimated average~power)x (Estimated reactor days'of operation) To show.compl iance with Technical Specification 3.11.2.4, the"projected month's dose should be compared as in the following: D<0.2 mrad to air fo'r gamma radiation Y (3.3-8)D<0.4 mrad to air for beta radiation (3.3-9)B If the projections exceed either Expressions,3.3-8 or 3.3-9, then the appro-Ea priate'ortions of the'aseous radwaste treatment system shall be used to reduce releases of radioactivity. DOCH (SHHPP}3-29 Rev.1.0 R I Dose factor for an organ for,radionuclide"i" for~3 the inhalation pathway, mrem/yr per uCl/m.Ri V Dose factor for an organ for radionuclide"i" for the vegetable pathway, mrem/yr per uCi/sec per m Ri 8 Dose factor for an organ for radionuclide"i" for-2 the meat pathway, mrem/yr per uCi/sec per m~Dose factor for an organ for tritium for the milk pathway mrem/yr per uCi/m.~3 R Ty Dose factor for an organ for tritium for the vege-3 table pathway, mrem/yr per uCi/m.RT I Dose factor for an organ for tritium for the inha-lation pathway, mrem/yr per uCi/m.,~3 RT 8 Dose factor for an organ-'for tritium f or the meat~3 pathway, mrem/yr per uC>/m.<Tv Release of tritium in.gaseous effluents for long-term vent stack releases (>500 hrs/yr), pCi.qTv Release of tritium in gaseous effluents for short-term vent stack releases (<500 hrs/yr), uCi.To show compliance with.10CFR50, Equation 3.3-10 is evaluated at the limiting real pathway location.At SHHPP this location is 2.2 miles in the H sector.The critical receptor is an infant.Appropriate X/g and D/g values from tables in Appendix A are used.For this document,'Song-term-annua'1 average X/9 and D/g values may be used in lieu of short-term values (see Section 3.0 earlier).ODCM (SHHPP)3-32 Rev.1.0 0, operational conditions for the projected month are expected to be the same as for the current month, the source-term inputs into the equation for the pro-jection can be taken directly from the current month's data.Where possible, credit for expected operational evolutions ('i.e., outages, increased power levels, major planned liquid releases, etc.)should be taken in the dose projections. This may be accomplished by using source term data from similar historical operating experiences where practical. This may also be accom-plished by the using projected Percent Power-Reactor Days for the unit as in the following expression: D2 1.e., 0 P2'PI{3.3->3)where: Past month's dose to total body or any organ, mrem Projected month's dose to total body or any organ, mrem P1 c For past month: operation) V (Average" power)x (Reactor days of P2 For projected month: (Estimated average" power)x (Estimated.reactor days of operation) To show compl i ance with Techni cal Speci f ication 3.11.2.4, the pro jected month's dose should be compared as in the following: D<0.3 mrem to any organ (3.3-14)If the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system.shall be used to reduce releases of radioactivity. ODCM (SHNPP)3-35 Rev.1.0 f UIIEINE bLITO VENT SlACK 1A Flgur~3.1 SIINPP GASEOUS WASTE STllEAMS UNIT T SsK II&IT1 I~Is~Irrrrf ntll~HADIAT ION lt ILUt HT MONI Ton WIS~WASTE tn4CElllNO SLD4 HAS~HEACToh AUKILIAHY~LD4 IH'I FUEL HAHOLIHO~LDO'NAOH r r gg rxr If v'll~CONDSNSth VACWM tIXKF WAE TE TIIQCEEE INa aLOa VEN T a TACK b Wtf HOT b COLO LAVNDhl.