Text

Draft Radiological Effluent Technical Specifications for Pwrs
	ML20069N044
Person / Time
Issue date:	03/31/1979
From:	; NRC
To:	;
References
	NUREG-0472, NUREG-0472-DFT, NUREG-0472-R03-DRFT, NUREG-472, NUREG-472-DFT, NUREG-472-R3-DRFT, NUDOCS 8212020141
	Download: ML20069N044 (76)
	v • d • e

{{#Wiki_filter:. e 1 ..i 6%f.- f ~ ,7,,n.p u elsa t( NUREG-0472 wet "" $' ' g,576 k g g,,,,.0 steu'-l DRAFT RADIOLOGICAL EFFLUENT j TECliNICAL SPECIFICATIONS FOR PWR'S d l l l l s y Revision 3 Ma rch 1979 8212O20141 790331 ~ PDR NUREQ 0472 R PDR I

7-o 7 l.0 DEFINITIONS ( DEFINED TERMS 1.1 The DEFINED TEPJ1S of this section appar'in capitalized type and are applicable throughout these Technical Specifications.* OPERABLE - OPERABIllTY 1.6 A system, subsystem, train, ccaponent or device shall be OPERABLE or have OPERARILITY when it is capable of perfonning its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, nonnal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equip-ment, that are requi red for the system, subsystem, train, component or device to perfonn its functions (s), are also capable of perfonning their t-E related support functions (s). {_ - C11ANNEL CALIBRATION 1.9 A CliANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The C11ANNEL CALIBRATION shall encompass the entire channel including the sensor and alann and/or trip functions, and shall include the Cl!ANNEL FUNCTIOFAL TEST. The CHANNEL CALIBRATION may be perfonned by any series of sequential, over-p= lapping or total channel steps such that the enti re channel is calibrated. CHANNEL CilECK i 5 1.10 A CHANNEL CitECK shall be the qualitative assessment of channel be-u havior during operation by observation. This detennination shall include, -t where possible, comparison of the channel indication and/or status with other irdications and/or status derived from independent instrumentation channels measuring the same parameter. CliANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCfl0NAL TEST shall be: a. Analog channels - the injection of a simulated signal into a the channel as close to the sensor as practicable to verify r OPERABILITY including alann and/or trip functions.

See NUREG-0212, NUREG-0103 and NUREG-0452 " Standard Technical Speci fications for PWR's".

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b 1.0 DEFINITIONS (Continued) b. Histable channels - the injection of a simulated signal into the sensor to verify 0PERARILITY including alann and/or trip functions. _ DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factort used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." TURCE_OlECV, 1.29 A TURCE OlECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. PROCESS CONTROL PROGRAM (PCP) Ah 1.30 A PROCESS C0i'TR0L PROGPAM s hall contain3 sampling, analysis, and for-nulation detennination by whi;h TLIDIFICATION of radioactive wastes from liquid systems is assured. mLIDIFICAT IOP 1.31 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid s.) stems to a homogeneous (0nifonnly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing). OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.32 The OFFSITE DDSE C/LCULATION idANUAL s hall contain the methodology and parameters ised in the calculation of offsite doses due to radio-active gascots and liquid effluents and in the calculation of gaseous and liquid effl uent monitoring instrumentation alann/ trip setpoints. PWR-SfS-1 1-2 jn_3; I : ; L [_ / ; ^ } - [. } :l J [ _j ~} ;

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7 1.0 DEFINI TIONS*(Continued) GASEOUS RADWASTE TREATMENT SYSTEM 1.33 A GASEOUS RADWASTE TREATHENT SYSTEM is any systm dts igned and in-stalled to rafuce radioactive gaseous effluents by collecting primary coolant systs offgases fra the primary systs and providing for delay or holdup for the purpose of reducing the total radioactivity prior to rel ease to the envirorment. VENTILATION EXHAUST TREATi;ENT SYSTEM 1.34 A VENTILATION EXHAUST TREAINENT SYSTEM is any sjstem dcs igned and irstalled to reduce gaseous radiciodine or radioactive material in parti-culate fann in offluents by passing ventilation or vent exhaist gases through charcoal adsorbers and/or HEPA filters for the purpose of rmoving iodines or particulatcs fra the gascots exhaist stream prior to the rel ease to the envirorment (s uch a s3s tom is not cors idered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric clcanup sys tens are not corsidered to be VENTILATION EXHAUST TREAINENT SYSTEM components. PURGE - PURGING l.35 PURGE or PURGING is the controlled proc (ss of discharging air or gas from a confircaent to maintain temperature, prcss ure, humidity, concentra-tion or other cperating condition, in such a manner that rcplacment air or gas is required to purify the confinement. VENTI NG l.36 VENTING is the controlled proc (ss of discharging air or gas from a confinement to maintain tmperature, pr(ssure, humidity, concentration or other operating condition, in such a manner that replacment air or gas is not provided or required during VENTING. Vent, ts ed in sys tem namcs, dots not imply a VENTING proccss. ~ Y PWR-STS-1 1-3

{ TAPLE 1.2 ~" ~ FRE0llENCY NOTATION NOTATION FREPUfNCY S At least once per 12 hours D At least once per ?4 hours. W At least once per 7 days. M ' At least once per 31 day. Q At least once per 92 days. SA At least once per 184 dag. R AT least once per 18 montis. S/ll Prior to each reactor startup. P Completed Prior to each relcase. N. A. Not applicable. a y PWR-STS-1 1-4 i i

l INSTRUMENTATION "- RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 1 9 U-3.3.3 5 The radioactive li id effluent monitoring instrumentation channels shown in Table 3.3-shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alam/ trip setpoints of these channels shall be de-tennined in acconiance with the Offsite Dose calculation Manual (0DCM). APPLICABILITY: At all times. ACTION: l With a radioactive liquid effluent monitoring instrumentation a. channel alann/ trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. b. With one or more radioactive liquid effluent monitoring in, strumentation channels inoperable, take the ACTION shown in Tabl e 3. 3-pl. le c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfonnance of the Cl{ANNEL CliECK, SOURCE CliECK, CllANNEL CALIBRATION, and CliANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-Jf. n- ~ Y C'l PWR-STS-1 3/4 3-j4' . ;.} ; ;.' ;._<:'[' x -- i e i..; - - W ; ; .cs. s '.= n,~.; 7 ^ ;~ ; '

TABLE 3.3-H' M 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l i 1 MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1. Gross Radioactivity Monitors Providing Automatic Termination of Release a. Liquio Radwaste Effluent Line (1) 18-2Y b. Stec: Generator Blowdown (1) M NJ Effluent Line c. Turbine Building (Floor Drains) (1) JO So Sumps Effluent Line a s "2. Gross Racioactivity Monitors-j Not Providing Automatic Termination of Release a., a. Service Water System Effluent Line (1) 30 ic b. Component Cooling Water System Effluent Line (1) JB3C ( (e> i b

TABLE 3.3.I$'(Continued) a = 4 RADI0 ACTIVE LIQUID EFFLUENT XCNITORING INSTRUMENTATION k l P MINIMUM i CHANNELS 'NSTRUMENT OPERABLE ACTION Flow Rate Measurement Devices l c. Liquid Radwaste Effluent Line (1) jMr 3/ l b. Discharge Canal (1) 2f 3/ c. Steam Generator Qlowdown Effluent (1) ,31 S/ Line Radioactivity Recorders (*) a. Liquid Radwaste Effluent Line (1) 23 55 b. Steam Generator Blowdown Effluent Line (k) j24 yf

i. Tank Level Indicating Devices (for tanks outside plant buildings) a.

(1) JMI 31 b. (1) y yg c. (1) 45! 3L d. (1) JFI ~32. (*Rcquired only if alarm / trip set point is based on recorder-controller) ,/~*% I k \\b s e-e

12 TABLE 3.3-1f (Continued) l RADI0 ACTIVE LIQUID EFFLUENT XONITORING INSTRUXENTATION MINIXUM CHANNELS INSTRUME.\\T OPERABLE ACTION 3. Continuous Composite Samplers and Sampler Flow Monitor a. SteamGenerator,plowdown (1) ,18' 2'/ cffluent Line b. Turbine Building Sumps Effluent (1) 20' 50 Line i 4; tur ? ~ s s- .m

TABLE 3.3-Fl

)

~ (Continued)> l o TABLE NOTATION 23 ~ ACTION )6 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirunent, effluent relcases may con-tinue for up to 14 days, provided that prior to initiating a release: 1. At least two independent samples are analyzed in acconiance with Specification 4.11.1.1.3, and; 2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving. Othenvise, suspend release of radioactive effluents via this pa thway. Si ACT10N J9 With the number of channels OPERABLE less than required by The Minimum Channels OPERABLE requi ranent, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radica detection of at least 10 ptivity (beta or gamma) at a limit of jiCi/ gram; 1. At least once per 8 hours when the specific activity of the secondary coolant is > 0.01 jiCi/ gram DOSE EQllIVALENT I-131. 2. At least once per 24 hours when the specific activity of the secondary coolant is < 0.01 ;iCi/ gram DOSE EQllIVALErvT I-131. FC ACTION.20'With the numbers of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requi ronent, effluent releases via this pathway may continue for up to 30 days provided that at least once per 8 hours grab samples are collected and analyzed for gross at least 10-b(ici/ml. radioactivi t beta or gamma) at a lower limit of detection of 31 ACT10Nfl With the number of channels OPERABLE less than requi red by the Minimum Channels OPERABLE requiranent, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate f~l ow. Tk ACTION F2 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requi rment,1iquid additions to this tank may opntinue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank. ACTION 2-3 Wi th the number of channels OPERABLE less than requi red by the Minimum Channels OPERABLE requi rement, effluent releases via the affected pathway may continue for up to 14 days provided the gross radioactivity Ievel is detemined at 1 cast once per 4 hours during actual release. PWR-STS-1 3/4 3 JAT 5-M

TABLE 3 3 fi O l-(Continued)- l TABLE t0TATION ACTIONJ4 With the number of channels OPEP.APLE less than required by the Minimum Channels OPERABLE requircnent, effluent releases via the affected pathway may continue for up to 30 days provided the gross. radioactivity level is detennined at least once per 4 hours during actual release. e e PWR-STS-1 3/4 3-

o $ 9* m TABLE 4.3-}Y Ei 6, RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Gi A. CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECX CHECX CALIBRATION TEST 1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Auto-matic Isolation a. LiquidTRadwaste Effluents Line D P R(3) Q(1) b. Steam Generator Blowdown Effluent D M R(3) Q(1) Line c. Turbine Building (Floor Drains) D M R(3) Q(1) Sumps Effluent Line R a 2. Gross Beta or Gamma Radioactivity ?> Monitors Providing Alarm But Not igte Providing Automatic Isolation a. Service Water System Effluent Line D M R(3) Q(2) b. Component Cooling System Effluent D M R(3) Q(2) Line 3. Continuous Composite Samplers and Sample Flow Measurement Device a. Steam Generator Blowdown Effluent 0 N/A R Q Line b. Turbine Building Sumps Effluent D N/A R Q Line O e e --e

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J r TABLE 4.3-11 (Conti nued) # TABLE NOTATION

