NRC Generic Letter 1978-25: Difference between revisions

NRC Generic Letter 1978-025: Appendix I Model Technical Specifications
	ML031280330
Person / Time
Issue date:	07/11/1978
From:	Grimes B K; Office of Nuclear Reactor Regulation
To:	;
References
	GL-78-025
	Download: ML031280330 (113)
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Revision as of 11:59, 4 March 2018

UNITED STATESNUCLEAR REGULATORY COMMISSIONA~WSHN T N, .0 HNT .C. 2055o9 y July 11, 1978TO ALL POWER REACTOR LICENSEESGentlemen:In order to provide reasonable assurance that the requirements of10 CFR 50 Appendix I are implemented at all nuclear power facilities,the NRC staff has prepared the enclosed Appendix I model TechnicalSpecifications. These model specifications are intended to provideguidance in the scope and types of required specifications for eachfacility in the areas of equipment and administrative requirementsincluding actions we consider appropriate if a limiting conditionfor operation cannot be met.The enclosure uses the Standard Technical Specification format withblanks or parentheses appearing where the information is plantspecific.We request that you submit a license amendment application toincorporate the applicable specifications of the enclosed guidanceinto your Appendix "A" Technical Specifications within the numberof days indicated for your facility in the attachment to thisletter. A staggered submittal schedule has been selected tofacilitate staff review. The staff considers such an amendmentto be a CLASS III Amendment per 10 CFR 170.22, provided theapplication is consistent with the enclosed guidance.If you have any questions on this matter, please contact us.

Sincerely,Brian K. Grimes, Assistant Directorfor Engineering and ProjectsDivision of Operating Reactors

Enclosures:

1. Model Appendix I TechnicalSpecifications2. Submittal Schedule J Nv' NUREG NO. 0472v-iDRAFTRADIOLOGICAL EFFLUENT TECHNICALSPECIFICATIONS FOR PWR'SK-MAY 1978 1.0 DEFINITIONSCHANNEL CALIBRATION1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of thechannel output such that it responds with the necessary range and accuracyto known values of the parameter which the channel monitors. The CHANNELCALIBRATION shall encompass the entire channel including the sensor andalarm and/or trip functions, and shall include the CHANNEL FUNCTIONALTEST. The CHANNEL CALIBRATION may be performed by any series of sequen-tial, overlapping or total channel steps such that the entire channel iscalibrated.CHANNEL CHECK1.10 A CHANNEL CHECK shall be the qualitative assessment of channelbehavior during operation by observation. This determination shall include,where possible, comparison of the channel indication and/or status withother indications and/or status derived from independent instrumentationchannels measuring the same parameter.CHANNEL FUNCTIONAL TEST1.11 A CHANNEL FUNCTIONAL TEST shall be:a. Analog channels -the injection of a simulated signal into thechannel as close to the sensor as practicable to verifyOPERABILITY including alarm and/or trip functions.b. Bistable channels -the injection of a simulated signal into thesensor to verify OPERABILITY including alarm and/or trip functions.SOURCE CHECK1.29 A SOURCE CHECK shall be the qualitative assessment of channel responsewhen the channel sensor is exposed to a radioactive source.PROCESS CONTROL PROGRAM1.30 A PROCESS CONTROL PROGRAM shall be the operating procedure andprocess parameters within which SOLIDIFICATION of radioactive wastes fromliquid systems is assured.SOLIDIFICATION1.31 SOLIDIFICATION shall be the conversion of radioactive wastes fromliquid systems to a homogeneous, monolithic, immobilized solid with definitevolume and shape, bounded by a stable surface of distinct outline on allsides (free-standing).I PWR-STS-I1-1 TABLE 1.2FREQUENCY NOTATIONNOTATION FREQUENCYS At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .W At least once per 7 days.M At least once per 31 days.Q At least once per 92 days.SA At least once per 184 days.R At least once per 18 months.S/U Prior to each reactor startup.P Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to each release.N.A. Not applicable.K.1\1- PWR-STS-I1-8 INSTRUMENTATIONRADIOACTIVE LIQUID EFFLUENT INSTRUMENTATIONLIMITING CONDITION FOR OPERATION3.3.3.8 The radioactive liquid effluent monitoring instrumentationchannels shown in Table 3.3-11 shall be OPERABLE with their alarm/tripsetpoints within the specified limits.APPLICABILITY: As shown in Table 3.3-11.ACTION:a. With a radioactive liquid effluent monitoring instrumentationchannel alarm/trip setpoint less conservative than the valueshown in Table 3.3-11, immediately suspend the release ofradioactive liquid effluents monitored by the affected channelor declare the channel inoperable.b. With one or more radioactive liquid effluent monitoringinstrumentation channels inoperable, take the ACTION shown inTable 3.3-11.c. The provisions of Specifications 3.0.3-and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.3.3.8 Each radioactive liquid effluent monitoring instrumentationchannel shall be demonstrated OPERABLE by performance of the CHANNELCHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TESToperations during the MODES and at the frequencies shown in Table4.3-11.PWR-STS-I3/4 3-44 CC(I'.1TABLE 3.3-11RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION-o(A-IMINIMUMCHANNELSOPERABLEALARM/TRIPSETPOINTMEASUREMENTRANGEINSTRUMENTAPPLICABILITYACTION1. Gross Activity MonitorsProviding AutomaticIsolation(a. Liquid Radwaste EffluentLineb. Steam Generator BlowdownEffluent Linec. Turbine Building (FloorDrains) SumpsEffluent Line**(1)(1)(1)***< (_cpm)< C-cpm)< (_cpm)(1-105 cpm)(1-105 cpm)(1-105 cpm)181920W4b-nCA)2. Gross Activity MonitorsNot Providing AutomaticIsolation Controla. Service Water EffluentLineb. Component Cooling WaterSystem(1)*< (_cpm)<!.(_cpm)(l-lO5 cpm)(1-105 cpu)20 (20(1)** During releases via this pathway**Includes rinse, flush and slurry waste from secondary systemdemineralizer or filter-demineralizers.condensate deep bed TABLE 3.3-11 (Continued)(>4-o-4I--ICAsIRADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSOPERABLEINSTRUMENTAPPLICABILITYALARM/TRIPSETPOINTMEASUREMENTRANGEACTION3. Continuous CompositeSamplers and SamplerFlow Monitorfa. Steam Generator BlowdownEffluent Lineb. Turbine Building SumpsEffluent Line *(1)*N.A.N.A.N.A.N.A.19(1)*204h-4. Flow Rate Monitorsa. Liquid Radwaste EffluentLineb. Steam Generator BlowdownEffluent Linec. Discharge Canal(1)*(1)*> (_gpm)> (_gpm)< (_gpm)(0-__gpm)(0-__gpm)(0-__gpm)2121(1)*21 (*During releases via this pathway**Includes rinse, flush and slurry waste from secondary systemdemineralizers or filter-demineralizers.condensate deep bed CTABLE 3.3-11 (Continued)RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONC3"I-oCAI--ICA.IMINIMUMCHANNELSOPERABLEINSTRUMENT5. Activity RecordersAPPLICABILITYALARM/TRIPSETPOINTN.A.MEASUREMENTRANGE(1-105 cpm)ACTION(a. Steam Generator BlowdownEffluent Line(1)*23, _b. Liquid RadwasteEffluent Line6. Tank Level Monitors (for tanksa.(1)*N.A.(1-105 cpm)outside the buildings)(1) **b.(1)C.(1)******<( ft3)<( ft3)<( ft3)<( ft3)(0-1000 ft3)(0-1000 ft3)(0-1000 ft3)(0-1000 ft3)2322222222d.(1)(* During releases via this pathway.**During liquid addition to the tan ITABLE 3.3-11 (Continued)TABLE NOTATIONACTION 18 -With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases from the tank may continue for up to 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sprovided that prior to initiating the release:ACTION 19 -1. At least two independent samples of the tank'scontents are analyzed, and2. At least two technically qualified members of theFacility Staff independently verify the release ratecalculations and discharge line valving;otherwise, suspend release of radioactive effluents viathis pathway.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue for up to 7 daysprovided grab samples are analyzed for gross radioactivity(beta or gamma) at a limit of detection of at least 10 7pCi/gram:1. At least once per hour when the specific activityof the secondary coolant is > 0.001 uCi/gram DOSEEQUIVALENT 1-131.2. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activityof the secondary coolant is < 0.001 pCi/gram DOSEEQUIVALENT 1-131.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue for up to 7 daysprovided that at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months grab samples areanalyzed for gross radioactivity (beta or gamma) at alimit of detection of at least 10 7 pCi/ml.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue for up to 7 daysprovided the flow rate is estimated at least once per 4hours.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, liquidadditions to this tank may continue for up to 7 daysprovided the tank liquid level is estimated during allliquid additions to the tank.ACTION 20 -ACTION 21 -ACTION 22 -PWR-STS-I3/4 3-48 TABLE 3.3-11 (Continued)TABLE NOTATIONACTION 23 -With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via the affected pathway may continue for up to7 days provided the gross radioactivity level is recordedat least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .PWR-STS I3/4 3-49 (C-o:'(AI-TABLE 4.3-11RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSINSTRUMENT1. Gross Activity MonitorsProviding Automatic Isolationa. Liquid Radwaste Effluents Lineb. Steam Generator BlowdownEffluent Linetoi c. Turbine Building (FloorDrains) Sumps Effluent Line2. Gross Activity Monitors NotProviding Automatic IsolationControla. Service Water Effluent Lineb. Component Cooling WaterSystemCHANNELCHECKPDDDDSOURCECHECKPMMMMCHANNELCALIBRATIONR(3)R(3)R(3)R(3)R(3)CHANNELFUNCTIONALTESTQ(1)Q(1)Q(M)Q(2)Q(2)MODES IN WHICHSURVEILLANCEREQUIRED****((