~wte colo LAUNonY Dnf tnt WFS OFFICE AHEA 1~r Aslo Irv~I~~wts oftlct AntA ExHAUIT wts coNlnoL noou suoxt EXHAUTT Wtl CHILLEH noolf EXHAUlf Wtl OtHEHAL ADEA EXHAUlf WASTE tnoCESIIN4 AhlAS FILI tnt D f XHAUlf WASTE OAS DECAY TANKS TTAETE FIIOCETIINO ~LM VENT ETACK EA rslrv I~~I I lrr~ssl Ak Wtf SWITCHOE Ahhoofl f XHAUlf 1(rx&lrrl~~I wts HYAc EDUlt.nooQ E xHAvs I wts ttnsoHHELHAHDLIHO FAcILI'IY ExHAvs'I Wtl llof~LOWACTIYITY EXIIAUST litt LAS AHEA EXIIAUlf PLANT VENT StACK I XIII Av'I~I>l~A rx~rl xr XIH CONf AhxltNf thE ENThY FUnof III'AY I~II HAS HOOIIAL EXHAUST IIKRIAY~I~~A appal nAS f VlnolHCY EXHAUST HAS Vf HIILAT ION SY Sf ELI HYDDOOEN tlxlot'AS SMOKE FIXIOE nxs tvnGE al 1xlalxr I~~Itx FHS HohllAL EXHAUST NOHTH FHS HonllAL txHAVST SOUTH ss~FHS HOnllAL tXHAVSI lot tn.Tl..f SOUTH KK Axial~Isl~~~FHS HonllAL EXHAUST lot th.TLI SOUTH axr AKMItlsl~K~A Oa K~M FHS EME notNCY EKHAVSf rxwIKDIK~~~~~1~Ks tl'lssss~~l~~I I~~I OMrxx~roL

CRAr r CARRIna flW5f IIEFVTLfNO WATth STOhAOE TANK hMWST htACTORMAKEVCWAl'thSfORAGE TANK CST COHOENSATE SIOhAOE TANK I LANT NORTII MAONE'TIC HORTII J 0 E r I J W VEIIT STACK IN I T VENT STACK F28 TX'CESSI P CST nwsr gw Pi3 SERVICE EATMEI 1Lll 4 0 OO WA ll IOV E'ECV FARRINO AREA COOLINO TOWER RARIIINO t AREA SWI f CNVARO F IOVflE 2.2 5IIEAflON IIARhfS NUCLEAR COWT fl CLAN I CAflOLINA FOWEh S LICIIT COMI'ANY SCIIEMATIC OF>LAHf AlflSOtlNE EFFI.VENT hELEASE FOIHTS

Flpure 3.3 SllNPP CONDENSEA OFF GAS SYSTEM 0 litt If V till IHtlOMI TUREIHE ELDO VENT STACKS.-SA GLAIIO Sf EAM COND.CVtEI 5'AIN COtt D 5 tt5 5 h Ilail I IV llll I IOG 0 HIO VALVE~LIND f LA NO E yVRGM TIIDE hAtlGE GA5 MOHIIOII REM RADIA J ION Elf LUEtll MOHIIOII'COHDEH5EIIVACUUM TUMT EffLUEtlf TIIEATMEHT SYSTEM Af MOSTIIERE ADATI TO I ROM SIGURE~I 0 5 Sttttit I SAR AMIHQMI Hf HO.IS gb r n~/~1 0~ FIGURE 4.l4\~'I i~~Ma/t"'II gII'Il/,'X..-/~'./SHEARON HARRIS NUCLEAR POWER PLANT ENVIRONMENTAL RADIOLOGICAL SAMPLING POINTS~,': '"'0/~w~/: lg+r/~/k I kl Sl i/'," ,!~'"., i'-Z.II~Q'lOMILE AADIU~I~ir~Arr~l/II~Ii I r'I Ill~'I gl ir~42~~Ir~I rh, Cwater~~M~I irr~I'~~a-~)g~~~rr I~,i~~iII~I~~~.~N Ib~rrr~II~~I rr~/~rI~rr~~I iir r, r<<I r~'~~~r'(r I IICSERT~Ir lalMG'I II ('II~r'~IJ I HI~I t I~r 1'~J.4-17 FIGURE 4.1<ERIENOSHII'HEARON HARRIS NUCLEAR POWER PLANT ENyIRPNMENTAL RADIOLOGICAL SAMPLING POINTS N a NEYI HILL'l I I INg BONSAI.Or MERRY OAKS a 4 hg x-~EXCLUSION SOUNOARY I.I.16 1$11 0 0 I Q~i 00o HARRIS LAKE=I l 1916\I 0 I'I*I I IQSP 1407 4-aS