During liquid additions to the tank.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control mom alarm annunciation occurs i f a ny o f t he fol 1 owi ng condi ti o ns ex i st : 1. Instrunent indicates neasured levels above the alarm / trip setpoint. 2. Ci rcui t fail ure. 3. Instrument indicates a dcwnscal e failure. 4. Inst rument control s not set i n operate mode. (2) The CHANNEL FUNC TIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the followi ng coaditions exi st: 1. Inst rument i ndicates measured l evel s above the al a rm/t ri p setpoint. 2. Ci rc ui t fa il u re. 3. Inst rument i ndicates a downscal e fail ure. 4. Inst runent cont rol s not' set i n operate node. (3) The initial CHANNFL CALIBRATION shall be perfonned using one or more of the reference standards certi fied by the National Bureau of Stan-dards or. usi ng standards that have been obtained f rom suppliers that pa rtici pate i n measurcr.ent assurance activi ti es wi th NP S. These standards shall penait calibrating the system over its intended range of energy and measurment range. For subsequent CHANNFL CALIPRATION, sources that have been related to the initial calibration shall be tion [. (Exist-img plants may substitute previously establi shed calib ra-used rocedures for thi s requi rment.) Sw., b (4) CH/JML CHI CK shall consi st of veri fyiog indication of fl ow during periods of rel ease. CHANNFL CHICK shall be rade at least once daily on any day on which conti nuous, periodic, o r ha t ch rel ea ses a re i :a d e. l$ n!R - S I S-1 3/4 3 M

INSTRuliENT ATION RADI0 ACTIVE GASEOUS EFFLUENT lONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION to f r3 3.3.3.9' The radioactive gasbots effluent monitoring instrumentation channels shown in Table 3.3-J2 shall be OPERABLE with their alann/ trip setpoints set to ensure that the limits of fpecification 3.11.2.1 are not exceeded. The alann/ trip setpoints of these channels shall be detennined in ~acconiance with the ODCM. 13 APPLICABILITY: As s hown in Table 3.3-12. ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alann/ trip setpoint less conservative than required by the above specification immediately suspend the release of radio-active gaseous effluents monitored by the affected channel or declare the channel inoperable. b. With one or more radioactive gaseous effluent monitcring instru-1 mentation channels inoperchle, take the ACTION s hown in Tabl e 3.3-yl. 8 The provisions of $pecifications 3.0.3 and 3.0.4 are not appl f-c. cabl e. SURVEILLANCE REQUIREMENTS 16 4.3.3.7 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfonnance of the 01ANNEL CitECK, SluRCE CllECK, 01ANNEL CALIBRATION, and GiANNEL FUNCTIONAL TEST operations dur4ng the-MME-S-and at the frequencies shown in Table 4.3-F. Ib W P 73 Pwa-si s-1 3/4 3=53 - Y'

TABLE 3.3-l( yg l a RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION G ,L MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY 1 ACTION 1. Waste Gas Holcup System a. Noble Gas Activity Monitor (1) Xf Sb b. Iodine & ampler (1) y/ c. Particulate Sampler (1) 23g/ g d. Effluent System Flow Rate (1) Measuring Device yg a 42 u, di g-Sampler Flow Rate Measuring (1) e. vevice .3 p5f. 2A. Waste Gas Holdup System Explos'.m Gas Monitoring System (for systems designed to' withstand the effects of a hydrogen explosion) a. Hydrogen Monitor (1) yjy pj b. Hydrogen or Oxygen Monitor (1) 7 77 p

15 TABLE 3.3-H (Continued) I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION h h MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 23. Waste Gas Holdup System Explosive Gas Monitoring System (for systems not designed to withstand the effects of a . hydrogen expigsion). a. Hydrogen Monitor (2) 37 @ b. Hydrogen or 0.<ygen Monitor' (2) )& 90 3. Containment Purge Monitoring System .~ 1B 58 a. Noole Gas Activity Monitor (1) o, 4 b. Iodine Sampler (1) JT g/ i 4. c. Particulate Sampler (1) Jr 9/ d. Effluent System Flow Rate (1) JF % Measuring Device e. Sampler Flow Rate Measuring (1) JF E Device

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' _ _,....,,,,.a. :, -.. ->~ y. .yy_, : + ..y _. ~. - , _ '. :p v . s* e ,.( l TABLE 3.3.1 (continued) I j RADI0 ACTIVE GASEGUS EFFLUENT MONITORING INSTRUMENTATION ^ aG MINIMUM e ~ CHANNELS INSTRUXENT OPERABLE APPLICABILITY ACTION 4. (See list below) a. Noble Gas Activity ( gonitor (1) .2787 Ji M/ b. Iodine Sampler (1) c. Particulate Sampler b d. Effluent System Flow 5 Rate Measuring Device (1) ,26 56 Y e. Sampler Flow Rate Measuring Device (1) 26 5(- %wu [1] Condenser Evacuation System [2] Vent Header System [3] Auxiliary Building Ventilation System [4] Fuel Storage Area (Building) Ventilation System [5] Radwaste Area Ventilation System [6] Sceam Generator Blowdown Vent System 5

is f/ TABLE 3.3-P2 (Centinued)d ~ TABLE NOTATION

At all times.
- During waste gas holdup system operation (treatment for primary system offgases).

36 ACTIONJJr With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requiranent, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release: 1. At least two independent samples of the tank's contents are analyzed, and 2. At least two technically qualified monbers of the facility Staff independently verify the release rate calculations and discharge valve lineup; Othentise, suspend release of radioative effluents via this pa thway. 4 ACTION,2ff With the number of channels OPERABLE 1ess than requi red by the Minimum Channels OPERABLE requi renent, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. 37 ACTION.,N With the number of channels OPERABLE 1ess than requi red by the Minimum Channels OPERABLE requi rement, effluent rel eases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. ACTION With the number of channels OPERABLE 1ess than requi red by the Minimum Channels OPERABLE requi renent, immediately suspend PURGING of radioactive effluents via this pathway. M ACTIONJ1 With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requi raaent, operation of the waste gas holdup system may continue for up to 30 days provided grab samples are collected at least once per 4 hours and analyzed within the next 4 hours. ACTION )if With the nYmber of channels OPERABLE one less than requi red by the Minimum Channels OPERABLE requi renent, operation of this system may continue for up to 14 days. With (two) channels in-operable, be in at least HOT STANDBY within 6 hours. PWR-STS-1 3/4 JJsT 3-1/

n

TABLE 3.3-O (Continued)d TABLE 110TATION 4I ACTION)1 With the number of channels OPERABLE less than requi red by the Minimum Channels OPEPABLE requirement, effluent releases via this pathway may continue for up to 30 days, provided samples are continuously collected with auxiliary sampling equipnent as requi red in Table 4.11-2. k 9 e M I - 78 PWR-STS-1 3/4 # .y59^ y w w.-4 5i:. .;.;yJ. m.;cr.c f. w v e u :;.:.a;: w.L.~.c 1;; p a e y

TABLE 4.3-W 2 ? RADI0 ACTIVE GASEGUS EFFLUENT MONITORING INSTRUMENTATION

RVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH!

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1. Waste Gas-Holdup System a. Noble Gas Activity Mur.itor P P R(3) Q(1) b. Iodine Sampler W N/A N/A N/A c. Particulate Sampler W N/A N/A N/A d. System Effluent Flow Rate P N/A R Q Measuring Device c. Sampler Flow Rate Measuring D N/A R Q R ^ 2. Waste Gas Holdup System Explosive l " 9:. Gas Monitoring System i IlM a. Hydrogen Monitor D N/A Q(4) M b. Hydrogen Monitor (alternate) D N/A Q(4) M yg c. Oxygen Monitor D N/A Q(5) M D d. Oxygen Monitor (alternate) D N/A Q(5) M

TABLE 4.3-1 (Continued) g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLAdCE REQUIREMENTS 3 1,5 CHANNEL MODES IN WHICH T CHANNEL SOURCE. CHANNEL FUNCTIONAL SURVEILLANCE' ~ INSTRUXENT CHECK CHECK CALIBRATION TEST REQUIRED 3. Containment Purge Vent System

a. Noble Gas Activity Monitor D

P R(3) Q(1) n

b. Iodine Sampler W

N/A N/A N/A h

c. Particulate Sampler W

N/A N/A N/A

d. System Effluent Flow Rate D

N/A R Q 7 Measuring Device _E$

e. Sampler Flow Rate Measuring D

N/A R Q E Device E S' T-E 8a r-Q r T L. L ,= k = E r (

13 TABLE 4.3.Pl(Continuedl l 3 RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS h HANNEL SOURCE CHANNEL CHANNEL FUNCTIONAL - MODES IN WHIC '1NSTRUMEN ' T CHECK CHECK CALIBRATION TEST SURVEILLANCE ~ REQUIRED 4 (see list below) a. Noble Gas Activity Monitor D M R(3) Q(2) b. Iodine Sampler W N.A. N.A. N.A. c. Particulate Sampler W N.A. N.A. N.A. d. System Effluent Flow Rate Measurement Device D N.A. R 'Q e. Sampler Flow Rate Measurement Device D N.A. R Q R a [1] Condenser Evacuation System h [2] Vent Header System sg [3] Auxili'.ry Buildic.1 Ventilatio n System [4] Fue' Storage Area (Building) Ventilation System [5] Radwaste Area Ventilation System [6] Steam Generator Blowdown Vent System 9 9

TABLE 4.3-1-2 4 _. ) (Continued) TABLE NOTATION

At all tin.,
- During waste gas holdup system operation (treatment for primary system offgases).

(1) The CHANNEL FUNCTIONAL TEST shall also denonstrate that automatic isolation of this pathway and control room alam annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alam/ trip setpoi nt. 2. Ci rcuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (?) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room ~ alann annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alam/ trip setpoint. 2. Ci rcuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (3) The initial CHANNEL CAliRRATION shall be perfomed using one or more of the reference standards certified by the National Bureau of Stan-dards or-using standards that have been obtained from suppliers that participate in measuranent assurance activities with NRS. These standanis shall permit calibrating the system over its intended range of energy and measuraaent range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (E-xist4ag plants may substitute previously established calibra-tion procedures for this requi rment.) p $% h.., 3*32 PWR-STS-1 3/4 34r-~3-6-f

na TABLE 4.3-P2 [) (Continued) # (4) The CIMNNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. One volume pertent hydrogen, balance nitrogen; and 2. Four volume percent hydrogen, balance nitrogen. (5) The CIMNNEL CALIBRATION s hall include the use of standard gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen; and 2. Four volume percent oxygen, balance nitrogen. e J 3-$3 PWR-STS-1 3/4 34f3-3~

I 3/4.11, RAD 10 ACTIVE EFFl.UENT S 3/4.11.1 LIQUID EFFLUErd S CONCENT RAT 10N LIMITING CONDITION FOR OPERATION 3.11.1.1 T he concentration of radioactive material rel eased f rom tAe s i te (see Figura 5.1-4) s hall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other gases, the concentration s hall be limited to P x 10 pd or entrained noble than dissolved or entrained noble gases. For dissolv pCi/ml total ac tiv ity. APPL I CABILIT Y: At all t im es. ACT 10t!: With the concentration of radioactive material rel eased f rom t he s i te exceeding the ab ove l imi ts immedia tely res tore conc entration wi thin t he ab ov e l im i ts. f }{ y 4 SU Ry_t II L ANC_E_ _R_FQU_l PE f(Nf S___ _ _ _ 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid was te s hall be detennined prior to rel ease by samplina and analys is in acconiance wi th Tabl e 4.11-1. T he res ul ts of pre-rel ease analyses s hall b e us ed wi t h t he c al cul a t io nal re t hods i n the ODCri to ess ure tha t tFe cor,- centr 2 tion at the point of rel e se is m aint eined within the l imits of Sp ec i fic at io n 3.11.1.1. 4.11.1.1.2 Pos t-rel ecs e an alys es of s cnpl es coiipos ited f rom b atc h rel e,s es s h al l b e pe rf o rrsi in ccr o ni anc e wi t h T chl e 4.11-1. T he res ul ts of the prev ious pos t-rel e<se an alys es s hall b e us ed wi th the c al cul ation al l methods in the ODCM to msure that the concentrations at the point of re-l eis e were n aint ained wi thin the l imits of Specific ation 3.11.1.1. 4ti t,l.3

u. ( a we,d gt

) l .I V PWR-S!S-1 3/4 11-1 i -m-- um um um um i

6 SURVEILLANCE RE0b REMENTS (Continued) 4.11.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be detennined by collection and analysis of samples in acconiance with Table 4.11-1. The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1. c e fr.r,L.h IC [kGGd PURpSTW1 pgg

lisle 4. ll-D ~ ,RADI0 ACTIVE LIQUID WASTE SAMPLit!G Arid At!ALYSIS PROGRAM .~. Lower Limit' Sampling Minimum Type of Activity of Detection Liquid Release Type Frequency Analysis Analysis (LLD) Frequency (uci/ml)a P P A. Batch Waste Re-Each Batch Each Batch Principal Gamma 5 x 10-7 lease Tanksd Emittersf I-131 1 x 10-6 p Dissolved and Entrained Gases 1 x 10-5 One Batch /M M (Gamma Emitters) 1 x 10-5 P H-3 Each Batch N b Cpmpesite Gross alpha 1 x 10-7 P-32 1 x 10-6 7 Each Batch Q b Composite Fe-55 1 x 10-6 c B. Plant Continuous Continuous W Principal Gamma 5 x 10-7 Releases. Composite Emitters f / e c I-131 1 x 10-6 Dissolved and M Entrained Gases Grab Sample li (Gamma Emitters) 1 x 10-5 c Continuous M c Composite Gross alpha 1 x 10-7 P-32 1 x 10-6 Continuous 0 Sr-89, Sr-90 5 x 10-8 c c Composite Fe-55 1 x 10 -6 i 11-f' Ph'R-STS 3/4