CTABLE 4.3-11 (Continued)C61-4LnI'--RADIOACTIVE LIQUID EFFLUENTMONITORINGINSTRUMENTATION SURVEILLANCE REQUIREMENTSINSTRUMENTCHANNELCHECKSOURCECHECKCHANNELCALIBRATIONCHANNELFUNCTIONALTESTMODES IN WHICHSURVEILLANCEREQUIRED(W-P.-I3. Continuous Composite Samplersand Sampler Flow Monitora. Steam Generator BlowdownEffluent Lineb. Turbine Building SumpsEffluent Line4. Flow Rate Monitorsa. Liquid Radwaste EffluentLineb. Steam Generator BlowdownEffluent LineDDN.A.N.A.RQRQ**DDN.A.N.A.RQ**RQ(c. Discharge CanalD N.A. RQ*

((-I(A'-4ITABLE 4.3-11 (Continued)RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNEL SOURCEINSTRUMENT CHECK CHECK5. Activity Recordersa. Steam Generator Blowdown D N.A.Effluent Lineb. Liquid Radwaste D N.A.Effluent Line6. Tank Level Monitors (for tanks outside the building)CHANNELCALIBRATIONCHANNELFUNCTIONALTESTMODES IN WHICHSURVEILLANCEREQUIRED*RQRQ*4-Ina.b.DDDDN.A.N. A.N.A.N.A.RRQQ****c.RRQQ****d.(

K-TABLE 4.3-11 (Continued)TABLE NOTATION* -During releases via this pathway.** -During liquid additions to the tank.(1) -The CHANNEL FUNCTIONAL TEST shall also demonstrate that automaticisolation of this pathway and control room alarm annunciation occursif any of the following conditions exist:1. Instrument indicates measured levels above the alarm/tripsetpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(2) -The CHANNEL FUNCTIONAL TEST shall also demonstrate that control roomalarm annunciation occurs if any of the following conditions exist:1. Instrument indicates measured levels above the alarm/tripsetpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(3) -The CHANNEL CALIBRATION shall include the use of a known (traceable tothe National Bureau of Standards radiation measurement system) liquidradioactive source positioned in a reproducible geometry with respectto the sensor and emitting beta and gamma radiation with fluences andenergies in the ranges measured by the channel during normal operation.PWR -STS-I3/4 3-53 INSTRUMENTATIONRADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATIONLIMITING CONDITION FOR OPERATION3.3.3.9 The radioactive gaseous effluent monitoring instrumentationchannels shown in Table 3.3-12 shall be OPERABLE with their alarm/tripsetpoints within the specified limits.APPLICABILITY: As shown in Table 3.3-12ACTION:a. With a radioactive gaseous effluent monitoring instrumentationchannel alarm/trip setpoint less conservative than the valueshown in Table 3.3-12, immediately suspend the release ofradioactive gaseous effluents monitored by the affectedchannel or declare the channel inoperable.b. With one or more radioactive gaseous effluent monitoringinstrumentation channels inoperable, take the ACTION shown inTable 3.3-12.c. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.3.3.9 Each radioactive gaseous effluent monitoring instrumentationchannel shall be demonstrated OPERABLE by performance of the CHANNELCHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TESToperations during the MODES and at the frequencies shown in Table4.3-12.PWR-STS-I 3/4 3-54 (A-I(nI-TABLE 3.3-12RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONCMINIMUMCHANNELSINSTRUMENT OPERABLE1. Waste Gas Holdup Systema. Noble Gas ActivityMonitor (1)b. Noble Gas Activity Recorder (1)c. Iodine Sampler (1)ind. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)g, Hydrogen MQnitor (1)h. Hydrogen Monitor (alternate)1) alarm 22) alarm and initiate 2automatic control functionAPPLICABILITY********ALARM/TRIPSETPOINTc (- cpm)N.A.N.A.N.A.> ( cfm)> (- cfm)4 (4%) by volumeMEASUREMENTRANGE(10-106 cpm)(10.106 cpm)N.A.N.A.(0- cfm)(0- cfm)(0-20%) by volume(0-20%) by volume(0-20%) by volume(ACTION25232525262629** s (2%) by volume* s (4X) by volume3030(* During**Duringreleases y1A this pathway.waste gas holdup system (treatment for primary system offgases) operatio ~I)1-4TABLE 3.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMIlCH)INSTRUMENT OPI1. Waste Gas Holdup System (continued)i. Oxygen MonitorJ. Oxygen Monitor (alternate)1) alarm2) alarm and initiateautomatic control function, 2, Condenser Evacuation Systemena. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate MonitorUIMUM%dNNELS'RABLEAPPLICABILITY(1)(2)(21(1)(. )(1)0l)(1)(1)**********ALARM/TRIPSETPOINTs (4%) by volumei (2%) by volumeZ (4%) by volume-C (_ cpm)N.A.N.A.N.A.MEASUREMENTRANGE(0-25%) by volume(0-25%) by volume(0-25%) by volume(l0-106 cpm)(10_106 cpm)N.A.N.A.(0- cfm)(0- cfm)ACTION(293030272327272626(> (_ cfm)> (- cfm)** During releases via this pathway.**During waste gas holdup system (treatment forprimary system offgases) operatio TABLE 3.3-12 (Continued)RADIOACTIVE GASEOUS EFrLUENT MCNITORING INSTRUMENTATION(*I-o(I--4(AMINIMUMCHANNELSOPERABLEINSTRUMENT3. Vent Header Systema. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate Monitor4. Containment Purge Systema. Noble Gas Activity Monitorb. Nobel Gas Activity Recorderc. Iodine Samplerd. Particulate SamplerAPPLICABILITY(1)(1)(1)(1)(1)(1)**ALARM/TRIPSETPOINT< (_ cpm)N.A.N.A.N.A.*(1)(1)(1)(1)******cfM)cfin)MEASUREMENTRANGF(10-106 cpm)(10106 cpm)N.A.N.A.(O- cfm)(0- cfm)(10-106 cpm)(10-106 cpm)N.A.N.A.ACTION27 (232/272626282328(28< (- cpm)N.A.N.A.N.A.* During releases via this pathwa ICTABLE 3.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONC:40-4MINIMICHANNINSTRUMENT OPERAIe. Flow Rate Mcnitor (1)f. Sampler Flow Rate Monitor (1)5. Auxiliary Building VentilationSystema. Noble Gas Activity Monitor (1)b. Noble Gas Activity Recorder (1)C. Iodine Sampler (1)X d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)6. Fuel Storage Area Ventilation Systema. Noble Gas Activity Monitor (1)b. Noble Gas Activitv Recorder (1)L0MELSBLEAPPLICABILITY********ALARM/TRIPSETPOINT, ( cfm)> ( cfm)< (- cpm)N.A.N.A.N.A., (- cfm)> (- cfm)< (- cfm)N.A.MEASUREMENTRANGE(0- cfm)(0-_ cfm)(10-106 cpm)(10_106 c pr-.)N.A.N.A.(0- _ cfm)(0- cfm)(10-106 cpm)(10-106 cpm)ACTION26F2( '272327272626(2723* During releases via this pathwa (TABLE 3.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION(CnI--I0-4MINIMUMCHANNELSINSTRUMENT OPERABLE6. Fuel Storage Area Ventilation System (continued)c. Iodine Sampler (1)d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1), 7. Radwaste Area Ventilation SystemUlqoa. Noble Gas Activity Monitor (1)b. Noble Gas Activity Recorder (1)c. Iodine Sampler (1)d. Particulate Sampler (1)e. Flow Rate Monitor (1)f. Sampler Flow Rate Monitor (1)APPLICABILITY*:*******ALARM/TRIPSETPOINTMEASUREMENTRANGEN.A.N.A.N.A.N.A.cfm)cfm)< (~ cpm)N.A.N.A.N.A.> (- cfm)> (- cfm)(O- cfm)(O- cfm)(10-10 cpm)(10-106 cpm)N.A.N.A.(0- cfm)(0- cfm)ACTION272726262723272I>2626* During releases via this pathwa (LAl-ITABLE 3.3-12 (Continued)GASEOUS EFFLUENT MONITORINGRADIOACTIVEINSTRUMFNTATIONINSTRUMENT C8. Steam Generator Blowdown Venta. Noble Cas ActivityMonitorb. Noble Gas ActivityRecorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Mcnitorf. Sampler Flow Rate Monitor1INIMUMCHANNELS)PERABLEAPPLICABILITYW-Wn(1)(1)(1)(1)(1)(1)******ALARM/TRIPSETPOINT< ( cpm)N.A.N.A.N.A.> ( cfm)> (- _cfm)MEASUREMENTRANGE(10-106 cpm)(10-106 cpm)N.AN.A.ACTION272327272626(0-~(0-~~cfm)cfm) -(* During release via this pathwa TABLE 3.3-12 (Continued)TABLE NOTATIONACTION 23 -ACTION 25 -ACTION 26 -ACTION 27 -ACTION 28 -ACTION 29 -ACTION 30 -With the number of channels OPERABLE less than required bythe Minimum Channels OPERABLE requirement, effluent releasesvia the affected pathway may continue for up to 7 days providedthe gross radioactivity level is recorded at least once per4 hours.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, the contentsof the tank may be released to the environment for up to72 hours provided that prior to initiating the release:1. At least two independent samples of the tank'scontent are analyzed, and2. At least two technically qualified members of theFacility Staff independently verify the release ratecalculations and discharge line valving;otherwise, suspend release of radioactive effluents viathis pathway.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue for up to 7 daysprovided the flow rate is estimated at least once per 4hours.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluentreleases via this pathway may continue for up to 7 daysprovided grab samples are taken at least once per 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sand these samples are analyzed for gross activity atleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, suspendrelease of radioactive effluents via this pathway.With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, operationof this waste gas holdup system may continue for up to14 days provided gas samples are analyzed at least onceper 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .With the number of channnels OPERABLE one less thanrequired by the Minimum Channels OPERABLE requirement,operation of this waste gas holdup system may continuefor up to 14 days. With both channels inoperable, immedi-ately suspend operation of this waste gas holdup system.PWR-STS-I3/4 3-61 (CC-o£US(ITABLE 4.3-12MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSRAnIOACTIVE GASEOUS EFFLUENTw4h-awIr~INSTRUMENT1. Waste Gas Holdup Systema. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate Monitorg. Hydrogen Monitorh. Hydrogen Monitor (alternate)i. Oxygen MonitorJ. Oxygen Monitor (alternate)CHANNELCHECKPDDDPDDDDDSOURCECHECKPN.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.CHANNELCALIBRATIONR(3)RN.A.N.A.RRQ(4)Q(4)Q(5)Q(5)CHANNELFUNCTIONALTESTQ(0)QN.A.N.A.QQMMMMMODES IN WHICHSURVEILLANCEREQUIRED***********((