FIGURE 4.1 5 LEGEND o 0 o 0'~0~STATION NUMddII 5'I2 12 14 15 15 15 20'21 2i SYMSOL AP, AC.TL Al, AC TL M,AC, TL AP, AC.TL Af, AC, Mrl.PC, Tl.TL TL TL Tl.TL TI.TL TL TL Tl.TL TL MrL TL TL Tl.Tl Tl.TL TL 0~0$'0 STATION NuMddh 42 49 51 5YMSOL AP.*C.SW.SS.'TL TL TL TL TL TL TL TL TL TL SW.OW GW MC, SC CH fH dc TL TL FIGURE 4.1-2 FIGURE 4.1<FIGURE 4.1A 0"'2 Qi*C Ae.SS SC OH GW M II 5W DW TL Arr eKrrreee Alt f errlcelKe donorrr Oecwroerr SrroreeIH Seolhlerrf oooo Croo 5 res G nwooererer Mrra Serteoe W erer Orroeeed Ye erer TLD 4-g 9 7.0 LICEHSEE-IHITIATED CHAHGES TO THE ODCM Pursuant to Technical Specification 6.14.2, licenseo-initiated changes to the Off-Site Dose Calculation Manual: A.Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the , change(s)was made effective. This submittal shall contain: 1.Sufficiently detailed information to totally support the rationale f'r the change without benefit of additional or.supplemental information. Information submitted should consist of a package of those pages of the ODCM changed with each page numbered, dated, and containing the revision number together with appropriate analyses of evaluations'justifying the change(s). .2.A determination that the change will not reduce the." accuracy or reliability= of dose calculations or setpoint determinations, 3.Documentation of the fact that the change has been reviewed-and found acceptable by-the PHSC.B.Shall become effective upon review and acceptance by the PHSC.ODCM (SHHPP)7-1 Rev.1.0

APPENDIX D RADIOACTIVE LIQUID AHD GASEOUS EFFLUEHT MONITORING IHSTRUMEHTATIOH NUMBERS>>>>Li uid Effluent Monitorina Instruments A.Treated Laundry and Hot Shower Tank............. .......B Waste Monitor Tank...'.................................. C.Waste Evaporator Condensate Tank........................ D.Secondary Waste Sample Tank..................;..... F.Outdoor Tank Area Drain Transfer Pump Monitor........... G.Turbine Building Floor Drains Effluent.............;.... Gaseous Effluent Monitorina Instruments A.Plant Vent Stack'l.,l'1..Plant Vent Stack'1................................. .'.-Reactor Auxiliary Building Normal Exhaust............ '...3.Reactor Auxiliary Building Emergency Exhaust........ 4'uel Handling Building Normal Exhaust (South)....... 5.Fuel Handling Building Normal Exhaust (South)....... 6.Fuel Handling Building Emergency Exhaust............ E.Hormal Service Water Returns to Circulating Mater System---From Waste Processing Building............. ......From.Reactor Auxiliary Building...................... Monitor Identification REM-3540 REM-3541 REM-3541 REM-3542 REM-1SW-3500A .REM-1$W-3500B REM-3530 REM-3528 REM-lAV-3509-SA RN-1AV-3509-1SA>> REM-1AV-3531 REM-1A-3532A REN 1FL-3506 REN-1FL-3507 REN-1FL-350BA-SA 7.Fuel Handling Building Emergency Exhaust........... REN-1FL-350BB-SB '.C.D.B.Containment Pre-Entry Purge.............. .'........Turbine Building Vent Stack 3A........... .............1.Condenser Vacuum Effluent Line.....Waste Processing Building Vent Stack 5.......... .......Waste Process'ing Building Vent Stack 5A................ REN-1LT-3502B RM-1TV-3536-1>> REM-1TV-3534 REM-1WV-3546 RM-1WV-3546-1>> REN-1WV-3547 RM-1WV-3547-1

• Wide-Range Gas Monitor (WRGM)ODCM (SHNPP)D-l Rev.1.0 Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c No changes have been made to the Environmental Monitoring Program during this report period.