TABLE 4.11-1 (Continued) TAP.LE fl0TATION + a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5". probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical ' sepa ration): 4.66 s LLD = b E V 2Tf2. Y. exp(~TAtJ where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standani deviation of the background counting rate or of gthe counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transJonnation) V is the sample size (in units of mass or volume) 2.22 is the number of transfonnations per minute per picocurie Y is the fractional & chemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide At is the clapsed time bet $ ween midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of sb used in the calculat' on of the LLD for a detec-i tion system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted va riance. In calculating the LLD for a radionuclide de-ternined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the sampi es. Typical values of E, V, Y, at shall be used in the cal cul ati on..The background count rate is calculated from the back-ground counts that are detennined to be within + one FWHM (Full-Width-Half-itaximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. 3 PWR-STS-1 3/4 11-4'

y pe

. 3 j. y.( y;.;_::3, y_y;3 3.3 3 _;p; y y_.3.;;; s.3;9.; g 3 y; g,y,

TABLE 4.11-1 (Continued) TABLE NOTATION b. A composite sumple is one in which the quantity of liquid sampled is proportional to the quantity of liquid vaste discharged and in which 2 the method of sampling employed results in a specimen which is repre-sentative of the liquids released. c.. To be representative of the quantities and concentrations of radio-active materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to he representa-s tive of the effluent release. d. A batch release is the discharge of liquid wastes of a discrete vol ume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling. e. A continuous release is the discharge cf liquid wastes of a non-di sc rete volume; e.g., from a volume of system that has an input p flow during the continuous release. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclider: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Cc-141, and Cc-144. Thi s li st E does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the aboy? nuclides, shall also be identi fied and reported. Nuclides which are aelow the LLD for the analyses shall be reported as "less than" the nuc'ide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in tS.e requi red dose cal culations. -m r V = 4 + Ph'R-ST S-1 3/4 ll-F

RADI0 ACTIVE EFFLUENTS DO SE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from raficactive materials in liquid effluents released from the site (see Figure 5.1-4) shall be limited: a. During any calendar quarter: 11.5 mrm to the total body and i 5 mran to any organ, and b. During any calendar year: 13 mrom to the total body and i 10 mran to any organ. APPLICABILITY: At all times. ACTION: a. With the calcul ated dose from the. release of raiioactive materials in liquid effluents exceeding any of the sove limits, in lieu of any other report required by Secification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Secifica-tion 6.9.2, a Secial Report which identifies the cause(s) for exceeding the limit (s-) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the renainder of the current calendar quarter and during the sibsequent three calendar quarters'so that the cumul a-tive dose or dose conmitment to an individual from such releases during these four calendar quarters is within 3 mran to the total body and 10 mran to any organ. (This Special Report shall also include (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requironents of 40 CFR 141, Safe Drinking Water Act.*) b. The provisions of Specifications 3.0.3 and 3.0.4 are not applichle. SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calcul ations. Cumul ative dose contributions from liquid effluents stall be detennined in acconiance with the ODCf' at least once pe r 31 days. Y

Applichle only if drinking water supply is taken from the receiving water body.

S PWR-ST S-1 3/4 Il-f

.t RADI0 ACTIVE EFF1UENTS LIOUID WASTE TREATMENT LIMITIlG CDNDITION FOR OPERATION da6 3.11.1.3 The liquid radwaste treatment system shall he OPERAPLE. The/N w system shall be used to reduce the radioactive materials in liquid wastes 'eg2/a prior to their discharge when the projected dose due to liquid effluent fran the site (see Figure 5.1-4) when averaged over 31 days would exceed 0.06 mran to the total body or 0.2 mran to any onjan. APPLICABILITY: At all times. ACTION: a. With the liquid radwaste system inoper*le for more than 31 days or with raficactive liquid waste being discharged without treat-ment and in excess of the bove limits, in lieu of any other report required by Secification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Secification 6.9.2, a Secial Report which includes the following infonnation: 1. Identification of the inoperble equipment or subsystems and the reason for inoperbility. 2. Action (s) taken to restore the inoper61e equipment to OPERABLE s tatus. 3. Summary description of action (s) taken to prevent a recurrence. b. The provisions of Secifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accortlance with the ODCM. 4.11.1.3.2 The 1iquid radwaste treatment system shall be danonstrated OPERABLE by operating the liquid radwaste treatment sys tem equipment for at 1 eas t minutes.sonce per 92 days un1ess the 1iquid radwaste system has been utilized to' process radioactive liquid effluents during the pre-vious 92 days. y u.l b Y y PWR-51 S-1 3/411-/ l

n ' RADIO. ACTIVE EFFLUENT S LIQUID 110LDUP TAth'S* ~ ~ LIMITING CONDITION FOR OPERATION 3.11.1.4[The quantity of radioactive material contained in each of the - dissolved or entrained noble gases. @ following tanks shall be limited to curies, excluding tritium and a. b. 6 c. d, o u z a.L.. h pe u 9A h. APPLICABILITY: At all times. ACTION: a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hrs reduce the tank contents to within the limit. The ;;ritten fol4cw-w rt s hal l inehde-a-sehedul-e-and-deseeipt-ion-of-eet-iv+t-ies-pl,3nned-and/o r-taken-to-reduee-the-ta nh-con ten ts-to-w i-th i n-the - -atreve-1-imi t* b. The provisions of Secifications 3.0.3 and 3.0.4 are not appl icabl e. SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be detennined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. T Tanks included in this Fpecification are those outdoor tanks that are not surrounded bygliners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and drains connected to y the liquid radwaste treatment system.)w t wa:u.nd. ay wn.. PWR-STS-1 3/4 11-Jr

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUEfff S DOSE RATE LIMITING C0f DITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents fran the site (see Figure 5.1-3) shall be limited to the following: a. For noble gases: < 500 mran/yr to the total btdy and i 3000 mran/yr to the skin, and b. For all radioiodines and for all radioactive materials in parti-culate form and radionuclides (other than noble gases) with half lives greater than 8 days : 11500 mran/yr to any organ. APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be detennined to be within the above limits in acconlance with the methods and procedures of the ODCM. s s 4.11.2.1.4 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be detennined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in acconiance with the sampl.ing and analysis progran, specified in Table 4.11-2. 3 Pl!R-ST S-1 3/411_f

TABLE 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM 7 Sampling Aa s Type of e et L D)' j,aseous Re, tease type Fraquency Frequency Activity Analysis ( Ci/ml)a 7;. ,u P P A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emittersg 1 x in-4 sank Gra6 l Sample i P P b l B. Containment Porge Each Purge Each Purge Prin_cipal Gamma Emit _ters9 1 x 10-4 Grab H-3 1 x 10-6 j Sample C. (List other release db, e, c g Principal Gamma Emit _ters9 1 x 10-4 b points where gaseous Grab effluents are dis-

Sample H-3 1 x 10-6 j

charged from the fa-y cility, e.g. air I ejector, steam gener ' ,_L - , ator flash yent, e-h _1 ! cuipment vents, ven-tilation e_xhausts. etd. 3 D. D. All Release Types Continuous W I-131 l' x 10-12 4, as listed in A, B, Charcoal e C above. Sample I-133 1 x 10-10 f d i Continuous W 9 Particulate Principal Gamma Emitters Sampl e_ (I-131, Others) 1 x 10-II Continuous M Gross alpha 1 x 10-" Composite Particulate Sampie f Continuous Q Sr-89, Sr-90 1 x 10-U Composite Particulate Sample } Continuo,us, ; Noble Gas Gross Noble Gases i x 10-6 t h h venunr Pn+n & An -

TABLE 4.11-2 (Ccntinued) ~ TABLE NOTATION a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95", probability with 5', probability _ of falsely concluding that a blank observation represents a "real" signal. For a particular measurment system (which may include radiochemical sepa ration): 4.66 s LLD = b E V 2.22 + Y exp(-AAt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s b s the standard deviation of the background counting rate or of i the counting rate of a blank sample as appropriate (as counts per . minute) E is the counting efficiency (as counts per transfonnation) V is the sample size (in units of mass or volume) 2.22 is the number of transfonnation per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide At is the elapsed time between midpoint of. sampie collection and time of counting (for plant effluents, not environmental sampies). The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically prc-dicted variance. In calculating the LLD for a radionuclide deter-mined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the sampl es. Typical values of E, V, Y and At shall be used in the calculation. VThe background count rate is calculated from the background counts that are detennined to be within + one Fk!HM (Full-Hidth-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. 1 PWR-STS-1 3/4 M d C //N I )

r T Aft.E 4.11-2 (Continued) TABLE t0TATION

b.. Analyses shall also be perfonned following shutdown, startup, or similar operational occurrence which could alter the mixture of radf unuclides.

'c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. d. Samples shall be changed at least once per 7 days and analyhes shall ' be coupleted within 48 hours after charging (or after removal from sampl er). Sampling, and analyses shall also be perfonned at least once per 24 hours for at least 7 days following each shutdown, startup or thennal power level change exceeding 15". of fsted tTiennaTTdiTe~r; in one hour. k' hen samples collected for 24 hours are analyzed,'the cor-responding LLD's may be increased by a factor of 10. m a4' c.:pu)

e.. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3. g. The principal gamma anitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xc-133m, Xc-135, and Xe-138 for gasects emissions and l'.n-54, fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Cc-141 and Ce-144 for particulate emissiois. Th'is list does not mean that only these nuc-lides are to be detected and reported. Other peaks which are measur-able and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be ised in the required dose calcula-t ions. h. The noble gas continuous monitor shall be calib rated tsing laboratory anabses of the grab samples fran A-and-B on Table 4.11-2. 4 34ndd y 3/4 11--p[i l PWR-STS-1

RADIDACTIVE EFFLUChiS DOSE,103E GASES = LIMITItG CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents fran the site (see Figure 5.1-3) shall be limited to the following: a. During any calendar quarter: ( 5 mrad for gamma radiation and < 10 mrad for beta radiation a'd, [ b. During any calendar year: < 10 mrad for gamma radiation and < 20 mrad for beta radiation. (The dose design objectives shall be reduced based on pre-7. dicted noble gas releases from the turbine building if effluent sampling is not provided. The dose design objectives shall also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the site boundary.) APPLI CABILITY: At all times. ACTION: i a. With the calcul ated air dose from radioactive noble gases in gase-ous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and sthmit to the Commission within 30 days, pursuant to Secification 6.9.2, a Secial Report which identifies the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the ranainder of the currbnt calendar quarter and during the sub-sequent three calendar quarters so that the cumul ative dose during l these four calendar quarters is within (10) mrad for gamma radia-tion and (20) mrad for beta radiation. 2 b The provisions of Secifications 3.0.3 and 3.0.4 are not appl ical e. SURVEILLANCE REQUIREMEffT S 4.11.2.2 Dose Calculations Cumul ative dose contributions for the cur-rent calendar quarter and current calendar year shall be detennined in accortlance with the ODCM at least once every 31 days. p PNR-ST S-1 3/4 11-)E = E