(-oCA(A14ATABLE 4.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCINSTRUMENT2. Condenser Evacuation Systema. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodtne Samplerd. Particulate Sampler* e, Flow Rate Monitorf. Sampler Flow Rate Monitor3. Vent Header Systema. Noble Gas Activity Monitorb. Noble Gas Actiyity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate MonitorCHANNELCHECKDDDDDDDDDDDDSOURCECHECKMN.A.N.A.N.A.N.A.N.A.MN.A.N.A.N.A.N.A.N.A.CHANNELCALIBRATIONR(3)RN.A.N.A.RRR(3)RN.A.N.A.RRCHANNELFUNCTIONALTESTQ(2)QN.A.N.A.QQQ(2)QN.A.N.A.QqMODES IN WHICHSURVEILLANCEREQUIRED**.***((

CCICA-eiTABLE 4.3-12 (Continued)r MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSRADIOACTIVE GASEOUS EFFLUENi-CHAINSTRUMENT CH4. Containment Purge Systema. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodine Sampler4h d. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate Monitor5. Auxiliary Building Ventilation Systema. Noble Gas Actvity Monitorb. Noble Gas Activity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate Monitor,NNELHECKDDDDDDSOURCECHECKPN.A.N.A.N.A.N.A.N.A.CHANNELCALIBRATIONR(3)RN.A.N.A.RRR(3)RN.A.N.A.RRCHANNELFUNCTIONALTESTQ(l)QN.A.N.A.QQQ(2)QN.A.N.A.QQMODES IN WHICHSURVE ILLANCEREQUIRED*******(DDDDDDMN.A.N.A.N.A.N.A.N.A.(

(TABLE 4.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS(-u--I(A-4CHANNELINSTRUMENT CHECK6. Fuel Storage Area Ventilation Systema. Noble Gas Activity Monitor Db. Noble Gas Activity Recorder Dc. Iodine Sampler Dd. Particulate Sampler De. Flow Rate Monitor Dcmf. Sampler Flow Rate Monitor D7. Radwaste Area Ventilation Systema. Noble Gas Activity Monitor Db. Noble Gas Activity Recorder Dc. Iodine Sampler Dd. Particulate Sampler DSOURCECHECKMN.A.N.A.N.A.N.A.N.A.MN.A.N.A.N.A.CHANNELCALIBRATIONR(3)RN.A.N.A.RRR(3)RN.A.N.A.CHANNELFUNCTIONALTESTQ(2)QN.A.N.A.QQQ(2)QN.AN.AMODES IN WHICHSURVEILLANCEREQUIRED******((