h lip 4 f', lip g'I 4 nc")'a t Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 2: Land Use Census Technical Specifications 3.12.2.a 3.12.2.b A land-use census was performed in May of 1987.Comparison with the 1986 land-use survey indicates the following changes: A.B.Milk goats were not located within the five-mile radius.Milk cows are presently located in the N and NNE sectors.These locations are commercial dairies that are currently included in the SHNPP environmental sampling program.Table 1 summarizes the location of the nearest milk animal, meat animal, residence and garden in each of the 16 compass sectors.Table 2 lists the kinds of meat animals at each meat animal location.Cattle and hogs are the predominate animals nearest the site.TABLE 1 DISTANCE TO THB NEAREST SPECIAL LOCATIONS FOR THE HARRIS NUCLEAR PROJECT (MILES)SECTOR N NNB NE BNE E ESB SE SSE S SSW SN NSW W-lQM NN EXCLUSION BOUNDARY 1.32 1.33 1.33 1.33 1.33 1.33 1.33 1.36 1.33 1.33 1.33 1.33 1.33 1.33 1.26 1.26 I.RESIDENCE 2.2 1.7 2.3 2.0 1.9 2.7 4.7 4,4 3.9 2.8 4.3 2.7 2.1 1.8 1.5 MILK ANIMAL 2.2'.6 GARDEN 2.2 1.7 2.3 4.7 2.8 4.7 3.9 2.8 4.3 3.0 2.1 3.8 1.9 MBAT ANIMAL 2.2 1.8 2.3 2.0 4.6 4.4 4.4 2.8 4.3 3.1 2.5 3.8 1.9 5/2 1//C>'r n I~.$'"~/>>~r Itff fy ff II'<<II,,I~II I'I It>I'4 It'lb'f a,>V<<f1 4>>~f frl>14)b,<<jV, tt,g 4"" II I 4 I h'I j, II>II('l)H,'Jf'Vlt n gtf>I<<lt."'l" Vf rl tl>>I f!Vg f/"'lbr'I'1'I>f 44>V I, f lbl,l I ll f"'" III-fb>'g tlf1 III,>$lt>l>~l<<)>II li I'>"." I f I~" jf<<$~If>>I ff l It'Ir~,>>$4'I (If>If>I,.v r/1>lt"~""<<V'5<<ft tfrp C>>It lb'f>1)/I)f'I t!I(fr I>VVV/~VVI'fI)b/)II II I b~f t V~~=l b lh II 4 b b Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 2: Land Use Census Technical Specifications 3.12.2.a 3.12.2.b TABLE 2 MEAT ANIMAL TYPE AT NEAREST LOCATION TO SHNPP BY SECTOR SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW DISTANCE (MILES)2.2 1.8 2.3 2.0 4.6 4,4 4,4 2.8 4.3 3.1 2.5 3.8 1.9 MEAT TYPE HOGS BEEF BEEF/GOATS RABBIT/FOWL BEEF HOGS HOGS BEEF/FOWL/GOATS HOGS RABBITS FOWL HOGS BEEF OWNER GOODWIN GUNTER JAMES REST HOME HARRIS McIVERS PATTERSON CROSS POLLARD SMITH, P.ALLEN, S.WILLIAMS STONE BRIDGES 5/3 P CN P l I f),)I Hhigi HI, (~/yCI~(,, I'~(I 5(i"ff'I ()>>)Cf" ll(t'1P~I9H<<('.'l,'IP! ), ,Cl('aP'f'..>>I((,'>f/Y.'C'H'">Cjl'l.("'f f'I HHC HICKS'l)f A'l" f';)(i'I'C"'.,Ol)~,'))'f I f HH Il 8'<"t"(8>Hl PC~, If f C*fl f E 0,'H l)/,IHH Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors out-of-service )30 Days for the Period After Receipt of Operating License (10/24/87) and Befoxe January 1, 1987 Radiation Monitor Days Inop.Reason REM-01MD-3528 Turbine Building Drains.62 Modification required to ensure monitoring of effluent stream when sump pump actuates.REM-21WL-3541 Waste Monitor Tank 39 Monitor does not correspond with analyzed results due to high sample chamber background. Investigation and procedural changes needed for determining new monitor setpoints and background subtract values.REM-1SW-3500A WPB Normal Service Water Monitor 39 Monitor in Pre-op testing.REM-1MD-3530 Tank Area Drains 39 Monitor in Pre-op testing.REM-1SW-3500B 54 RAB Normal Service Water Monitor Modification required to relocate sample line. ,f)(,,;")) rl.)UU',',-,f)),,,")1iv U'f tr"4 II 4'"IU)~44)'" ff t.'1 1)')"'l~/")"l I)')ff$'p UI)t>>tgI'v.trf, f)rt/,, v'tf ff44)vtt"Tl>>-f, I lent"lt)UIC=)f I,'11 t)4~It v"'f1/ffv I If\j