RADI0' ACTIVE EFFLUEUT S, DOSE, RADI0 IODINES, R_ADI0 ACTIVE MATERI AL IN PARTICULATE FORM, AND RADIONUCLlDES OTHER THA.N f0BLE GASES l L1MITItG CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiofodines and radioactive materials in particulate fonn, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-3) shall be limited to the following: a. During any calendar quarter: 17.5 mran to any organ and, b. During any calendar year: 115 nran to any organ. (The dose design objective shall be reduced based on predicted cathon-14 releases and turbine building releases if effluent sampl ing is not provided.) APPLICABILITY: At all t imes. ACTION: a. With the calcul ated dose from the release of radiciodines, radio-active materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the sove limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Secification 6.9.2, a Secial Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the ~ rel. cases of radioiodines and radioactive materials in particul ate fonn, and radionuclides (other than noble gases) with half-lives - greater than 8 days in gaseous effluents during the rewainder of the current calendar quarter and daring the stbsequent three cal ' endar quarters so that the cumulative dose or dose commitment to an individual from such releases during these four calendar quarters is within (15) mran to any organ. b. The provisions of Secifications 3.0.3 and 3.0.4 are not appl ic ab1 e. SlRVEILLANCE REQUIREMENT S 4.11.2.3 Dose Calculations Cumulative dose contributions for the current ~ calendar quarter and current calendar year shall be detenained in acconianc; with the ODCM at least once every 31 days. 13 PWR-ST S-1 3/4 Il-14

RAD 10 ACTIVE EFFLUEt6S GASE0US RADWASTE TREATMENT LIMITING CONDITION F0P OPEP.ATION

1 3.11.2.4 The gaseous radwaste treatment system and the ventil ation exhaust treatment system shall be OPERABLE. The. appropriate portions of the 'gaseots radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site-(see Figure 5.1-3) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation and the appropriate portions of the ventilation exhaust treatment system shall be used tc. educe radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3) when averaged x

over 31 days v:ould exceed 0.3 mren to any organ. APPLI CAP,ILITY: At all times. ACTION: a. With the gaseous radwaste treatment system and/or the ventilation exhaust treatment system inopersle for more than 31 days or with gaseous waste being discharged without treatment and in ex-cess of the above limits, in lieu of any other report required l by Specification 6.9.1, prepare and sthmit to the Commission within 30 days, pursuant to.9ecification 6.9.2, a.Secial Report, which includes the following information: 1. Identification of the inoperible equipment of subsysters and the reason for inoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABLE r.tatus. 3. Summary description of action (s) taken to prevent a re-l currence. b. The provisions of Secifications 3.0.3 and 3.0.4 are not appl ic abl e. F SURVEI LL ANCE REQUI REMENT S ([ Cont i nd V 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in acconiance with the ODCM. 4 P:!R-ST S-1 3/4 11-}6 s

) / s l.\\; c_j St'EYU tt.ANCE REQUIREMENTS (Centinued) av.y J: 1 All.2.4.2 The gaseous radwaste treatment system a'nd ventilation exh)6st l system shall be demonstrated OPERARLE by operating the gasecut radwaste ~" treatment system equipment and ventilation exhaust treatment system equip-ment for at least. minutes, at least once per.92 days unless the appro-priate system has been utilized to process radioactive gaseous effluents ~ c-j +" during the previous 92 days. g 1 o - /,, 6, g v. j e g . qPA* # ) II T i 6

ee t"

l f. m I s e 4 / e / s - f / 6 b It*l$ PWR-STS-1 3/4 @ W i .//'/E i

RADI0 ACTIVE EFFLUENTS O DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose commitment to any real individual from uraniun fuel cycle sources shall be limited to < 25 mrem to the total body or any organ (except the 'hvroid, which~shall be limited to < 75 mrem) over 12 consecutive months. APPLICARILITY: At' all times. ACfl0N: s a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the l imits of Specifications 3.11.1.2. a, 3.11.1.2.b, 3.11.2.2. a, 3.11.2.2.', 3.11.2.3.a, or 3.11.2.3.h, in l ieu of any other report ra,uired by specification 6.9.1, prepare and submit a Special Feport to the Commissiv.7 Firsuant to Tpecificatien 6.9.2 and limit the stbsequent releases releases such that the dose or dose commitment to any real individual from uranium fuel cycle sources is limited to < 25 mrem to the total body o: any organ (except thyroid, which is limited to < 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to any real individual fran uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 St and ard. b. The provisions of specifications 3.n.3 and 3.0.4 are not appl ic dal e. SURVEILLANCE REQUIREMENTS 4.11.2.5 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shalT be determined in accordance with Specifi-cations 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the OPCM. Il-Ik PWR-ST S-1 3/4 I g -ltd

RADIDACTIVE EFFLUF,NTS EXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion) LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen or oxygen in the waste gas holdup system shall be limited to $_4" by volume. APPLICABILITY: At all times. ACTION: s a. With the concentration of hydrogen or oxygen in the waste gas holdup system exceeding the limit, restore the concentration to within the limit within 48 hours. b. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e. SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen or oxygen in the waste gas holdup system shall be detennined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the (hy-drogen or oxygen) monitors required OPERABLE by Table 3.3-)2 of Specifi-cation 3.3.3.p. t3 10. A e II-I i PWR-STS-1 3/4 11-11 jfdV 1

i RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen urle/,c.Q explositn)( LIMITING CONDITION FOR OPERATION 3.11.2.6A The concentration of hydrogen and/or oxygen in the waste gas holdup system shall be limited to < 2% by volume. _A_PPLI CABILITY: At all times. ACTION: a. With the concentration of hydrogen and/or oxygen in the waste gas holdup system > 27, by volume but < 47, by volume, restore the concentration of hydrogen and/or oxygen to within the limit 48 hours. h. With the concentration of hydrogen and/or oxygen in the waste gas holdup system > 4% by volune, immediately suspend all additions of waste gases to the system and reduce the concentra-tion of hydrogen and/or oxygen to < 2" within 48 hours. c. The provisions of Specification 3.0.3 and 3.0.4 are not appli cabl e. SURVEILLANCE REQUIREMENTS 4.ll.2.6A The concentrations of hydrogen and/or oxygen in the waste gas holdup system shall be detennined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3-Jf of Speci fication 3.3.3.9'. 13 10, PWR-STS-1 3/4 1 IV'f'

RADIO ACT IVE EFFr0Ef6 S GAS SIORAGE T Af1KS LIMITIfG CDilDITI0ff FDR OPERATI0f1 3.11.2.7 The quantity of radioactivity conta'ined in each gas storage tank shall be limited to < curies noble gases (considered as Xe-133). APPLI CABILIT Y: At all times. ACT 10ft: a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all addi-tions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. l b. The provisions of Socifications 3.0.3 and 3.0.4 are not appl icabl e. 3JRVEILLAf4CE REQUIREf1 Erd S 4.11.2.6 T he quantity of radioactive material contained in each gas storage tank shall be detemined to be within the above limit at least once per 24 hours when radioactive materials are heirg added to the tank. 9 il-19 PWR-ST S-1 3/4 JJ M .]/e w

RADI0 ACTIVE EfflUEr# S 3/4.11.3 9 TID RADI0 ACTIVE WASTE LIMITIfS (DifDITION FDR OPERATION w a.ppGadk 3.11.3.1 T he solid radwaste sys tem s hall be OPERABLE and us ed,, gin acconf-ance with a PROCESS C0tiTROL PROGRAM, for the TLIDIFICATI0f! and packaging of radioactive wastes to ensure meeting the requiroments of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site. APPL ICABILITY: At all times. ACT I0ti: a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, stspend shipments of defectively packaged solid radioactive wastes Trca the site. b. With the solid radwaste system inoperable for more than 31 days, in licu of any other report required by Secification 6.9.1, prepare and stbmit to the Conmission within 30 days, pursuant to Specification 6.9.2, a Secial Report Which includes the following information: 1. Identification of the inoperable equipment of sibsystems and the reasons for inoperability. 2. Action (s) taken to restore the inoperable equipment to CPERABLE s tatts. 3. A description of alternative used for SLIDIFICAIION and packaging of wastes. 4. Summary description of action (s) taken to prevent a re-currence. c. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e. SURVEILLANCE REQUIREliENT S 4.11.3.1.1 Tile sol 4d radwaste system shall be demonstrated OPERABLE at 1 east once per 92 days by: p-20 PWR-ST S-1 3/4 Ji-ffr-ll &

SURVEILLANCE REFjetEMENTS (Continued) a. Perfomance of functional tests of the equipment and components ~" of the solid radwaste system, b. Operating the solid radwaste system at least once in the pre-vious 92 days in acconiance with the PROCESS CONTROL PROGRN4 Ov 3 c. Verification of the existence of a valid contract for SOLIDIFI-CATION to be perfomed by a contractor in acconfance with a PROCESS CONTROL PROGRAM. 4.11.3.1.2 The PROCESS CONTROL ' PROGRAM shall be used to verify the SOLI-DIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate sol utions). a. If any test specimen fails to verify SOLIDIFICATION, the SOLI-DIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, al-ternative SOLIDIFICATON parameters can be detemined in acconiance with the PROCESS C0f4 TROL PROGRMi, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters detemined by the PROCESS CONTROL PROGRAM. b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall pro-vide for the collection and testing of representative test specimens from each consecutive hatch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modi fied as required, as provided in Specification 6.14, to assure SOLIDIFICATION of subsequent batches of itaste. G tt-2.1 P1,'R-ST S-1 3/4 W W -//8

P 3/4.12 RADIOLOGICAL ENVIR0fiMENTAL FONITORING 3/4.12.1 IONITORIfG PROGRAM LIMITIiG CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1. APPLICABILITY: At all times. ACTION: a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and sthmit to the Commission, in the Annual Radiological Environmental Operating Report, a desc ription of the reasons for not conducting 1 the program as required and the plans for preventing a recurrence. -(Ceviations are pem.itted f.c.. the requi ed sempWg schedul e -if specimcas-arc anchteineble due to harerdoes-cond4t-ions, -s c as o n al un cv e il eb il i ty, o r to-tral f unc t ion c f e u tem atic-tampi-ing- -equipnent. If--t+e4etter, every-effort-shal-1-he-faade-to -conpl-ete-corrective-aet-ion prior 10-the end of-the-next s enpi ing-- ' period.) C b. With the level of radioactivity in an environmental sampling medium at-one-or more of thc iccetions specified-in the Offs-ite 00sc Celcui et-ion f'encal--(OfEf4)*' exceeding the repnrting levels 3.rt-2. -*Tf Table W9 when averaged over any calendar quarter, prepare and sthmit to the Commission within 30 davs from the end of the affected calendar quarter a report pu'rsuant to 6. 9.1.13. 5.w #((1 c. With milk or fresh leafy vegetable samples unavailable from one or more of the sampl e 1ocations required by the 00Cl','W4 uz-4 4 prepare and sthmit to the Commission within.30 days, pursuant f to Specification 6.9.2, a Secial Report,ffNeu-of-any athen i reporA identifies the cause of the unavailability of samples y and identifies locations for obtaining replacment samples. j The. locations frm which samples were unavailable may then s/ he deleted from3the-CDGH provided the locations from which .h M#9 yb,2-l'the replacement samples were obtained are added to the environ-y' 6)E mental monitoring program as repl acement locationsg 4f-aveil-eb+c. d. The provisions of Fpecifications 3.0.3 and 3.0.4 are not h appl ic abl e. ]- r hW k a o PWR-ST S-1 3/4 12-1 7 P. CD = ? C