C2:-ILA4TABLE 4.3-12 (Continued)RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSINSTRUMENT7. Radwaste Area Ventilation Systeme. Flow Rate Monitorf. Sampler Flow Rate MonitorX 8. Steam Generator Blowdown Venta. Noble Gas Activity Monitorb. Noble Gas Activity Recorderc. Iodine Samplerd. Particulate Samplere. Flow Rate Monitorf. Sampler Flow Rate MonitorCHANNELCHECK(continued)DDDDDDDDSOURCECHECKN.A.N.A.MN.A.N.A.N.A.N.A.N.A.CHANNELCALIBRATIONCHANNELFUNCTIONALTESTRRQQMODES IN WHICHSURVEILLANCEREQUIRED*****(R(3)RN.A.N.A.RRQ(2)QN.AN.A.QQ(I K>~-TABLE 4.3-12 (Continued)TABLE NOTATION* -During releases via this pathway.** -During waste gas holdup system operation.(1) -The CHANNEL FUNCTIONAL TEST shall also demonstrate that automaticisolation of this pathway and control room alarm annunciationoccurs if any of the following conditions exist:1. Instrument indicates measured levels above the alarm/tripsetpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(2) -The CHANNEL FUNCTIONAL TEST shall also demonstrate that controlroom alarm annunciation occurs if any of the following conditionsexist:1. Instrument indicates measured levels above the alarm/tripsetpoint.2. Circuit failure.3. Instrument indicates a downscale failure.4. Instrument controls not set in operate mode.(3) -The CHANNEL CALIBRATION shall include the use of a known (traceableto the National Bureau of Standards radiation measurement system)gaseous radioactive source positioned in a reproducible geometrywith respect to the sensor and emitting beta and gamma radiationwith fluences and energies in the ranges measured by the channelduring normal operation.PWR -STS -I 3/4 3-67 K>TABLE 4.3-12 (ContinuedTABLE NOTATION(4) -The CHANNEL CALIBRATION shall include the use of standard gassamples containing a nominal:1. One volume percent hydrogen, balance nitrogen, and2. Four volume percent hydrogen, balance nitrogen.(5) -The CHANNEL CALIBRATION shall include the use of standard gas samplescontaining a nominal:1. One volume percent oxygen, balance nitrogen, and2. Four volume percent oxygen, balance nitrogen.PWR-STS-I3/4 3-68 3/4.11 RADIOACTIVE EFFLUENTS3/4.11.1 LIQUID EFFLUENTSCONCENTRATIONLIMITING CONDITION FOR OPERATION3.11.1.1 The concentration of radioactive material released from the siteto unrestricted areas (see Figure 3.11-1) shall be limited to the concentra-tions specified in 10 CFR Part 20, Appendix B, Table II, Column 2 forradionuclides other than noble gases and 4 x 10-5 uCi/ml total activityconcentration for all dissolved or entrained noble gases.APPLICABILITY: At all times.ACTION:With the concentration of radioactive material released from the site tounrestricted areas exceeding the above limits, immediately decrease therelease rate of radioactive materials and/or increase the dilution flowrate to restore the concentration to within the above limits and provideprompt notification to the Commission pursuant to Specification 6.9.1.12.SURVEILLANCE REQUIREMENTS4.11.1.1.1 The concentration of radioactive material in unrestrictedareas shall be determined to be within the above limits by obtainingrepresentative samples in accordance with the sampling and analysisprogram specified in Table 4.11-1.4.11.1.1.2 Reports -The semiannual Radioactive Effluent Release Reportshall include the results of analyses performed in accordance with theprogram of Table 4.11-1 and a summary of all releases of radioactiveliquid effluents.PWR-STS-I3/4 11-1 TABLE 4.11-1RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower LimitSampling Analysis Type of Activity of DetectionLiquid Release Type Frequency Frequency Analysis (LLD)'a(pCi/ml),W. Batch Waste Release Each Batch Each Batch Principal Gamma 0.5Tanks EmittersPOne Batch/M M Dissolved and 10Entrained GasesPEach Batch W 1-131 1.0CompositecP-.IEach Batch M H-3 10CompositecGross a 0.1P-32 1.0PEach Batch Q Sr-89, Sr-90 0.05Compositec(Fe-55) (1.0).Plant Continuous Continuousd W Principal Gamma 0.5bReleases , (Steam Composited Emittersgenerator blowdownand turbine build- I-131 1.0ing drainage) MGrab Sample M Dissolved and 10Entrained GasesContinuous d H-3 10Composite H-Gross a 0.1P-32 1.0Continuous ted Sr-89, Sr-90 0.05Composited(Fe-55) (1.0)PWR-STS- I3/4 11-2 I>TABLE 4.11-1 (Continued)TABLE NOTATIONa. The lower limit of detection (LLD) is defined in Table Notation a. ofTable 4.12-1 of Specification 4.12.1.1.b. For certain radionuclides with low gamma yield or low energies, orfor certain radionuclide mixture, it may not be possible to measure7radionuclides in concentrations near the detection limit of 5 x 10uCi/ml. Under these circumstances, it may be necessary to calculatethe concentration of such radionuclides to a lower limit of detectionof 5 x 10 uCi/ml using observed ratios with those radionuclideswhich are measurable, or the lower limit of detection of 5 x 10- UCi/mlmay be increased proportionally to the magnitude of the gamma yield(i.e., 5 x 10 /I, where I is the photon abundance expressed as adecimal fraction), but in no case shall the lower limit of detectionas calculated in this manner be greater than 10% of the MPC valuespecified in 10 CFR 20, Appendix B, Table II, Column 2.c. A composite sample is one in which the quantity of liquid sampledis proportional to the quantity of liquid waste discharged and inwhich the method of sampling employed results in a specimen whichis representative of the liquids released.d. To be representative of the average quantities and concentrations ofradioactive materials in liquid effluents, samples shall be con-tinuously collected in proportion to the rate of flow of the effluentstream. Prior to analyses, all samples taken for the composite shallbe thoroughly mixed in order for the composite sample to be repre-sentative of the average effluent release.e. A batch release is the discharge of liquid wastes of a discretevolume. A continuous release is the discharge of liquid wastesof a nondiscrete volume; e.g., from a volume or system that has aninput flow during the continuous release.X, PWR-STS-I3/4 11-3 This figure shall consist of a mapof the site area showing the unre-stricted area boundary for liquideffluents as defined in 10 CFR Part20.3(a)(17).* Figure 3.11-1PWR-STS-I314 11-4 RADIOACTIVE EFFLUENTSDOSELIMITING CONDITION FOR OPERATION3.11.1.2 The dose or dose commitment to an individual from radioactivematerials in liquid effluents released to unrestricted areas (see Figure3.11-1) shall be limited:a. During any calendar quarter to < 1.5 mrem to the total bodyand to < 5 mrem to any organ, aWdb. During any calendar year to < 3 mrem to the total body and to< 10 mrem to any organ.APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of radioactivematerials in liquid effluents exceeding any of the abovelimits, prepare and submit to the Commission within 30 days,pursuant to Specification 6.9.2, a Special Report whichidentifies the cause(s) for exceeding the limit(s) and definesthe corrective actions to be taken to reduce the releases ofradioactive materials in liquid effluents during the remainderof the current calendar quarter and during the subsequentthree calendar quarters so that the average dose or dosecommitment to an individual from such releases during thesefour calendar quarters is within 3 mrem to the total body and10 mrem to any organ. (This report shall also include (1) theresults of radiological analyses of the drinking water sourceand (2) the radiological impact on finished drinking watersupplies with regard to the requirements of 40 CFR 141, SafeDrinking Water Act.)b. With the calculated dose from the release of radioactivematerials in liquid effluents exceeding twice the limits ofSpecification 3.11.1.2.a or 3.11.1.2.b, prepare and submit aSpecial Report to the Commission pursuant to Specification6.9.2 and limit the subsequent releases such that the doseor dose commitment to a real individual from all uranium fuel'cycle sources is limited to < 25 mrem* to the total body orany organ (except thyroid, which is limited to < 75 mrem*)over 12 consecutive months. This Special Report shall includeI*The assessment of radiation doses shall be performed in accordance withNUREG-0133.PWR-STS-I3/4 11-5 RADIOACTIVE EFFLUENTSACTION: (Continued)an analysis which demonstrates that radiation exposures toall real individuals from all uranium fuel cycle sources(including all effluent pathways and direct radiation) are lessthan the 40 CFR Part 190 Standard. Otherwise, obtain a variancefrom the Commission to permit releases which exceed the 40 CFRPart 190 Standard.c. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.1.2.1 Dose Calculations -The dose contributions for the totalmtime period r at, shall be determined by calculation at least once per 7E=1days and a cumulative summation of these total body and any organ dosesshall be maintained for each calendar quarter. These dose contributionsshall be calculated for all radionuclides identified in liquid effluentsreleased to unrestricted areas using the following expression:m=E EAi1r 1 AItz CIL F9Jwhere-D = the cumulative dose or dose commitment to the total bodyor an organ T from the liquid effluents for the total timemperiod E Att, in mrem.L=1At = the length of the ith time period over which CIL and FQare averaged for all liquid releases, in hours.C The average concentration of radionuclide i in undilutedIt liquid effluent during time period at from any liquidrelease, in iiCi/ml.PWR-STS-I3/4 11-6 RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS (Continued)Ai = the site related ingestion dose and dose commitment factorto the total body or any organ T for each identifiedprincipal gamma and beta emitter listed in Table 4.11-2,in mrem-ml per hr-uC1.F. = the near field average dilution factor for C during anyliquid effluent release. Defined as the ratl& of themaximum undiluted liquid waste flow during release to theproduct of the average flow from the site dischargestructure to unrestricted receiving waters times(_ is the site specific applicable factor for themixing effect of the discharge structure.)For radionuclides not determined in each batch or weekly composite, thedose contribution to the current calendar quarter cumulative summationmay be approximately by assuming an average monthly concentration basedon the previous monthly or quarterly composite analyses. However, forreporting purposes, the calculated dose contributions shall be based onthe actual composite analyses.4.11.1.2.2 Reports -The calendar quarter cumulative summation ofcalculated dose contributions shall be included in the semiannualRadioactive Effluent Release Report.PWR- STS- I3/4 11-7 K>TABLE 4.11-2LIQUID EFFLUENT INGESTION DOSE FACTORS*A. Dose or Dose Commitment FactorsjT (mrem-ml per hr-pCi)Total Body Criticat OrgansRadionuclideH-3P-32Cr-51Mn-54Fe-55Fe-59Co-58Co-60Zn-65Rb-86Sr-89Sr-90Y-91Zr-95Zr-97Nb-95Mo-99Ru-103Ru-1 06Ag-llOmSb-124Sb-i 25Te-125mTe-127mTe-129mTe-131mTe-132I-131I-133Cs-134Cs-136Cs-i 37Ba-140La-140Ce-141Ce-143Ce-144Np-239*The listed dose factors are for radionuclides that may be detected inliquid effluents.PWR-STS-I3/4 11-8 vRADIOACTIVE EFFLUENTSLIQUID WASTE TREATMENTLIMITING CONDITION FOR OPERATION3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. Theappropriate subsystems shall be used to reduce the radioactive materialsin liquid waste prior to their discharge when the projected doses dueto the liquid effluent releases to unrestricted areas (see Figure 3.11-1)when averaged over 7 days, exceed 0.015 mrem to the total body or0.05 mrem to any organ.APPLICABILITY: At all times.ACTION:a. With the liquid radwaste treatment system inoperable for morethan 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or with liquid waste being discharged withouttreatment as required above, prepare and submit to the Commissionwithin 30 days pursuant to Specification 6.9.2 a Special Reportwhich includes the following information:1. Identification of the inoperable equipment,2. Cause of inoperability,3. Action(s) taken to restore the inoperable equipment toOPERABLE status,4. A description of alternate equipment used for treatmentof radioactive materials,5. Length of time the above requirements were not satisifed,6. Volume and curie content of the waste discharged whichwas not processed by the inoperable equipment but whichrequired processing.7. Actionts) taken to prevent a recurrence of equipmentfailures.b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.PWR-STS- I3/4 11-9 IRADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS4.11.1.3 The liquid radwaste treatment system shall be demonstratedOPERABLE at least once per 31 days by operating the radwaste treatmentsystem equipment.IPWR-STS-I3/4 11-10 RADIOACTIVE EFFLUENTSLIQUID HOLDUP TANKSLIMITING CONDITION FOR OPERATION3.11.1.4 The quantity of radioactive material contained in each of thefollowing tanks shall be limited to < curies, excluding tritium anddissolved or entrained noble gases.a.b.c.APPLICABILITY: At all times.ACTION:a. With the quantity of radioactive material in any of the abovelisted tanks exceeding the above limit, immediately suspendall additions of radioactive material to the tank and within48 hours either reduce the tank contents to within the limitor provide prompt notification to the Commission pursuant toSpecification 6.9.1.12. The written followup report shallinclude a description of activities planned and/or taken toreduce the tank contents to within the above limit.b. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.1.4 The quantity of radioactive material contained in each of theabove listed tanks shall be determined to be within the above limit bynalyzing a representative sample of the tank's contents at least onceper 7 days when radioactive materials are being added to the tank.PWR-STS-I3/4 11-11 RADIOACTIVE EFFLUENTS3/4.11.2 GASEOUS EFFLUENTSDOSELIMITING CONDITION FOR OPERATION3.11.2.1 The dose rate in unrestricted areas (see Figure 5.1-1) due toradioactive materials released in gaseous effluents from the site shallbe limited to the following expressions:a. Release rate limit for noble gases:z K; E(x7/Q1] < 500 mrem/yr, andr (Li + 1.1 M;) [(X7/Q)4] < 3000 mrem/yriwhere the terms are defined below:b. Release rate limit for all radiolodines and radioactive materialsin particulate form and radionuclides other than noble gases:E P1 [W Qi] < T500 mrem/yrwhere:K. = The total body dose factor due to gamma emissions foreach identified noble gas radionuclide, in mrem/yrper pCi/M3 from Table 4.11-3.Li = The skin dose factor due to beta emissions for eachidentified noble gas radionuclide, in mrem/yr perVCi/m3 from Table 4.11-3.M. = The air dose factor due to gamma emissions for eachidentified noble gas radionuclide, in mrad/yr perpCi/m3 from Table 4.11-3 (unit conversion constantof 1.1 mrem/mrad converts air dose to skin dose).PWR-STS-I3/4 11-12 K>RADIOACTIVE EFFLUENTSLIMITING CONDITION FOR OPERATION (Continued)P = The dose parameter for radionuclides other than noblegases for the inhalatton pathway, in mrem/yr per pCi/m3and for the food and ground plane pathways in m2 (mrem/yrl per pCi/sec from Table 4.11-4. The dose factorsare based on the critical individual organ and mostrestrictive age group (child or infant).= The release rate of radionuclides, i, add in gaseouseffluent from all release points at the site, inMCi/sec.t-x74 __ _ sec/m3.The highest calculated annual averagerelative concentration for any area at or beyond theunrestricted area boundary.W = The highest calculated annual average dispersionparameter for estimating the dose to an individualat the controlling location:W = __ sec/M3, for the inhalation pathway. Thelocation is the unrestricted area in the sector.W = meter-2, for the food and ground planepathways. The location is the unrestricted areaboundary in the sector.APPLICABILITY: At all times.ACTION:With the release rates exceeding the above limits, immediately decreasethe release rate to within its limit and provide prompt notification tothe Commiission pursuant to Specification 6.9.1.12.PWR-STS-I3/4 11-13 RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS4.11.2.1.1 The release rate of radioactive materials released in gaseouseffluents from the site shall be determined to be within the abovelimits by obtaining representative samples In accordance with the samplingand analysis program specified in Table 4.11-5.4.11.2.1.2 Reports -The semiannual Radioactive Effluent Release Reportshall include the results of analyses performed in accordance with theprogram of Table 4.11-5 and a summary of all releases of radioactivegaseous effluents.PWR-STS-13/4 11-14 TABLE 4.11-3DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*C-I14Total BodyDose FactorKI(mrem/yr per iCi/m3)Skin Dose FactorL(mrem/yr per iiCi/m3)Gamma AirDose FactorM i(mrad/yr Rer pCi/M3)Beta AirDose FactorN1(mrad/yr per pCi/m3)Radionuclide-P.--a-.AIaL'Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Kr-90Xe-i 31mXe- 33mnXe-133Xe-i 35mXe-i 35Xe-i 37Xe-i 38Ar-417.56E- 02**1 .17E+031 .61E+Ol5.92E+031 .47E+041 .66E+041.56E+049.15E+O12.51E+022. 94E+023.12E+031.81 E+031 .42E+038.83E+038.84E+031 .46E+031 .34E+039.73E+032.37E+031 .01 E+047.29E+034.76E+029.94E+023.06E+027.11E+021 .86E+031 .22E+044.13E+032.69E+031 .93E+Ol1 .23E+031 .72E+Ol6.17E+031 .52E+041 .73E+041 .63E+041 .56E+023.27E+023.53E+023.36E+031 .92E+031 .51E+039.21E+039.30E+032.88E+021 .97E+031 .95E+031 .03E+042.93E+031 .06E+047.83E+031 .l1E+031 .48E+031 .05E+037.39E+022.46E+031 .27E+044.75E+033.28E+03C*The listed dose**7.56E-02 = 7.56factors areX 10-2.for radionuclides that may be detected in gaseous effluent TABLE 4.11-4DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVEPARTICULATE, GASEOUS EFFLUENTS*C-g(AI-I(ARadio-nuclideP.Inhalation Pathway(mrem/yr per pCi/m3)P.Food & Ground Pathways(m2.mrern/yr per pCi/sec)PiInhalation Pathway(mrem/yr per vCi/m )Radio-nucli idePiFood & Ground Pathways-(m2.mrem/yr per pCi/I )H-3P-32Mn-54Fe-59Co-58Co-60Zn-65Rb-86Sr-89Sr-90-IJ Y-91...A Zr-95Nb-95Ru-103Ru-106Ag-llOm6.5E+022.OE+062.5E+042. 4E+041.lE+043.2E+046.3E+041.9E+054. OE tO54.1E+077.OE+042. 2E+041.3E+041.6E+041.6E+053.3E+042. 4E+031.5E+ll1 .1 E+097. OE+085. 7E+084. 6E+091.7E+l01.6E+l01.OE+l09. 5E+i01.9E+093. 5E *083. 6E+083.4E 04.4E+ll1.5E+10Cd-il 5mSn-123Sn-126Sb-124Sb-125Te-127mTe-129mCs-134Cs-136Cs-137Ba-140Ce-141Ce-1441-131I-133Unidentified**7.OE+042.9E+051. 2E+065.9E+041.5E+043.8E+043.2E+047.OE+051.3E+056.1E+055.6E+042.2E+041 .5E+051 .5E+073.6E+064.1E+074.8E+073.4E+091.lE+091 .lE+091.lE+O97.4E+101.3E+095.3E+105.4E+094.7E+102.4E+088.7E+076.5E+08l.lE+129.6E+099.5E+10(*The listed dose parameters aregaseous effluents.for radionuclides that may be detected in**If Sr-90 analysis is performed, use P. given in Ru-106 for unidentified components.If Sr-90 and Ru-106 analyses are perfArmied, use Pi given In I-131 for unidentified components.If Sr-90, Ru-106 and I-131 analyses are performed, use Pi given in P-32 for unidentified component CTABLE 4.11-5(-g2C/Cn-I--ARADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMMinimum Lower Limit ofSampling Analysis Type of Detection (LLD)Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)aP PA. Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 100bTank GrabSample H-3 1B. Containment Purge Each Purge Each Purgec Principal Gamma Emitters l 00GrabSample H-31C. (List other release Mcf Mc Principal Gamma Emitters 100bpoints where gas- Grabeous effluents are Sample H-31discharged from thefacility, e.g. airejector, steam gen-erator flash vent,equipment vents,ventilation ex-hausts, etc.)C(D. All Release Typesas listed in A, B,C above.Continuous9weCharcoalSample1-1314.1-133lo04Continuous9 We Principal Gamma Emitters 10 5Particulate (1-131, Others)SampleContinuous9 M Gross a 10 5CompositeParticulateSample _Continuous9QCompositeParticulateSampleSr-89, Sr-9010-5... ._ _--_______ _________________ I. -I _________________________