i'I"')C)1/g[v))v)UIIIU'I/ l'v/'f/v haft 4)))v)U,l Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors out-of-service >30 Days For the Report Period Radiation Monitor Days Inop.Reason REM-01MD-3528 Turbine Building Drains 181 Modification required to ensure monitoring of effluent stream when sump pump actuates.REM-1WL-3540 Treated Laundry and Hot Shower 71 Monitor does not correspond with analyzed results due to high sample chamber background. Investigation and procedural changes needed for determining new monitor setpoints and background subtract values.38 Same as above REM-21WL-3541 Waste Monitor Tank 59 Monitor does not correspond with analyzed results due to high sample chamber background. Investigation and procedural changes needed for determining new monitor setpoints and background subtract values.Same as above.REM-1WS-3542 Secondary Waste Sampling Tank Monitor detector damaged by high temperature water.Modification required to provide cooling water for sample line.6/2 >)1 i I t<)I'I>I<<~<<)<>"'0,<<>"'fk';f-8,<< tg)li)ri"'"gj>>Jr>><<,'."),><<'>>>>),f">>; I t'I j~<<<<>>r)r'I))>>I'<<><<,'tf<<I<<>>)II>><)>if<<>>i>>t>)>>'>>><<>>")J))>/V>))'>,=f>II<<'"~il>lf">>>)'g>'f f"lf)fI"'I"'I I, f, I ff>>', ff>>>g>I>g>>><<<<>f I I>>>>><<p)>("~t'f'I"f=>>t')'>>)>>>>>It)*>>)>>(>>r v,<<>II,, Ir><<,ff I>t,>(rip>'pf>4>t)'iff'>)>"'r"~>>>>k)t>>I,'>,>T<<off'i g f)<<>r>r>>)>,>>,l)>f>)il I,').f>"')'~.r>t)).>,~'."',"'C)')f>>l lfl~)>>~>r<<g>>'>t'$'<<(" EI f"I'f I~f (ir)>>'J><<f J f i)*<<l)~)'>')(> >, f).'I<<>>>>'fi1"()>'Ig)r.>>if~I)><<r>l,r t>fff<<)'>f>>>r,ff>><<, lfi ii'r"'<<'<<<<r)>I<>r(>t" I'l'll'f,>'g>f~'":;1 II>>i>if)>>>>II Iv'f f<<If)i'>>>>r><<fl>><<I)f<<>~))>)>><<~'l>ll 1 iil'I>C)r"k" I<<" Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors out-of-service >30 Days for the Period After Receipt of Operating License (10/24/87) and Before January 1, 1987 Radiation Monitor RM-lAV-3509-SA Plant Vent Stack 1 FIG Days Inop.Reason Monitor in Pre-op Testing HM-lTV-3536-1 Turbine Building Stack 3A WRGM o REM-1WV-3546 WPB Vent Stack 5 PIG 66 Monitor in Pre-op Testing Monitor in Pre-op Testing REM-1WV-3547 WPB Vent Stack 5A PIG 66 Monitor in Pre-op Testing REM-1WV-3547-1 WPB Vent Stack 5A WRGM 60 Monitor in Pre-op Testing 6/3 H)l)>>"'<<W f'>>>>y IJ',.'I',W'W>>tl"">>WlWQ WW,(H">>t W}i(W h th W J I g>>>>>>)P)h>>h, W f>>,>>t,ht(H>>~v-'t>>, W>>, W'IW>>yW', I gk'I<<'<<ff}f>>>>(fr(H W>>~>>I~~>>(h y W<<WW>>.3 Wf}~W;"'I<<>>'H'I'<<>>I>>>>t<<$H"h W f'f.>>W~I'II (f h, WIH}t~i I<<>>I W hl'I'l'>>'I I Il W>>Il II,, t}'<,,>>W\'I W~<<lf<">>W't I'h~(h W H',>>t WW","'JW H,I W""C g"j<<I<<II Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors out-of-service >30 Days For the Report Period Radiation Monitor Days Inop.Reason Turbine Building 75 Stack 3A Flow Rate Monitor Flow monitoring problems due to excessive moisture in the sample lines.Modification required to install moisture control unit.WPB Vent Stack 5 Flow Rate Monitor Problems with calibration of flow control system resulting in discrepancies between actual and expected flow rates.119 Same as above.%'B Vent 181 Stack 5A Flow Rate Monitor Problems with calibration of flow control system resulting in discrepancies between actual and expected flow rates.66 Same as above. i~ii)~)i~t I','fW.