N2n pet @ .,,,., 2 /Tfnen more than one of the radionuclidC in labTe C.C 2-] ' are'Wtected in the sampling meditn, this report shall be sib- ,mitted if: .t I concentration (1) concentration (2) ,g TiEiit l'cTeTV)~~ + 'l iHi~t 1 ev el ~(2T -- - ~- +...> 1.0 s. Al -:t. tihen radionuclides other than those in Table k9 C-- are' detected and are the result of plant e'fluents, this report shall be sihmitted if the potential annual dose to an individual is ecual to or greater than the calendar year limits of Fpecific a-i t ions 3.11 1.2, 3.11.2.2 an:' 3.11.2.3. This report is not required if the neasured level of, radioactivity was not the resul t of pl ant effluents; horever, in such an event, the con-dition shall be repo. ;ed and desc ribed in the Annual Padiological Environnental Operating Peport. hvu8 . sui 1YElli ANCE REQUIREMENTS 4.12.14 The radiological envirormental monitoring samples shall be collected pursuant to Tabic 3.12-1 fran the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirc.nents of Tables 3.12-1 and 4.12-1. m. O =+=geg --mmmm mumm um mm m

TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~I os h Exposure Pathway Sampling and Type and Frequency anc/or Sample Sample Locations ** Collection Frequency of Analysis m 1. AIRBORNE a. Radiciodine (Locations 1-5) Continuous operation of Radioiodine canister.. and Partic-sampler with sample col-Analyze at least once per ulatesy lection as required by 7 days for I-131. dust loading but at least once per 7 day's. Particulate sampier. Analyze for gross beta, radioactivity > 24 hours t followin'g filter change. Perform gamma isotopic q analysis on each sample 4 wnen gross beta activity is s N > 10 times the yearly mean of 1 control samples. Perform Y isotopic analysis on com ganna posite (by location) sample - at least once per 92 days. ] 2. DIRECT RADIATION (Locations 1-8) At least once per 31 days. Gamma dose. At least once > 2 dosimeters or > 1 per 31 days. Instrument for con 7 or tinuously measuring At least once per 92 days. r and recording dose (Read-out frequencies are Gamma dose. At least once rate at each location, determined by type of dosi-per 92 days. meters selected.)

- Sample locations are given on figure and table in Offsite Dose Calculation Manual (0DCM) 1 1

TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING pR_0 GRAM is N y Exposure pathway Sampling and Type and Frequency L and/or Sample Sample Locations ** Collection Frequency of Analysis._ 3. WATERBORNE a, Surface (Locations 9 and 10) Composite

sample collected Gamma isotopic analysis T

over a period of < 31 days. of each composite sample by location. Tritium anal; sis of composite sample at least once per 92 days. g b. Ground (Locations 11 an' 12) At least once per 92 days. Gamma isotopic and tritiur. d ^ analyses of each sample. M k c. Drinking (Locations 13-15) Composite" sample collected I-131 analysis of each over a period of 1 1 4 days, composite sample; sy if I-131 analysis is per-formed; or and Composite

sample collected Gross beta and gamma over a period of 131 days.

isotopic analysis of each composite sample. Tri tiur. . analysis of composite sample at least once per 92 days. d. Sediment from (Locations 18) At least once per 184 days. Gamma isotopic analysis Shoreline of each sample. Composite samples shall be collected by collecting an aliquot at intervals ot e

- Sample locations are shown on figure in the Offsite Dose Calculation Manual [0DCMfceeding 2 hours ~

TABLE _3.12-1 (Continued) g RADIOLOGICAL ENVIRONMENTAL MONITORING' PROGRAM 5,5 i? ~' Exposure pathway Sampling and Type and Frequency and/or Sample Sample Locations ** Collection Frequency of Analysis

4.

INGESTION a. Milk (Locations 17-20) At least once 'per 15 days Gamma isotopic and I-131 'T when animals are on pasture; analysis of each sample.- at least once per 31 days at other times, b. Fish and In-(Locations 21 and 22) One sample in season, or at Gamma isotopic analysis vertebrates least once per 184 days if on edible portions. not seasonal. One sample of i each of the following species: 1M a 1. 2. c. Food Products (Locations 23-25) At time of harvest. One Gamma isotopic analysis s,y sample of each of the fol, on edible portion. ( lowing classes of food products: 's. 2. 3. (Location 26) At time of harvest. One I-131 analysis. sample of broad leaf vegetation.

- Sample locations are shown on figure in Offsite Dose Calculation Manual

_ _. g

3. rt -2 TABLE 6-9,

y REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTA $1 m' Reporting Levels Water Airborne Particulate Fish Milk Food Prodects ~ Analysis (pCi/1) or Gases (pCi/m3) (pCi/Xg, wet)' (pCi/1) (pCi/Xg, wet) 4 H-3 2 x 10 3 I Mn-54 1 x 10 4 3 x 10 2 Fe-59 4 x 10 4 1 x 10 i {. Co-58 1 x 10 4 3 x 10 ( 2 Co-60 3 x 10 4 N m, 1 x 10 d9 Zn-65 3 x 10 4 2 2 x 10 2M Zr-Nb-95 4 x 10 I-131 2 0.9 2 3 1 x 10 Cs-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 50 20 2 x 10 70 2 x 10 3 3 2 (b) Ba-La-140 2 x 10 2(b) 3 x 10 \\ (a) For drinking water samples. This is '40CFR Part 141 value. uO \\ (b) Total for parent and daughter. >V)

u. n g I:

i? ~

TABLE 4.12-1 i I LOWER LIMITS OF DETECTION (LLD)ad y Water Airborne Particulate Analysis (pCi/1) or Ga Fish Milk Food Products Sediment (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg dry) b gross beta 4 1 x 10-2 b H 2000 (1000 ) 54 15 F.n 130 59 30 Fe 260 58,60 15 130 Co 65 30 260 7n 95Zr-Nb 15 131; 1 7 x 10-2 1 60 b 134,137 15(10 ), 18 1 x 10-2 130 15 60 150 Cs c I,140 15 C Ba-La 15 e /

TARLE 4.12-1 (Continued) TAPLF NDTATIDN a. The LLD is the smallest concentration of radliaactive material in a sample that will be detected with 957, probability with 57. probability of falsely. concluding that a blank observation rcpresents a "real" signal. For a particular measuronent system (which may include radio-chemical separation): 4.66 s LLD = b E V,P72<Ye exp(-AaTT where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standard deviation of the background counting rate b or of the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transfonnation) V is the sample size (in units of nass or volume) 2.22 is the number of trans fonnations per ninute per picocurie Y is the fractional radiochenical yield (when applicable) A is the radioactive decay constant for the particular radionuclide AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for envirorrnental s ampi es, not pl ant ef fl uent s ampi es ). The value of s used in the calculation of the LLD for a detec-b l tion system shall be based on the actual observed variance of l the background counting rate or of the counting rate of the blank sampleY (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide detennined by ganma-ray spectronetry, the back-ground shall include the typical contributions of other radio-nuclides nonaally present in the samples (e.g., potassium-40 in mil k s ampl es). Typical values of E, V, Y and AT should be is ed in the cal col ations. pFR-STS-1 3/4 IPrT z -/,, /

@+ TABLE 4.12-1 (Continued) TABLE NOTATION 1 b. LLD for drinking wcter. 5 c. Total for parent and daughter. f d. This does not mean that only the radionuclides in Table 4.12-1 are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall he identified and reported. s = w_- ] ) n u g4.f o4.- l-The LLD is deflined as an a oriori (before th .a t) limit representing the carabilitd of a ne' s)irt,nent =- a sy4 tem and oot a a coster'iori (a ft h, the fa c t) lin'i t for a pa r ticula r/ r.da sure.,fnt. f t T- ~~ A / / Arulysss shall1 be perior.;ed in /such a tr.aryner thathej'sta ted LDs Wil! be ac, hic' icd order routin condi tioris. , = _ tions, unavoidably s, mall knole si zes, the creigc4 of.j nterfppei gOcca sior.aj r nucijdes, or uncontrollable circumst.ances.,ay rende/'q,ese LLDs un. jj/ I achieva31c. l In' s:;ch ca ses, the con'trib6 ting factor's wiTi tid identi fied ?_ '=- at f ' 2<criNd in the Anmial Padicle)ic)! Envir: ce.tal Crer(pr'nc d e r "r t. c Ul \\ \\ J V \\J l v e i 1.-V I i PWR-SIS-1 3/4 1 W W ^ 2 4 m._ mmmumm

, RADIOLOGICAL ENVIRONIEtiT AL FON110RifG 3/4.12.2 L AND U SE. CENSU S LIMITING CONDITION FOR OPERATION 3.12.2 A 1and use census shal1 he conducted and shal1 identify the 1oca-tion of the nearest milk animal, the nearest residence and the nearest ga rden* of g reater than 500 s qua re feet producing f res h lea fy vegetabl es in each of the 16 meteorological sectors within a distance of five miles. (for elevated releases as defined in Regulatory Guide 1.111, (Rev 1) July 1977, the land use census shall also identify the locations of all milk aninals and al1 gardens of greater than 500 square feet prodocinq f resh leofy vegetablos in each of the 16 c.eteorological sectors within a distance of t hree mil es.). A_PL l_CARI L 1 T_Y :At al 1 t imes. AG ION: a. With a land use cens ts identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently b eing calcul ated in pec i ficat ion 4.11.F. 3.1, in l ieu c of any other report requi red by Epecification 6.0.1, prepa re and s ubmit to the Coi, mission wi thin 30 days, purs uant to Specifica-tion F.9.2, a Tec;al Repo rt which identi fies t he new 1 ocation(s). b. With a land use censis identifying a location (s) which yields a calculated dose or dose commitment (via the same expos ure pathway) greater than at a location from which sampl es are currently beinq nbtained in accordance with Fpecification 3.12.1, in lieu of any other repo rt requi red by Fpeci fication 6.9.1, prepa re and s thmit to the Conmission wi thin 30 days, purs uant to Specification 6.9.7, a Epecial Report which identifies the new location. The new l o-cation shall be added to the radiological environmental monitoring program wi thin 30 days. The sanpling location, excluding the control s t a t io n l oc a t i o n, ha v i ng t he l owes t c al cul a ted dos e o r d os e c om-mitment (via the same expos ure pathway) nay be deleted from this monitoring program after (October 31) of the year in which this l and us e cens us was conducted. c. The provisions of cpec i fica t ions 3. 0. 3 a nd 3. 0. 4 are not applicable. 9)RVFIl l ANCE RFQUI RLMLNT S 4.17.2.1 The land us e tens us s hall be conduc t ed at least once per 12 iionths between the dates of June 1 and Oct ober 1, by door-to-door s urvey, aerial s urvey, or by c ons ul t ing lural ag ric ul t ure aut ho ri t ies. ~

Broad lea f voge t a t. ion s oi: ol ing may h e pei fo n.ed a t ti'e s i te b ounda ry in t he di r et t ion set tor wi th t he highos t D/Q in 1 ieu of t he ga rdon ci ns uc.