TABLE 4.11-5 (Continued)TABLE NOTATIONa. The lower limit of detection (LLD) is defined in Table Notation a.of Table 4.12-1 of Specification 4.12.1.1.b. For certain radionuclides with low gamma yield or low energies orfor certain radionuclide mixtures, it may not be possible to measureradionulldes in concentrations near the detection limit of1 x 10 pCi/ml. Under these circumstances, it may be necessaryto calculate the concenration of such radionuclides to a lower limitof detection of 1 x 10 pCi/ml using observed ratios with thoseradionuclies which are measurable, or the lower limit of detectionof 1 x 10. pCi/ml may be increased proportionally to the magnitudeof the gamma yield (i.e., 1 x 10- /I, where I is the photon abundanceexpressed as a decimal fraction), but in no case shall the lower limitof detection as calculated in this manner be greater than 10% ofthe MPC value specified in 1 CFR 20, Appendix B, Table II, Column 1.c. Analyses shall also be performed following shutdown, startup, orsimilar operational occurrence which could alter the mixture ofradionuclides.d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when therefueling canal is flooded.e. Analyses shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for 7days following each shutdown, startup or similar operationaloccurrence which could lead to significant increases or decreasesin radiotodi'ne releases. Samplers shall also be changed and analyzedat intervals in Specifications 3.11.2.1 and 3.11.2.3.f. Tritium grab samples shall be taken at least once per 7 days fromthe ventilation exhaust from the spent fuel pool area.g. The ratio of the sample flow rate to the sampled stream flow rateshall be known for the time period in Specifications 3.11.2.1,3.11.2.2 and 3.11.2.3.PWR-STS-I3/4 11-18