(i((II" Iform'('t)'S)))<R<, If (II'," Ijl'if I, II)("(r~I'[)1+i I 2~If,<')<<)f'(,i)f II<'((~.I ASCII 1I,'" (*l Eg)a~.'f I E>fI')i)~lIi i" Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this reporting period.6/5 ~fl lI)'II I", ll ll k~'t I I I, I ll Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 6: Additional Technical Specification Responsibilities : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceed the Technical Specification limit during this reporting period.6/6 I P 4 I 4I If 44~'I 4I 4II4 4I II, I pl[1 W 4 4 f,,, II 44 v Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 Appendix 7: Major Modifications to Radwaste System Technical Specification 6.15.1 RADWASTE SOLIDIFICATION SYSTEM Functional Summer: The original design of, the Radwaste Solidification System did not provide the capability to hook up a vendor's mobile solidification system as a backup to the installed solidification system.This modification allows a vendor to hook up a mobile unit to the plant Solidification System Pretreatment Tank, Spent Resin Storage Tank, and Filter Particulate Concentrates Tank.Mobile solidification and resin dewatering services were installed in March 1987.Safety Summary: The modification was reviewed in accordance with 10 CFR 50.59 and found not to be an unreviewed safety question.The consequences of a spill of the Liquid Waste Processing System will not increase since the contents will be contained within the Waste Processing Building (WPB).The modification will not increase the inventories or sources contained in the WPB which hav'e already been analyzed.Reason for Change: Change was required due to'tartup Testing of the Radwaste Solidification System was not completed and the system was not operable.In accordance with Technical Specification 3.11.3 contract capabilities must be available when the installed Solid Radwaste System is not operable.Description: Three spool pieces were added to the inlet lines to the installed solidification system.These spool pieces allow waste to be routed to the plant solidification system or connected to lines which direct the waste to the future drum storage area located adjacent to the truck loading bay on level 261'f the Waste Processing Building.These spool pieces allow waste evaporator bottoms and chemical waste from Solidification Pretreatment Tank B, spent resin and filter particulates concentrates to be sent to a mobile solidification system and provides positive isolation between the plant solidification system and the vendor system.Service connections for service air, demineralized water, and a connection to the Waste Processing Building floor drain system is provided.Penetrations for lines from the bulk vendor chemical trailer are provided through the east wall of the truck loading bay.Vendor solidification and resin dewatering services were contracted in March 1987.These services are provided by Chem-Nuclear Systems, Inc.and are described in Topical Reports, CNSI-2-4313-01354-01-A, Mobile Cement Solidifi-cation System and CNSI-DW-11118-01-NP-A, Dewatering Control Process Contain-ers.7/1 "'>>I N"(NK h)1, IN (tf ft f<<, FN I'" I,,'tl<<ft tlf ft, t.I ff'l (1 1 Il~H*1'4.'>>)', 4 (~4'(f 1 1 lf If 5 HW 9'l<<f IH 1 It,f(<<,<<,'lf" I WPJ,1 1 4 t t'1$lfffh(1, t,', KFK 1, I'l/1 4'Uh RF I'F(fl h f,~hl g'1'N<<lt 1~K 1 4 4'll.'1'ft K t<<FI<<$';, N,,l'j(<<Nr.,'Klf(W f'I K ail WN IN 1'f<<'ifff 1'lip(1,', WNI',, j l lft<<1>>" N~I<<, I N~<<tl If<<(>>1 I It I<<<<,I'I h Flu,g~I If W ,4 K)4,>>W'tN 1"r K<<1 I'4 1'f I~K Ft h,t'K lf pl 1 1'N;KN N Flt I ff N,'~1'4 ,(Ntl I, g 1 1~H rl'1>>t.