PWR-ST S-1 3/4. X ll$ y q

RADIOLOGICAL ENVIRONMENTAL IDNITORIfS 3/4.12.3 INTERLABORATORY COMPARIf0N PROGRAM LIMITIiS CONDITION FOR OPERATION 3.12.._3_~Analyses shall be perfonned on radioactive materials supplied as pNrt' of an Interlaboratory Comparison Program which has been approved by NRC. APLICABILITY: At all times. ACT ION: a. With analges not being perfonned as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Repo rt. b. The provisions of Specification 3.0.3 and 3.0.4 are not appl icable. SURVEILL ANCE REQUIREMENT S A s ummary of results obtained as part of the above rhuired 4.12.3 Interlaboratory Comparison Program and in acconiance with the Offsite Dose Calculation Manual (00CM) shall be included in the Annual Radiological Environmental Operating Report. IT-Ic PWR-STS-1 3// L?A6 if7

INSThUMENTATION BASES 3/4.3.3. ' RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with a procedures in the Offsite Dose Calculation Manual (0DCM)- to ensure that the alanm/ trip 1411 occur prior to exceeding the limits of 10 CFR Part 20. ~ The OPERABILITY and use of this instrumentation is consistent with the s requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Pa rt 50. LC 3/4.3.3.f RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The al a rm/tri p setpoints for these instruments shall be calculated in accordance with procedures in the Offsite Dose Calculation Manual (0DCM) to ensure that the alarm / trip sdll occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and control-ling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requi renents of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 7 s ) 5 O V t - r PUR-STS-1 B 3/4 3-4 W h g t

F . 3/4.11 RADI0 ACTIVE EFFl.UENTS BASE S = -m 3/4.11.1 L10VID EFFLUENTS 3 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive material s released in liquid wa ste ef fluents f rom the site to I unrestricted areas will be less than the concentration levels specified g in 10 CFR Pa rt 20, Appendix R, Table II, Column 2. Thi s limitation provides 5 additional assurance that the levels of radioactive material s in bodics of water outside the site will result in exposures wi thin (1) the Section II. A 1 design objectives of Appendix I,10 CFR Part 50, to an individual and (2) the linits of 10 CFR Part 20.106(e) to the population. The concentration limit for di ssolved or entrained noble gases is based upon the assumption that Xc-135 is the controlling radioisotope and its MPC i n ai r (submersion) g-- wa s converted to an equival ent concent rati on in wa ter usi ng the nethods desc ribed i n Interna ti onal Commi ssi on on Radi ol ogi cal Protecti on (ICPP) Publication 2. 7 1 3/4.11.1.2 D O SE_ ini s s f oci fi ca ti on i s providod to impl cnent the reoui runents of Secti ons II. A, III. A a nd I V. A of Appendix I,10 Cl R Pa rt 50. The Limiling 1 Condition for Operation impl eaents the guides set forth in Section II. A of Appendix I. The AC IION statements provide the requi red ope rati ng fl exi-bility and at the sane tine inpircent the guides set forth i n Section IV. A of Appendix I to assure that the rel rasos of radioacti ve naterial in liquid ef fl uents wi11 he Lept "as 1 ow a s i s reasonably achi evabl e". Al so, fo r fresh water si tes wi th drinki ng wa ter supplies s.hich can be potentially i d f fected by plant operdlions, there i s roasonabl e assurance that the opera-g tion of the facility will not resul t i n radionuclide concent rations i n the fi ni shed drinki ng rater that a re in excess of the requi rments of 40 CFR 141. The dose calculations in the ODCM impl ement the requi rements in Section III. A of Appendix I that cuntonnance wi th the guides of Appendix I i s to be shown by calculational procedures based on models and data such =- that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestinated. The equa ti ons speci fi ed in the ODCM for calculating the deses due to the actual rel ea se rat es of radioactive nat erial s i n li quid ei fl uents a re consi st ent wi th the rethndo-l ogy p r cvid ai i n Icgul a to ry Gui de 1. ln9, ralculation of Annual roses to "an f t co Dcoti ne "el cases of Reactor Lf fl uents for the Pu rpose of Eval ua ti ng Coopliance wi th 10 CFR Pa rt 50, Appendix I," Pevi sion 1, October 19/7, and Regul a t ory Guide 1.1} 3, "Fstina ti ng Squati c Di spe rsi on of Ef fl uents f rom Accidental and Routi ne reactor Rel ec < os fo r the ru rpose of Inpl w enti ng appadi x I," Apr il 19/7. imG -Ol r providos nothods for dose cal cul ations c onsi st ent wi t h J g ul a t o ry Gui v os 1. ; N a nd 1.113. j i NR-S!bl R 3/4 11-1 ---m M I EII u I p ri

'RADI0 ACTIVE EFF1.UEt6S BASES i This specification applies to the release of liouid effluents from each reactor at the site. For units with shared radwaste treatment systens, the liquid effluents from the shared system are proportioned among the units sharing that system. 3/4.11.1.3 LIQUID WASTE TREATl<Et6 ~ The OPERABILITY of the liquid radwaste treatnent system ensures that this systan will be available for use whenever liquid effluents require treatment prior to release' to the environment. The requirements that the appropriate portions of this system be used when specified provides assur-7 ance that the releases of radioactive materials in liquid effluents will r be kept "as low as is reason 61y achievable." This specification impl e-1 ments the requircaents of 10 CFR Part 50.36a, General Design Criterinn 60 E of Appendix I to 10 CFR Part 50 and design objective and in Section II.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were speci-fied as a suitable fraction of the dose design objectives set forth in f Section II. A of Appendix I,10 CFR Part 50, for liquid effluents. 3/4.11.1.4 LIQUID 110LDUP T Af KS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled rel case of the tanks ' contents, the resul ting concentrations would be less than the limits of 10 CFR Part 20, /ppendix 8, Table II, Column 2, ~ at the nearest potable water supply and the nearest surface water supply in an unrestricted area. 3/4.11.2 GASEGUS EFFLUEIR S 3/4.11.2.1 DO SE RAT E This specification is provided to ensure that the dose rate at any time at the site boundary from gaseous effluents fran all units on the site ~ will be within the annual dose limits of 10 CFR Part 20 for unrestricted 7 a reas. The annual dose limits are the doses associated with the concentra-2 tions of 10 CFR Part 20, Ippendix B, Table II, Column 2. These limits provide reason <ble assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outs ide the site boundary, to annual average concen-trations exceeding the limits specified in /ppendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)). For individuals who may at times be uithin the site boundary, the occupancy of the individual will be suf ficiently low to canpensate for any increase in the atnospheric 6 PWR-SIS-1 P-3/4 11-2 C

b _ RAD 10 ACT I VE EFfl QEt(S J B A SE S di f f ts i on f a c to r ab ov e t ha t fo r t he s i te b ounda ry. T he s pec i fi ed rel eas e = rate limits res t rict, a t all t ines, t he corres ponding ganna and beta dose = rates above background to an individual at or bcyond the site boundary to _{ 500 nron/ year to the total body or to _$ 3,000 mran/ year to the skin. T hes e rel eas e ra te l imi ts al s o res t r ic t, a t al l t ines, t he co rres po nd i ns thyroid dose rate ab ove background to an infant via the cow-milt-infant pa thway to ( 1500 mran/ year fo r the neartst cow to the pl ant. q T his s pec i fic a t ion appl ies to the release of gaseous ef fl uents f rom al l reac to rs a t t he s i te. Fo r un its wi t h s ha red radvas te treatnent g sys ters, t he gaseous ef fl cents f rom t he s ha red sys t en a re p ropo rtioned a:.ong t he units s ha ring t ha t s.vs t en. _T .a 3/4.11.7.2 DO SE, lO RI E G A SE S_ S This speci fication is prov ided to inpl a mnt t he roo ui rments of llI. A a nd IV. A of / ra"fix 1,10 CFP Pa rt 50. T he Limiting j Sec t io ns 11. 8, t Condi tion for Ope ra tion impl ments the guides set fo rt h i n Sec t i o n I I. R o f q fy'; e nd ix 1. T he ACT 10 N s ta tr nents prav ide t he requi red cpe rating fl ex ib il it v and at the same time inpl enent t he guides set forth in Fec t i o n I V. A o f E /ppendix I assure that the releases of radioactive naterial in gas eous ef fl uents will be I.ept "as l ow as is reasonably achievable." T he Su rveil-1ance requi rn onts ir.pl ment t he rmui reents in Section i1I. A of /ppendix I t na t c r ofo rm wi t h t he auides of /prend ix 1 t o b e s Mn b v c al cul a t ional p rncedur(s b as ed on ianlels end da t a s uc h t h $ t t he ac t ual' e> c os i.re of an d ind iv id ual t hroug h t he app rop ria te ra tin;ays is unlil ely t o be s +s entially f-und e r,s t ira ted. I he des e cal cul a t ions es t ab1is L>d in the ODC" f or cal cc-lating the doses due to the act ual rel e.m e ra t es of radioac t i / e nobl e gas es = in gas eous ef fl uents will be c ons is tent wi th t he i.ethodol ogy p rovided in 7 Regul a to ry Guide 1.109, " Cal cul a tion of Annual Dos es t o t'a n f rom Pout ine Releases of Reactor Ef fl uents fo r the Purpose of Eval ua ting Conpliance wi th J 10 Cf R Pa rt 50, /-ppendix 1," Revision 1, Octob er 19/7 and Pogul atory Guide Q 1.111, "f'et hods fo r Fs t inating Atmos phe ric T rans po rt and Dis pe rs ion of ] Gaseous Ef fl uents in Rnut ine Rel eases f rm Light 4'a ter-Cool ed Peacto rs," 5 Pov is ion 1, July 19/ 7. T he ODCf' en ua t io ns p rov ided fo r Nte n,in ing t he a i r ] d<.e e t t b s i t e b et.r J e ry a ~ ' " d L, ,n t he F " ' o ric al e o r. m a t as - Ac r ic t %d i t in ns. V ' 1 C -Ul 3 3 p i m, i &s r ! *:,ds for ese c al c ul a t i ons 13 3 t uns is t ent wi t h reg ul M o ry ru ides 1.1U0 ond 1.111. E 3/4.11.P.3 DO SF, PAD 101001 T4 S, MDIO Af f I VE I'Al i PI /t ' r: p Ar i n1 AT E 10 PM A!:D P Y!(ain I!H S l'i N R I P AN I' ' Bl i G A V S_ ~ -i T his s; 4 i fic :t ion is ; r ov ided 1 o pl, ut ' ' > i. ;ui r os of -f " u t i o ns II.C, llI.A <nd IV.A of M a dix I, 10 i ' P ' rt 50 '! n ! a 'i t ina a G T - M E -1 P l l ' -3 j. e = l

RA010ACllVE Lf f LUENTS BASE S Conditions for Operation are the guides set forth in Section II.C of Appendix 1. The ACTION statements provide the requi red operating flexi-bility and at the same time implement the guides set forth in Section x IV. A of Appendix I to assure that the releases of radioactive materials in gaseous ef fluents will be kept "as low as is reasonably achievable." c The ODCM calculational methods specified in the surveillance requi renents implement the requi renents in Section III. A of Appendix I that confonn-m ance with the guides of Appendix I he shown by calculational proc ed u res s based on models and data such that the actual exposure.of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual rel case rates of the subject naterial s a re requi red to be consi stent wi th the nethodol ogy provided i n Regul atory Gui de 1.109, " Cal cul ati ng of Annual 1 Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of = Eval uatiag Compli ance wi th 10 CFR Pa rt 50, Appendix I," Revi si on I, October 1917 and Regulatory Guide 1.111, %tFmis for Estimating Atnospheric Trans-po rt and Di spersi on of Ca seous Li fl uent s i n Pouti ne Rel eases f rom Li ght-Md ter-Cool ed PeaClo rs," Revi si on 1, July 19/7. These equati ons al so pro-vide for detemining the actual doses based upon the hi storical average a tnos pheric condi ti ons. The rel ease rate sPeci fi cati ons fo r radioiodi nes, radioactive na terial in pa rticulate fonn and radionuclides other than noble ga ses a re des emf ent on the exi sti ng radionuclide pathways to nan, i n the un rest ri c t ed a rea. The pathways which were exami ned in the devel opment of these cal cul ations were:

1) individual inhalation of ai rborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consuoption by nan, 3) deposi tion onto grassy a reas where nilk animal s and meat produci ng ainal s graze wi th consunption of the milk and meat by ran, and 4) deposition on the ground with subsewnt exposure of man.