-RADIOACTIVE EFFLUENTSDOSE, NOBLE GASESLIMITING CONDITION FOR OPERATION3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due tonoble gases released in gaseous effluents from the site shall be limitedto the following expressions:a. During any calendar quarter, for gamma radiation:3.17 x 10i8 E Mi [(-xm Qj + (-xq) qia < 5 mrad, andiDuring any calendar quarter, for beta radiation:3.17 x 108 E N1 [(i7XM Qj + (j77) qj] < 10 mrad, andib. During any calendar year, for gamma radiation:3.17 x 10 8 Mi [(177 Qj + (-Xq) qj] < 10 mrad, andK-iDuring any calendar year, for beta radiation:10-8 eV 1x/Q3.17 x 10 8 N. [1 770 Q. + (x/q) qj] < 20 mradwhere:3.17 x 10 8 = The inverse of the number of seconds in a year.M. = The air dose factor due to gamma emissions for eachidentified noble gas radionuclide, in mrad/yr perVCi/m3 from Table 4.11-3.Ni = The air dose factor due to beta emissions for eachidentified noble gas radionuclide, in mrad/yr perVCi/m3 from Table 4.11-3.(G7n = sec/m3.The highest calculated annual averagerelative concentration for any area at or beyond theunrestricted area boundary for long term releases (greaterthan 500 hrs/year).(iJ7) = _sec/m3.The relative concentration for any areaat or beyond the unrestricted area boundary for shortterm releases (equal to or less than 500 hrs/yr).PWR-STS- I3/4 11-19 IIRADIOACTIVE EFFLUENTSLIMITING CONDITION FOR OPERATION (Continued)Q = The release of noble gas radionuclides, I, in gaseous.effluents,for long term releases (greater than 500 hrs/yr), in pCi.Releases shall be cumulative over the calendar quarter or yearas appropriate.q= The release of noble gas radionuclides, t, in gaseous effluents,for short term releases (equal to or less than 500 hrs/yr),in ACi. Releases shall be cumulative over the calendar quarteror year as appropriate.CThe dose design objectives may be reduced based on predicted noble gasreleases from the turbine building if effluent sampling is not provided.The dose design objectives may also be reduced based on expected publicoccupancy of areas, e.g., beaches and visitor centers within theunrestricted area boundary.)APPLICABILITY: At all times.ACTION:a. With the calculated air dose from radioactive noble gases ingaseous effluents exceeding any of the above limits, prepare andsubmit to the Commission within 3( days, pursuant to Specifica-tton 6.9.2, a Special Report which identifies the cause(s) forexceeding the limit(ssl and defines the corrective actions tobe taken to reduce the releases of radioactive noble gases ingaseous effluents during the remainder of the current calendarquarter and during the subsequent three calendar quarters sothat the average dose during these four calendar quarters iswithin (10) mrad for gamma radiation and (20) wrad for betaradiation.b. With the calculated air dose from radioactive noble gases ingaseous effluents exceeding twice the limits of Specification3.11.2.2.a or 3.11.2.2.b, prepare and submi't a Special Reportto the Commisston pursuant to Specification 6.9.2 and limitthe subsequent releases such that the dose or dose commitmentto a real individual from all uranium fuel cycle sources islimited to 4 25 mrem* to the total body or any organ (exceptthyroid, which is limited to < 75 mrem*) over 12 consecutivemonths. This Special Report shall include an analysis whichThe assessment of radiation doses shall be performed in accordance withNURE6-O 33.PWR-STS-I3/4 11-20 RADIOACTIVE EFFLUENTSACTION: (Continued)demonstrates that radiation exposures to all real individualsfrom all uranium fuel cycle sources (including all effluentpathways and direct radiation) are less than the 40 CFR Part 190Standard. Otherwise, obtain a variance from the Commissionto permit releases which exceed the 40 CFR Part 190 Standard.c. The provisions of Speciftcations 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.2.2 The release of radioactive materials released in gaseouseffluents from the site shall he determined to be within the abovelimits by obtaining representative samples in accordance with thesampling and analysis program specified in Table 4.11-5.PWR-STS-I3/4 11-21 RADIOACTIVE EFFLUENTSDOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM ANDRADIONUCLIDES OTHER THAN NOBLE GASESLIMITING CONDITION FOR OPERATION3.11.2.3 The dose to an individual from radioiodines, radioactivematerials in particulate form and radionuclides other than noble gases ingaseous effluents released to unrestricted areas (see Figure 5.1-1) shallbe limited to the following expressions:a. During any calendar quarter:3.17 x 10 8 R1 [W Q. + w qj] < 7.5 mrem, andb. During any calendar year:3.17 x 10° R. [W Q: + w qua < 15 mremwhere:3.17 x 10 8 = The inverse of the number of seconds in a year.Q. = The release of radioiodines, radioactive materials in particulateform and radionuclides other than noble gases in gaseouseffluents, i, for long term releases (greater than 500 hrs/yr),in PCi. Releases shall be cumulative over the calendar quarteror year as appropriate.q= The release of radioiodines, radioactive materials in particulateform and radionuclides other than noble gases in gaseouseffluents, i, for short term releases (equal to or less than500 hrs/yr), in pCi. Releases shall be cumulative over thecalendar quarter or year as appropriate.W = The annual average dispersion parameter for estimating thedose to an individual at the controlling location for longterm releases (greater than 500 hrs/yr):W = (Ax/A for the inhalation pathway, in sec/m3 fromTable 4.11-6a.W = (D/Q) for the food and ground plane pathways, in meters 2from Table 4.11-6b.w = The dispersion parameter for estimating the dose to anindividual at the controlling location for short term releases(equal to or less than 500 hrs/yr):PWR-STS-I3/4 11-22 RADIOACTIVE EFFLUENTSLIMITING CONDITION FOR OPERATION (Continued)w -(x-/q) for the inhalation pathway, in sec/m3 fromTable 4.11-6c.w = (W7q) for the food and ground plane pathway, in meters 2from Table 4.11-6d.R = The dose factor for each identified radionuclide, i, in ml(mrem/yrl per zCi/sec or mrem/yr per pCi/m3 from Table 4.11-7.For the direction sectors with existing pathways within 5 milesfrom the unit, use the values of R, for these pathways. If no realpathway exists within 5 miles from the center of the buildingcomplex, use the cow-milk R assuming that this pathway exists atthe 4.5 to 5.0 mile distance in the worst sector. If the R for anexisting pathway within 5 miles is less than a cow-milk R It 4.5to 5.0 miles, then use the value of the cow-milk R at 4.5 to 5.0miles. The values used for calculating dose contributions shall beconsistent wtth. the results of the land use census performed pursuantto Specification 3.12.2. The controlling value for each radionuclideof Table 4.11-7 shall be determined and made effective within 30days after the completion of each required land use census. Theparameters W and w shall correspond to the applicable R1 for thesame sector, pathway and location condition.(The dose design objective may be reduced based on predicted carbon-14releases and turbine building releases if effluent sampling is notprovided.)APPLICABILITY: At all times.ACTION:a. With the calculated dose from the release of radioiodines,radioactive materials in particulate form, or radionuclidesother than noble gases in gaseous effluents exceeding any ofthe above limits, prepare and submit to the Commission within30 days, pursuant to Specification 6.9.2, a Special Reportwhich identifies the cause(s) for exceeding the limit anddefines the corrective actions to be taken to reduce thereleases of radiojodines, radioactive materials in particulateform, and radionuclides other than noble gases in gaseouseffluents during the remainder of the current calendar quarterand during the subsequent three calendar quarters so that theaverage dose or dose commitment to an individual from suchreleases during these four calendar quarters is within(C151 mrem to any organ.PWR-STS-I3/4 11-23 RADIOACTIVE EFFLUENTSACTION: (Continued)b. With the calculated dose from the release of radioiodines,radioactive materials in particulate form, or radionuclidesother than noble gases in gaseous effluents exceeding twicethe limits of Specification 3.11.2.3.a. or 3.11.2.3.b, prepareand submit a Special Report to the Commission pursuant toSpecification 6.9.2 and limit the subsequent releases suchthat the dose or dose commitment to a real individual fromall uranium fuel cycle sources is limited to < 25 mrem* tothe total body or any organ (except thyroid, Which is limitedto < 75 mrem*l over 12 consecutive months. This SpecialReport shall include an analysis which demonstrates that radiationexposures to all real individuals from all uranium fuel cyclesources (including all effluent pathways and direct radiation)are less than the 40 CFR Part 190 Standard. Otherwise, obtaina variance from the Commission to permit releases which exceedthe 40 CFR Part 190 Standard.c. The provisions of Speciftcations 3.Q.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.2.3 The release of radioactive materials released is gaseous effluentsfrom the site shall be determined to be within the above limits byobtaining representative samples in accordance with- the sampling andanalysts program specified in Table 4.11-5.*IThe assessment of radiation doses shall be performed in accordance withNUREG-0133.PWR-STS-I3/4 11-24 (CTABLE 4.11-6a(A DISPERSION PARAMETER (7M) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTRDistance to the control location, in milesSector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0NNNENEENEEESESESSESWSW_a WSWWUl WNWNWNNW((

(((-o-4--iTABLE 4.11-6bDISPERSION PARAMETER (O7) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTRDistance to the control location, in milesSector e 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.04.5 4.5-5.0NNNENEENEEESESESSESSSWSWWSWWWNWNWNNW(--AI9(

2:44 DISPE-ISector e 0-0.5NNNENEENEEESESESSESSWWSWI W4 WNWNWNNWC(TABLE 4.11-6c`RSION PARAMETER (xlg) FOR SHORT TERM RELEASES i 500 HR/YR OR : 125 HR/QIRDistance to the control location, in miles0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0(.(

(<TABLE 4.11-6d(A DISPERSION PARAMETER (Onh) FOR SHORT TERM RELEASES s 500 HR/YR OR r 125 HR/QTRCADistance to the control location, in milesSector o 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0NNNENEENEEESESESSESSSWSW-. WSWWNWNNW (C(CATABLE 4.11-7PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASESInhalationPathwayRap(mrem/yrper pCli/m3)MeatPathwayRi(tm2.mrem/yrper pCi/sec)Ground PlanePathwayRi(W2.mrem/yrper pCi/sec)Cow-Milk-InfantPathwayRm2.mrem/yrper MC1/sec).Leafy VegetablesPathwayRi(m2.mrem/yrper pCi/sec)(Radio-nucl ide-A-a(