(W 1 Wt f'W*FI'., 1'f(,'>>)', ft, 1/*FF)" h ,4 Il t>>t~f I~4 I'KW.<<I 1"~J As provided in Section 4.2 of the Shearon Harris Nuclear Power Plant Process Control Program, PLP-300, the vendors Process Control Program, CNSI-SDWP-003, is being used to establish processing conditions assuring safe and effective solidification of waste.10 CFR 61 Waste Form Certification Testing has been completed by Chem-Nuclear System, Inc.and is contained in Topical Report CNSI-WF-Ol-NP. Solidification and dewatering is being performed under the direction and supervision of a Radwaste Shiit Foreman by the vendor's trained operator using vendor's approved procedures. ~uuantit of Solid Waste: Based on the solid waste processing system inputs given in the FSAR Table 11.4.1-1, the projected quantity of solid waste that will be generated using the vendor's service is as follows: Source Spent Resin Evaporator Bottoms Filter Particulates Dry Solids Chemical Drains Form Dewatered Solidified Solidified Compressed Solidified Quantity cu.ft.gyr 1,840 (1)10,894 (2)2,733 (2)2',000 (3)190 Q2}"17,567 Quantity 195 cu.ft.100 cu.ft.liners boxes 9 53 13 20 20 Notes: (Bases for values)(1)Based on 180 cubic feet of resin in a 195 cubic foot liner with a burial volume of 205 cubic feet.High integrity containers (HIC)may be used as required.(2)Based on 135 cubic feet of waste in a 195 cubic foot liner with a burial volume of 205 cubic feet.(3)Based on a 6 to 1 volume reduction using a vendor's super compactor ser vice.Exposure to a Member of the Public: No exposure to a member of the public in an unrestricted area different from those previously estimated in the License application is expected from use of the vendor's solidification/dewatering service.Ex~ected~Actual Waste Generated: During the period of March 1987 through June 1987 expected and actual waste generated is given below.Prior to March 1987 no solid waste was generated. Source Spent Resin Evaporator Bottoms Filter Particulates Chemical Drains Form Dewatered Solidified Solidified Solidified Expected(l) cu.ft.460 2,701 683 48 3, 892 Generated cu.ft.205 1,845 0 0 2,050 7/2 ~<<It><<f)l>>'<>>lf ff>>r>>~!>>r'fl H.f>>>>ri', H<<4 I f,>'>>f r'<>)M I*I>><<"I H'll H W>')1'>>>li[I'>il<<'I'I H>>>1!H'I H 4 Uf f'HH<<>IK~H>r l H>>f" 4 j)t~f r<<.I'Hf(I'f.j,,>If,f;,,~,>>,,<<W>., I;f)>H f>>r<<>>I I ir>>I'<<ff=, r I'r g<<f';H ff I.f<<>>f ('tf>>,l>>>fi'"'f r>>'r*.H."'tl'E r>>~II>'I,<<)f I!Ill I'<<H.fr r'r.,,r f>>H, I<<<<ig lf<<~"'H'<<HI'>>~r>I II ,~I'<<W S"><<t"rf-'if!r>!<<fj'f>PW)<<r'<<>>W II f I'I ff I(VII ,)f,)>><<lf'H P,<<'<<Iaf><<<<'t f f>>I Hf I'I 4<<-ff>~Hff I>>>>I>>"'l" f I 4 p'I<<)<<I, f>>>>ffl<<4~f>)rl vf>>r,!J'I'.>>HI If H>>i<<f I f f(ff<<If, I I>'l ff<<I'<<t I,<<.)f<<.f I<<r)w)'ff>>$<<>I>>I)I r j AH II I fir<<>>'>il'W>>r~t>>!II>>~I I'I I<<>>>>'>I'f I'll 4 H If>>>'ff<<Wr<>>>y.p)<<, fl>>>>)7 I>>",I I I>>'I H Notes: (1)-o One third of the yearly value given in Quantity of Solid Waste.Exposure Plant~0 crating Personnel: It is estimated that exposure to plant operating personnel may increase by 0.5 man-rem due to the use of vendor solidification service.Safety and Technical Reviews: Documented safety and technical review in accordance with Technical Specification 6.5.1 have been completed for this modification. nnnnn 7/3 t'P"~-l'l ,I c ll~'I N t , N K II}}