= 3/4.11.2._4_ GA 510'u S M S TE T RE A f E N T_ The OPERARihl TY of the gaseous radwa ste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever ga seous ef fluents requi re treatment prior to rel ease to the envi ron1ent. The requi rment that the appropriate portions of these systems be esed when speci fied provides reasonabl e assurance that the celeases of radioactive naterials in gaseouc e f fl ue nt s wi l l b e ke pt "as low as i s reasonably achi evable." Thi s spec 1 ication inpl ements t he rr;ui r r ent s of 10 CF R Pa ct Sn. ?Fa, General D si gn Cri t e r i on 60 of Eppen-di x A t o 10 Li R Pa rt S0,.nd design objective 4ction llD of App < ndix I to 10 CF R Pa rt 50 The speci fi ed limi ts governing t he use of a npropria te portinns of the syst ems were sp?ci fi ed as a sui table f raction of the dnse t design objectives set forth i n Sections II.B a nd II.C of f ppendix I,10 CFR

== 4 nds effIunnts. Pa rt 50, for ga P! R 4i S-1 B 3/4 11-4 m .--mm--------imumim

E L-RADl0 ACTIVE EFFLUEfifS l BASES a { 3/4.11.2.5 DOSE [ This speci fication is provided to meet the dose limitations of 40 CFR 190. The Speci fication requi res the prepa ration and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed E twice the design objective doses of Appendix I. For sites containing up to 7 4 reactors, it i s highly unlikely that the resultant dose to a real indivi-e dual will exceed 40 CFR 190 i f the individual reac tors rmai n wi thi n the '= c-3 repo rti ng requi ronent l evel. The Special Report will desc ribe a course of s E action which should result in the limitation of dose to a real individual I for 12 consecutive months to wi thin the 40 CFR 190 limits. For the purposes cf the Special Peport, it nay be assumed that tFe dose comitnent to the = real individual f rom other urani um f uel cycle snucces i s negli gibl e, vi th f the oxception that dose contributions from other nuclear fuel cvcl e facili-a ~ h ties at the same site or wi thi n a radi us of S mil es nust he considered. g = -{ 3/4.11_.2.6 FXPI USIVE GAS MI X Tl!RE E fhi s speci fication is prcvided to ensure that the concentration of pot ntially expl osive gas iiixtures contained in the waste gas treatment j system i s r uintai ned bel ow the fl amnabili ty limi ts of hyd rogen and oxygen, f ( Autonatic control features a re incl uded in the system to prevent the hy-drogen and oxygen conc ent rati ons f rom reachi ng these fl annabili ty 1imi t s. = f rhese automatic cont rol features i ncl ude i sol ati on of t're source of byd m-gen and/or oxygen, a utomatic fiversi on to reroohi ners, or i nj ec ti on or di-l ot a nt s to raiuc e the conc ent ra ti on bel ow the fl a: ' ability limits.) f 'a i n - tai ni ng the conc ent ra ti on of hyd rogen and oxygen bel ow thei r fl anrabili ty 2 _E limits provides assurance tha t the rel eases of radioactive naterial s will he controlled in confoncance wi th the requi rments of General Design 2 \\- Criterion 60 of Aprendix A to 10 CFR Part 50. = f 3/4.11.2.7 GAS STORAGE IAi(KS m Restricting the quantity of radioactivity contained in each gas storage J b tank provides assurance that in the event of an uncontrolled release of the N t a ni s cont ents, the resulting total hoiy exposure to an individual at the E y nea t os t ex cl usi o n a rea b,u.o f a ry wi l l not exceed 0.5 w. Mi s i s consi st ent -= wi t h M a nda rd Revi ew Pl an 15. 7.1, "Q st e C a s yst m Fail ure." c 1 = -E s ? y } h. g PWP-slS-1 B 3/4 11-5 2 a b w n 9l p -3 3 B is

== l

i hAD10 ACTIVE EFFLUENTS BASES 3/4.11.3 SOLID RADI0 ACTIVE WASTE The OPERASILITY of the solid radweste system ensures that the systen 1d11 he available for use whenever solid raduattes require processing and packaging prior to being shipped offsite. This specification impl ements the requiranents of 10 CFR Part 50.36a and General Desi'gn Criteria 60 of Appendix A to 10 CFR Part 50. The process parameters used in establish-ing the PROCESS CONTROL PROGR/J4 may include, but are not limited to waste type, waste pli, waste / liquid / solidi fication agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times. S e PWR-SIS-1 B 3/<1 11-6 P

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ~ BASES 3/4.12.1 MONITGRING PROGRAM The radiological monitoring program required by this specification provides measuranents of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation expsures of individuals resulting from the station ope rati on. This monitoring program thereby supplenents the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than ex-pected on the basis of the effluent measuronents and modeling of the environmental exposure pathuays. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities requi red by Table 4.12.-l are sten #-the-art for routine environmental measurenents in industrial laboratt ries. The LLD's for drinking water meet the requirements of 40 CFR 141. bw@ t 3/4.12.2 LAND USE CENSUS 9-t@ This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if requi' red by the results of this census.XThis census satisfies the requirenents of Section IV.B.3 of Appendix I to 10 CFR Pa rt 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a ganien of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To detennine this minimum ganien size, the following assumptions were used,1) that 20% of the garden was used for growing bmad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. 3/_4.12.3 INTERLABORATORY COMPARI SGN PROGRAM The requi rement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of th,e measuranents of radioactive material in envi ronnmental sample matrices are perfonned as part of a quality assi!rance program for environmental monitoring in order to demonstrate that the results are reasonably valid. PNR-STS-1 B 3/4 12-1 r

l. t g 1[ r ~ ^' _7 _ ~ _ ? ~ a y .4 )lu. ,\\s For more ccuplete di scussion of the LLD and other detection limi ts,'sch_.. .s the follcwing: (1-) HASL Procedures Ib nual,11ASL-300 (ravi sed anntally). .c (2) Cur ri e, L. A., "Limi t s'.for Qua lita tive Detection ar.d Puantita tive ' Detenaination - Application to Radiochemistry" Anal. Chen. 40, 7 586-93 (1968). i .7y (3) Ha rtrwell, J. K., " Detection Limits for Radio'sotopic Counting tz, Techniques," Atlant;c Richfield Hanford Company Report APH-2537, (June 22,1972). ~~ O e. g -t D hv0 c. LL.. /~OMYi A$ L' lIil fi' 1L NI A ~~ ' W j c a,a s t: y a dtJ ~ qa p ea % d A u % 4'k 'n * . k.,u ud. e s e" s 1,.

n _m r E L 5.0 'E! a' GN f f t TURE S _a, E T 5.1 Si TE-y SI TE BOWMARY FOR CASE 0VS EF Ft UENTS { 5.1./9 The site boundary for gaseous effluents shall be shown in Fi g ure S.1 -3. q .Sl IE __BOUJ{DAR_Y F0R l 10__UI D f;FFl UENT S, g S.1./,/ The site bounrfary for liquid ef fluents shall be shown in F; gure 5.1 -4. 1 -- -. t t .5 LXCLUSION AREA e-E;- 5.1.f; The excl usion area shall be as shown in Fi gure 5.1-1. = r+ A L O_W POPUL AII ON /0NE_ P S.1./ The l ow 13pul ati on zone shall be as shown Fi oure 5.1-2. p E h M. Mk" --r t( W P'-lR - S ! 3 -1 5 -1

'e .i; .~ s i l l . This figure shall consist of (map of the site area and provide at a minimum, the infonnation described.in Section'(2.1.2) of the FSAR and meteorological tower location. d EXCLUSION AREA ' FIGURE 5.1-1 O 5-[v' PWR-STS-1

A., r This' figure shall consist of a map of the site area shotiing the Low Population Zone - bounda ry. Features such as totins, roads and recreational areas shall be indicated in sufficient detail to allow identification of significant shifts in population distribution tiithin the LPZ. LOW POPULATION ZONE FIGURE 5.1-2 e 5-[3 PHR-STS-1

This figure shall consist of a map of the site area showing the perimeter of the site and locating the points where gaseous ef fl uent a re rel ea sed. If on-site land and areas subject to radioactive materials in gaseous waste are utilized by the public for recre-ational or other purposes, then these areas shall be identified by occupancy factors and the licensee's method of occupancy control. The figure shall be sufficiently detailed to allow identification of structures and release point elevations, and areas within the site boundary that are accessible by menbers of the general public. See NUREG-0133 for additional guidance. SITE B0UNDARY FOR GASE0US EFFLUENTS FIGURE 5.1-3 p PWR-STS-1 .g. q. 1

This figure shall consist of a map of the site area showing the perimeter of the site and locating the points where liquid effluent leaves the site. If on-site water areas containing radioactive wastes are utilized by the public for recreational or other purpuses, the points of release to these water areas shall be identified. The figure shall be sufficiently detailed to allow identi fication of structures near the release points and areas within the site boundary where ground and surface water is accessible by members ')f the general public. See NUREG-0133 for additional guidance. SITE B0UNDARY FOR LIQUID EFFLUENTS FIGURE 5.1-4 6 PNR-STS-1 (

) " O

~.. s PWR-STS-1 STANDARD TECHNICAL SPECIFICATIONS SECTION 6.0 ADMINISTRATIVE CONTROLS =

AMIill ST RATIVE C0h7 ROL S Respons ibilities 6.5.1.6 The (Unit Review Group) shall be responsible for: D c19L2 Review of every g, ding the preparation and forwarding of reports k. planned release of radioactive material to 3 the environs inclu covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the (Superintendent of Po' 1r Plants) and to (Company Nuclear Review.and Audit Group). 1. Review of ' major changes' to radwaste systens. AUDIT S 6.5.2.8 Audits of unit activities shall be performed under the cognizant ofthe(CNRAG). These aud its shall encompass : 1. The radiological enyironmental monitoring progran and the results thereof at least once per 12 months. m. The OFFSIT E DOSE CALCULATION MA'JUAL and impl enenting procedures at least once per 24 months. n. The PROCESS C0bTROL PROGRAM and imp 1naenting procedures for sol i-dification of radioactive wastes at least once per 24 months. o. The performance of activities required by the Qual ity Assurance Program to meet the criteria of Regul atory Guide 4.15, December 1977 at least once per 12 months. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, impl emented, and maintain-ed covering the activities referenced below: h. PROCkSS C0hTROL PROGRAM implunentation.

i. OFFSITE 00SE CALCULATION 11Al'UAL imp 1 anentation.

j. Qual ity Assurance Progran for effluent and environmental monitor-ing us ing the guidance in Regulatory Guide 4.15. V PWR-ST S-1 6-1 9

ADMINI ST RATIVE CONT ROL S l 9 SI MNUAL RAD 10 LOGICAL ENV1RONMENT AL OPERATIfG REPORT-g A d Routine radiological environmental operating reports covering[s he operation of the unit during the previous calendar year sb.511 he .9.1.6 6 + The initial report shall be } t thmitted prior to May 1 of each year.thmitted prior to May 1 of the year follo s w,? s The annual radiological environmental operating reports shall nclude summaries, interpretations, and an analysis of trends of the .9.1.7 6 for y sults of the radiological environmental surveillance acti i 3 r il - J/ operational controls (as approprf ate), and previous enyironmental surve t 4 lance reports and an assessment of the observed impacts of the pl [ 9 If hannful operation on the environment. of the land use censuses required by Specification 3.12.2. ito ring, effects or evidence of irreversible damage are detected by the mon the report shall provide an analysis of the probica and a planned course of action to alleviate the problon. gghimiuk 4.SULIH) d incl ude The annual radiological environmental operating r9 ports l id In radiological environmental samples taken during the report per o. the event that some results are not available for inclusion with h s report, the report shall be submitted noting and explaining t e reasonT for the missing results. passible in a suppl onentary report. a summary description The reports shall also include the following: a map of all of the radiological environmental monitoring progran; sampling locations keyed to a table giving distances and directions fraa one reactor; the result of land use censuses required by the Secifi-lb cation 3.12.2; and the results of licensee participation in the Inter a or-atory Comparison Program required by Fpecification 3.12.3. SI SEMI ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine radioactive effluent release reports covering the h ll be operation of the unit during the previous 6 months of operation s a The sthmitted within 60 days after January 1 and July 1 of ii l ity. The b s ingle submittal may be made for a multiple unit station. sthmittal should combine those sections that are common to all A units at the station; hotiever, for units with separate raduaste sptems, the sihmittal shall specify the relcases of radioactive material from each unit. 6-2 BWR-ST S-1 L ~ +- =