IRADIOACTIVE EFFLUENTSGASEOUS WASTE TREATMENTLIMITING CONDITION FOR OPERATION3.11.2.4 The gaseous radwaste treatment system shall be OPERABLE. Theappropriate subsystems shall be used to reduce radioactive materials ingaseous waste prior to their discharge when the projected gaseous effluentreleases from all release points to unrestricted areas (see Figure 5.1-1)would result in a dose in any period of 7.days -that exceeds 0.05 mrad forgamma radiation, Q.lQ mrad for beta radiation, or 0.075 mrem to anyorgan for that same 7 day period.APPLICABILITY: At all times.ACTION:a. With the gaseous radwaste treatment system inoperable for morethan 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or with gaseous waste being discharged withouttreatment as required above, prepare and submit to the Commissionwithin 30 days pursuant to Specification 6.9.2 a SpecialReport which includes the following information:1. Identiftcation of the inoperable equipment,2. Cause of inoperability,3. Actions)l taken to restore the inoperable equipment toOPERABLE status,4. A description of alternate equipment used for treatmentof radioactive materials,5. Length of time the above requirements were not satisfied,6. Volume and curie content of the waste discharged whichwas not processed by the inoperable equipment but whichrequired processing.7. Actionts) taken to prevent a recurrence of equipmentfailures.b. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.PWR-STS-I3/4 11-30 RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS4.11.2.4.1 The gaseous radwaste treatment system shall be demonstratedOPERABLE at least once per 31 days by operating the radwaste treatmentsystem equipment.4.11.2.4.2 Dose Calculations. The dose contributions shall be calculatedfor all radionuclides in gaseous effluents projected to be released tounrestricted areas during any projected 7 day period using the followingexpressions:For noble gases, the gamma radiation:3.17 x 10 z M1 [(x-7) Qi + (V74) qa c Q0.O5 mrad, andiFor noble gases, the beta radiation:3.17 x 100 8E N1 £ii7 Q1 + (x70) qi] < 0.10 Brad, andiFor radioiodines, radioactive materials in particulate form andradionuclides other than nokle gases:3.17 x 10- z R1 £WQi + wqi] ; 0.075 mremwhere:Q = The projected release over the next 7 days of radionuciides,1, in gaseous effluents for long term releases (greater than500. hrslyrL, in ICi .q The projected release over the next 7 days of radionuclides,1, in gaseous effluents for short term releases (equal toor less than 50Q hrs/yrl, in pCi.and. all other terms are defined in Specifications 3.11.2.2 and3.11.2.3.PWR-STS-I3/4 11-31 RADIOACTIVE EFFLUENTSEXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion)LIMITING CONDITION FOR OPERATION3.11.2.5 The concentration of (hydrogen or oxygen) in the waste gasholdup system shall be limited to < 4% by volume.APPLICABILITY:At all times.ACTION:a. With the concentration of (hydrogen or oxygen)gas holdup system exceeding the limit, restoreto within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .in the wastethe concentrationb. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.2.5 The concentration of (hydrogen or oxygen) in the waste gasholdup system shall be determined to be within the above limits by con-tinuously monitoring the waste gases in the waste gas holdup systemwith the (hydrogen or oxygen) monitors required OPERABLE by Table 3.3-12of Specification 3.3.3.9.PWR-STS-I3/4 11- 32 RADIOACTIVE EFFLUENTSEXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)LIMITING CONDITION FOR OPERATION3.11.2.5A The concentration of (hydrogen and/or oxygen) in the waste gasholdup system shall be limited to < 2% by volume.APPLICABILITY: At all times.ACTION:a. With the concentration of (hydrogen and/or oxygen) in the wastegas holdup system > 2% by volume but < 4% by volume, restorethe concentration of (hydrogen and/orhoxygen) to within the limitwithin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .b. With the concentration of (hydr'ogen and/or oxygen) in the wastegas holdup system > 4% by volume, immediately suspend alladditions of waste gases to the system and reduce the concen-tration of (hydrogen and/or oxygen) to < 2% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .c. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.2.5A The concentrations of (hydrogen and/or oxygen) in the waste gasholdup system shall be determined to be within the above limits bycontinuously monitoring the waste gases in the waste gas holdup systemwith the (hydrogen and/or oxygen) monitors required OPERABLE by Table 3.3-12of Specification 3.3.3.9.IPWR-STS-I3/4 11-33 RADIOACTIVE EFFLUENTSGAS STORAGE TANKSLIMITING CONDITION FOR OPERATION3.11.2.6 The quantity of radioactivity contained in each gas storagetank shall be limited to < -curies noble gases (considered as Xe-133).APPLICABILITY: At all times.ACTION:a. With the quantity of radioactive material in any gas storagetank exceeding the above limit, immediately suspend alladditions of radioactive material to the tank and within 48hours either reduce the tank contents to within the limit orprovide prompt notification to the Commission pursuant toSpecification 6.9.1.12. The written followup report shallinclude a description of activities planned and/or taken toreduce the tank contents to within the above limit.b. The provisions of Specifications 3.0.3 and 3.0.4 arenot applicable.SURVEILLANCE REQUIREMENTS4.11.2.6 The quantity of radioactive material contained in each gasstorage tank shall be determined to be within the above limit at leastonce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to thetank.PWR-STS-I3/4 11-34 RADIOACTIVE EFFLUENTS3/4.11.3 SOLID RADIOACTIVE WASTELIMITING CONDITION FOR OPERATION3.11.3.1 The solid radwaste system shall be OPERABLE and used, as appli-cable, in accordance with a PROCESS CONTROL PROGRAM, which providesSOLIDIFICATION of wet solid wastes, to solidify and package radioactivewastes and to meet the requirements of 10 CFR Part 20 and 10 CFR Part 71prior to shipment of radioactive wastes from the site.APPLICABILITY: At all times.ACTION:a. With the requirements of 10 CFR Part 20 and 10 CFR Part 71 notsatisfied, suspend shipments of solid radioactive wastes fromthe site.b. With the solid radwaste system inoperable for more than 72hours, prepare and submit to the Commission within 30 dayspursuant to Specification 6.9.2 a Special Report whichincludes the following information:1. Identification of the inoperable equipment,2. Cause of inoperability,3. Action(s) taken to restore the inoperable equipment toOPERABLE status,4. Length of time the above requirements were not satified.5. A description of alternate equipment used to solidify andpackage radioactive materials,6. Type, volume and curie content of waste shipped usingalternate equipment, and7. Action(s) taken to prevent a recurrence of equipment failures.c. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE atleast once per 31 days by performing functional tests of the equipmentand verifying that the system performs its design functions.PWR-STS-I3/4 11-35 11RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS (Continued)4.11.3.1.2 The above required PROCESS CONTROL PROGRAM shall verifySOLIDIFICATION of at least one representative test specimen obtained fromat least every tenth batch of each type of radioactive waste from liquidsystems when the test specimens are processed in accordance with thePROCESS CONTROL PROGRAM. If any test specimen falls to verify SOLIDI-FICATION, additional waste samples shall be taken from consecutive batchesof the same type waste until five consecutive test specimens demonstrateSOLIDIFICATION and the PROCESS CONTROL PROGRAM shall be modified asrequired.4.11.3.1.3 Reports -The semiannual Radioactive Effluent Release Reportshall includ-ethIefollowing information for each type of solid wasteshipped offsite during the report period:a. container burial volume,b. total curie quantity (determined by measurement or estimate),c. principal gamma radionuclides (determined by measurement orestimate),d. type of waste (e.g., spent resin, compacted dry waste, evaporatorbottoms),e. type of container (e.g., LSA, Type A, Type S, Large Quantity),andf. solidification agent (e.g., cement, urea formaldehyde).PWR-STS-I3/4 11-36