TABLE 6.9-1 l ENV100NMENTAL BADIOLOGICAL MONITOnlNG PROGRAM EUMMAnY Name of Facility Docnat No. Location of Faci!!!y Reporting Period (County,5 ts tel Tygw ana ower L!rnis gg,,4,,, g lac 81104 Wllin Ill.hrst Annual Mesa Mediurn or Pathmy Told themi.t of All Indicsior Leicollons - Costtrol Luctlons REPORTMLE i a b s m.* d or Andy.. o.... n me.n in ri n. 1 u..a lo ^," ]e,u Y n n.nr . OCCURREHCES b 6 g tun;i or u.. u,.m.no c.,to,n.d Itton n.ne oi,t nc..nu cinci'aa l i l I b (q) t g e c ?. E I %I S I y I i e i e 1 l l I I i i l ' Nomina: Lovver Limit of Detection {LLD) as defined in table notellon a. of Tatele 4.121 of Spocalicailon 4.12.1.1. Mean ased range base.8 upon sistectable measuremerita uniy. Pescalon of deteciatele mesaurements et s,.ec6fied * ' ellosis le imilcated les aiarenil'es*A. II) N d s-uei.: Ti.....mgi. d.i..,. grosadea or uivii,sitv. pur,io... oniy. .. ~ ~ _ _., m A

' ADMINI ST RATIVE CONT R0L S .9.1.9 The radioactive effluent release reports shall include a summary f the quantities of radioactive liquid and gaseous effluents and solid 6 e aste released from the unit as outlined in Regulatory Guide 1.21, o 1 Measuring, Evaluating, and Reporting Padioactivity in Solid Wastes and w eleases of Radioactive Materials in Liquid and Gaseous Ef fluents from 2 ight-Water-Cooled Huclear Power P1 ants," Pevision 1, June 1974, with R ata summarized on a quarterly basis following the fonnat of Appendix B L d thereof. Isaddit= ion fhe radioactive effluent release report to be submitted 60 days safter January 1 of each year shall include an annual summary This of hourly meteorological data collected over the previous year. annual smmary may be either in the form of an hour-by-hour 1isting of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the fonn of joint frequency distribu-( A s ug-tions of wind speed, wind direction, and atmospheric stability. gested magnetic tape fonnat is available from the the llydrology-Meteorology Branch, Division of Site Safety and Environmental Analysis, NRR, NRC, Was hington, D.C. 20555.) This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station dur9g the previous calendar year. This report shall also include an assessment of the radiation ~ All assumptions site boundary (Figur@5.1-377furiEg the report period. used in making these assessments (e.g., specific activity, exposureThe meteorological time and location) shall be included in these reports. conditions concu t) .in gaseous effluents (as determined by sampiing frequency hnd measuremen The assessment shall be used for detennining the gaseous pathway doses. of radiation doses shall be perfonaed in accordance with the Offsite pose Calculation Manual (0DCM). The radioactive effluent release report to be submitted 60 da.ys after January 1 of each year shall also include an assessment of radiation i' individual from reactor releases doses to th.e likely most exposed real and other neatty uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show confonnance with 40 CFR 190, Environmental Radiation pro-Acceptable methods for tection Standards for Nuclear Power p eration. p calculating the dose contribution from liquid and gaseous effluents are The SKY.911NE Code (available given in Regulatory Guide 1.109, Rev.1.fran Radiation Shielding Infonna calculating the dose contribution from direct radiation due to N-16. f l 6 -3 PWR -ST S-1 F

ADi41NISTRATIVE C0tRROLS .[ UREG-XXXX (to be ptb ished) discusses the staff's "l'ethods for Demon-f!trating Compliance with the EPA Uranium Fuel Cycle Standard." s d he radioactive effluent release reports shall include the following in-i onnation for each type of solid waste shipped offsite during the report T f period: I a. Container volume. - {' Total curie quantity (specify whether detennined by measurc-b. ment or estimate). s Principal radionuclides (specify whether detemined by measure-c. ment or estimate). Type of waste (e.g., spent resin, compacted dry waste, d. evaorator bottoms. Type of container (e.g., LSA, Type A, Type B, Large Ouantity). e. Solidification Agenet (e.g., cement, urea fonnaldehyde). f. The radioactive effluent release reports shall include the4014 ewing-in-fetation-for unplanned releases from the site to unrestricted areas of, CL 2% radioactive materials in gaseous and liquid effluents m c. A-tieseription-of-the ev ent. and-- equipuent involh a. .b_ rause(s) for th_e__. unplanned -relcareRA Actions takenAprevent recurrericew tu Consequences--of_the_ unplanned rel~eM d. The radioactive effluent release reports shall include any changes to the PROCESS COTRROL PROGRAM (PCP) made during the reporting period. 10fRHLY REACTOR OPERATING REPORT _ Any changes to the Offsite Dose Calculational l'anual oE-Secif4-au J cat 4en-6715 shall be submitted with the lionthly Operating Peport within 6.9.1.10 In addition, naJor c.g 90 days in which the change (s) was made effective. tment systems to-hmo by4ce-i-changes to the radiaoctive waste t th the Monthly Operating Report for f-ieaticrr 5.% s hall be suhmitted the period ~ in which the evaluation {was reveiwed and accepted by the (Unit Review Group). l e. PWR-ST S-1 e-9

pI ' r' "7[ l d' lH ' IIl 'llp pI' N "'IF' MIPJ H l' u I FI HI 41 ' ADMINISTRATIVE CONTR0LS o PR0MPT NOTITF1CATkON WITH 0RITTEN FOLLOWUP 6.9.1.12 9, c@

j. Occur +enee-of an unus ual ae-ieportant event that-eauses a s ignifi -

eent-radiokg+eal i;..pect -cr-t-het has high pibiic or potential ptbl-ic-interesrteern-ing-red-iokg-ieal impcet-from-un-it-operat-ionr-THIRTY DAY WRITTEN REPORTS

6. fl. i. 83 e.

An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following infomation: 1. A desc'ription of the event and equipment involved. 2. Cause(s) for the unplanned release. 3. Actions taken to prevent recurrence. 4. Consequences of the unplanned release. f. Measured levels of radioactivity in an environmental sampling medium detemined to exceed the reporting level values of 3.g Tables 6v9-2 when averaged over any calendar cuarter sanpling perion. When acre then enc--ei the redionuciida in T eb l e G. 9=2--f. are-detected in tte sempi ing r.ediunri-tMs i epor t Jall be sub-mitted if. -concen w - on- - -{1) concentration-f23 + ... >-id a-t ti Mmit-1 evel T2T ~~ CHait-tevelTIT ~ Whe n-rad io nueHd es-ot he r-t-ha n-t host-in-T-abh-69-2-a re-de tected-anda re-the-res ul-t-o f-pl-an t-e f fl ue n tsHh is-repo rt-s hal-1-b c sem i tted-i f--the-po ten t-i al-enn ua l-dos e-to--en-ind iv-id ual-is-equal-t0-0 r-g re a te r-tha n-the-c al end a r-ye a r-14a i ts-o f-Fe ec-i&ica - t-ions-3rHrl-2, 3rH r2.2 and-3rlhBr-3. T his-repo rt-is-not-requi red i f-t he-eeest red-lev el-o f-rad i o act-i v-i ty-was--no t-the-res ul-t-o f-pl e n t-ef4ke4:ts ; however, in-s4*eh-an-event, the cand-i4.-ion-sha14-be-rc ported-and-desc-r-ibed-in the Annual-Radichgical-Environmental Ope ra t-ing-Repo rt. PWR-ST S-1 6-&* b-$

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, sta ike rL xte en;4cn f Midifih fn ud as:d/n.hbn A A"ke' un:swidue.ztexycyaJb-6. \\

0'~ ADMINISTRATIVE G)NTROLS 6.10 RECORD RETENTION 6.10.2 d._Asconis--ef gaseous -a'n&-Hgirid, odisc-tiea 'naterM.-## 6 to-thnv irn ne,-~t/ j i 1. Records of analyses required by the radiological environmental monitoring program. 4 6.14 PROCESS CONTROL PROGRAff (PCP) 6.14.1 The PCP shall be approved by the Commission prior to implementa-tion. 6.14.2 Licensee initiated changes to the PCP may be made provided the change: 1. Shall be submitted to the Commission pinch.s i in the semiannual Radioactive Effluent Release Report for the period in which the change (s) was made and shall contain: a. s ufficiently detailed infonnation to totally support the rationale for the change without benefit of addi-tional or suppl enental infonnation; b. a detennination that the change did not reduce the overall confonnance of the solidified vaste product to existing criteria for solid wastes; and c. documentation of the fact that the change has been reviewed and found acceptable by the (URG). 2. Shall become effective upon review and acceptance by the (URG). 6.15 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.15.1 The ODCM shall be approved by the Commission prior to implementa-tion. 1 1 PWP,-ST S-1 4+ l (. 4 i i

d '

ADMINISTRATIVE CONTROLS 6.15.2 Licensee initiated changes to the ODCM may be made provided the change:

1. Shall be sthmitted to the Corx.ission in the Monthly Operating Report pursvant-to-See+f-ioat-ion 5.0.-l.17within 90 days of the date the change (s) was made effective and shall contain: a. sufficiently detailed infomation to totally support the rationale for the change without benefit of additional or supplanental infomation. Infomation submitted should consist of a package of those pages of the ODCM to be changed with each page numh~ered and provided with an s approval and date box, together with appropriate analyses or evaluations justifying the change (s); b. a detemination that the change will not reduce the accuracy or reliability of dose calculations or setpoint deteminations; and c. documentation of the fact that the change has been reviewed and found acceptable by the (URG). 2. Shall become effective upon review and acceptance by the (URG). 6.16 MAJOR CHAfGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) Licensee initiated;/ jor changes to the radioactive waste system 6.16.1 ma (liquid, gaseous and solid) may be made provided: Ths fr}I' Jrchange is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the (Unit Review Group). The discussion of each change shall contain: a,J7 a summary of the evaluation that led to the determination that the change coul be made in acconiance with 10 CFR 50.59; /r 27' sufficient detailed infomation to totally support the reason for the change without benefit of additional or supplemental infomation; e.)7 a detailed description of the equipment, components and pro-cesses involved and the interfaces with other plant systems; d.M an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/ or quantity of solid wastegfrom those previously predicted in the 1icense application and amendments thereto;

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.S~9 VI , % ; h i. M.i & M E k M ~ % % % % b & M -

b r_ ADf1IllI 5TRAf!VE 00lff ROLS e..fr7 an evaluation of the change which shots the expected naxi-mum exposures to individuals in the unrestricted area and to the general population. rom those previously estimated in the license applicatio and amendments thereto; T 1Q:491 ?

f. Af a comparison of the predicted releases of radioactive g

materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes j were made r i <f.11 an estimate of the exposure to plant operating personnel as j a result of the change; and i lt, af documentation of the fact that the change was reviewed and found acceptable by the (URC). .). Jf The change shall be come effective upon review and acceptance by [ the (URG). s ') 3 s i !/ 6 -3 PWP.ST S--I fedTf I i}}

ML20069N044

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