\ J3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.1 MONITORING PROGRAMLIMITING CONDITION FOR OPERATION3.12.1 The radiological environmental monitoring program shall beconducted as specified in Table 3.12-1.APPLICABILITY: At all times.ACTION:a. With the radiological environmental monitoring program notbeing conducted as specified in Table 3.12-1, prepare andsubmit to the Commission, in the Annual Radiological OperatingReport, a description of the reasons for not conducting theprogram as required and the plans for preventing a recurrence.b. With the level of radioactivity in an-environmental samplingmedium at one or more of the locations specified in Table3.12-1 exceeding the limits of Table 6.9-2 when averaged overany calendar quarter, prepare and submit to the Commissionwithin 30 days from the end of the affected calendar quarter,a Special Report which includes an evaluation of any releaseconditions, environmental factors or other aspects whichcaused the limits of Table 6.9-2 to be exceeded. This reportis not required if the measured level of radioactivity was notthe result of plant effluents; however, in such an event, thecondition shall be reported and described in the Annual Radio-logical Environmental Operating Report.c. With milk or fresh leafy vegetable samples unavailable fromany of the sample locations required by Table 3.12-1, prepareand submit to the Commission within 30 days, pursuant toSpecification 6.9.2, a Special Report which identifies thecause of the unavailability of samples and identifies locationsfor obtaining replacement samples. The locations from whichsamples were unavailable may then be deleted from Table 3.12-1and Figure 3.12-1 provided the locations from which the replace-ment samples were obtained are added to the environmentalmonitoring program as replacement locations.d. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.PWR-STS- I314 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORINGSURVEILLANCE REQUIREMENTS4.12.1.1collectedand shall4.12-1.The radiological environmental monitoring samples shall bepursuant to Table 3.12-1 from the locations shown on Figure 3.12-1be analyzed pursuant to the requirements of Tables 3.12-1 and4.12.1.2 Reports -The results of analyses performed on the radio-logical environmental monitoring samples shall be summarized in theAnnual Radiological Environmental Operating Report.K>PWR-STS- 33/4 12-2 I'TABLE 3.12-1RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM(-oCA-4CAExposure Pathwayand/or SampleNumber of SamplesandSample Locations**Sampling andCollection FrequencyType and Frequencyof Analysis1. AIRBORNEa. Radiolodine andParticulates(Locations 1-5)(Continuous operation ofsampler with sample col-lection as required bydust loading but at leastonce per 7 days.Radioiodine canister.Analyze at least onceper 7 days for 1-131.f1%.4.JParticulate sampler.Analyze for gross betaradioactivity > 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sfollowing filter change.Perform gamma isotopicanalysis on each samplewhen gross beta activityis >' 10 times the meanof control samples for anymedium. Perform gammaisotopic analysis oncomposite (by location)sample at least onceper 92 days.A2. DIRECT RADIATION(Locations 1-8)> 2 dosimeters or > 1Tnstrument for con-tinuously measuringand recording doserate at eachlocation.At least once per 31 days.orAt least once per 92 days.(Read-out frequencies aredetermined by type of dosi-meters selected.)Gamma dose.once per 31orGamma dose.once per 92At leastdays.At leastdays.** Sample locations are shown on Figure 3.12- C(TABLE 3.12-1 (Continued)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-o-In(A0I-.Exposure Pathwayand/or SampleNumber of SamplesandSample Locations**Sampling andCollection FrequencyType and Frequencyof Analysis3. WATERBORNEa. Surfaceb. Groundc. Drinking(Locations 9 and 10)(Locations 11 and 12)(Locations 13-15)Composite* sample collectedover a period of < 31 days.At least once per 92 days.Composite* sample collectedover a period of < 14 days,if 1-131 analysis isperformed; orGamma isotopic analysis (of each composite sample.Tritium analysis of com-posite sample at leastonce per 92 days.-Gamma isotopic andtritium analyses of eachsample.1-131 analysisof each composite sample;andComposite* sample collectedover a period of _ 31 days.Gross beta and gammaisotopic analysis ofeach composite sample. (Tritium analysis ofcomposite sample at leastonce per 92 days.d, Sediment fromShoreline(Locations 181At least once per 184 days.Gamma isotopic analysisof each sample.* Composite samples shall -be collected by collecting**Sample locations are shown on Figure 3.12-1.an aliquot at Intervals not exceeding 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (C(TABLE 3.12-1 (Continued)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMCAI-i(AExposure Pathwayand/or SampleNumber of SamplesandSample Locations**Sampling andCollection FrequencyType and Frequencyof Analysis4. INGESTIONa. Milk(Locations 17-20)At least once per 15 dayswhen animals are on pasture;at least once per 31 daysat other times.Gamma isotopic and (I-131 analysisof each sample.b. Fish andInvertebrates(Locations 21 and 22)One sample in season, or atleast once per 184 days ifnot seasonal. One sample ofeach of the following species:Gamma isotopic analysison edible portions.W1.g~-Jin2.c. Food Products(Locations 23-25)At time of harvest. Onesample of each of the fol-lowing classes of foodproducts:Gamma isotopic analysison edible portion.(1.2.3.(Location 26)At time of harvest.sample of broad leafvegetation.One1-131 analysis.**Sample locations are shown on Figure 3.12- Figure 3.12-1Radiological Environmental Monitoring Sample LocationsPWR-STS-I 3/4 12-6 (((-o--I(ATABLE 4.12-1MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a9* -w --AnalysisWater(pCi/I)Airborne Particulateor Gas(pci/m )Fish(pCi/kgwet)Milk(pCi/i)Food Products(pCi/kg,wet)Sediment(pCi/kg, dry:-, t tCa~-.8gross beta3 H54Mn59Fe58,60Co65Zn95Zr-Nb1311134,137cs1 40 Ba-La2b33015301530100. 5c15151 X 10-27 X 10-21 X 10-2130260130260130(0.8c151 525c,d80-i a a -- a a TABLE 4.12-1 (Continued)TABLE NOTATIONa -The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability withonly 5% probability of falsely concluding its presence.For a particular measurement system (which may include radio-chemical separation):LLD 4.66 sbE

V

2.22

Y

exp(-Xat)whereLLD is the lower limit of detection as defined above (aspCi per unit mass or volume)Sb is the standard deviation of the background countingrate or of the counting rate of a blank sample as appro-priate Cas counts per minute)E is the counting efficiency (as counts per transformation)V is the sample size (in units of mass or volume)2.22 is the number of transformation per minute perpicocurieY is the fractional radiochemical yield (when applicableA is the radioactive decay constant for the particularradi.onuclideat is the elapsed time between sample collection and analystsThe value of sb used in the calculation of the LLD for a detectionsystemnishall be based on the actual observed variance of thebackground counting rate or of the counting rate of the blanksamples (as appropriate} rather than on an unverifted theoreticallypredicted variance. In calculating the LLD for a radionuclidedetermined by gamma-ray spectrometry, the background shallinclude the typical contributions of other radionuclidesnormally present in the samples (e.g., potassium-40 in milksamples).' vPWR-STS-I3/4 12-8 TABLE 4.12-1 (Continued)TABLE NOTATIONb -LLD for drinking water.c -LLDs for 1-131 in water, milk and other food products correspondto one-quarter of the Appendix I (10 CFR Part 50) design objec-tive dose-equivalent of 15 mrem/year for atmospheric releases and10 mrem/year for liquid releases to the most sensitive organand individual using the assumptions given in Regulatory Guide1.109.d -LLD for leafy vegetables.PWR-STS-I3/4 12-9 IRADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.2 LAND USE CENSUSLIMITING CONDITION FOR OPERATION3.12.2 A land use census shall be conducted and shall identify thelocation of the nearest milk animal, the nearest residence and thenearest garden* of greater than 500 square feet producing fresh leafyvegetables in each of the 16 meteorological sectors within a distance offive miles. (For elevated releases as defined in Regulatory Guide1.111, March 1976. The land use census shall also identify the loca-tions of all milk animals and all gardens of greater than 500 squarefeet producing fresh leafy vegetables in each of the 16 meteorologicalsectors within a distance of three miles.)APPLICABILITY: At all times.ACTION:a. With a land use census identifying a location(s) which yieldsa calculated dose or dose commitment greater than the valuescurrently being calculated in Specification 4.11.2.3.1,prepare and submit to the Commission within 30 days, pursuantto Specification 6.9.2, a Special Report which identifies thenew location(s).b. With a land use census identifying a location(s) which yieldsa calculated dose or dose commitment (via the same exposurepathway) greater than at a location from which samples arecurrently being obtained in accordance with Specification3.12.1, prepare and submit to the Commission within 30 days,pursuant to Specification 6.9.2, a Special Report which identifiesthe new location. The new location shall be added to theradiological environmental monitoring program within 30 days.The sampling location having the lowest calculated dose ordose commitment (via the same exposure pathway) may be deletedfrom this monitoring program after (October 31) of the year inwhich this land use census was conducted.c. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.*Broad leaf vegetation sampling may be performed at the site boundary inthe direction sector with the highest D/Q in lieu of the garden census.PW-T-I / 21PWR-STS- I3/4 12-10 IRADIOLOGICAL ENVIRONMENTAL MONITORINGcirDiti AIUrc DcniITDrMMLrTCJunXc WLLU~nucncu nrln4.12.2.1 The land use census shall be conducted at least once per 12months between the dates of (June 1 and October 1) by a door-to-doorsurvey, aerial survey, or by consulting local agriculture authorities.4.12.2.2 Reports -The results of the land use census shall be includedin the Annual Radlological Environmental Operating Report.PWR-STS-I3/4 12-11 RADIOLOGICAL ENVIRONMENTAL MONITORING3/4.12.3 CROSSCHECK PROGRAMLIMITING CONDITION FOR OPERATION3.12.3 Analyses shall be performed on radioactive materials supplied aspart of the Environmental Protection Agency's (EPA's) EnvironmentalRadioactivity Laboratory Intercomparisons Studies (Crosscheck) Programthat are also included in Table 3.12-1.APPLICABILITY: At all times.ACTION:a. With analyses not being performed as required above, reportthe corrective actions taken to prevent a recurrence to theCommission in the Annual Radiological Environmental OperatingReport.b. The provisions of Specifications 3.0.3 and 3.0.4 are notapplicable.SURVEILLANCE REQUIREMENTS4.12.3 The results of analyses performed as part of the above requiredcrosscheck program shall be included in the Annual Radiological EnvironmentalOperating Report.PWR-STS- I3/4 12-12 INSTRUMENTATIONBASES3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATIONThe radioactive liquid effluent instrumentation is provided to monitorand control, as applicable, the releases of radioactive materials inliquid effluents during actual or potential releases of liquid effluents.The alarm/trip setpoints for these instruments are provided to ensure thatthe alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.The OPERABILITY and use of this instrumentation is consistent with therequirements of General Design Criteria 60, 63 and 64 of Appendix A to 10CFR Part 50.3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATIONThe radioactive gaseous effluent instrumentation is provided tomonitor and control, as applicable, the releases of radioactive materialsin gaseous effluents during actual or potential releases of gaseouseffluents. The alarm/trip setpoints for these instruments are provided toensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. This instrumentation also includes provisions for monitoring(and controlling) the concentrations of potentially explosive gas mixturesin the waste gas holdup system. The OPERABILITY and use of this instru-mentation is consistent with the requirements of General Design Criteria60, 63 and 64 of Appendix A to 10 CFR Part 50.PWR-STS-IB 3/4 3-4 3/4.11 RADIOACTIVE EFFLUENTSBASES3/4.11.1 LIQUID EFFLUENTS3/4.11.1.1 CONCENTRATIONThis specification is provided to ensure that the concentration ofradioactive materials released in liquid waste effluents from the site tounrestricted areas will be less than the concentration levels specified in10 CFR Part 20, Appendix B, Table II. The concentration limit for noblegases is based upon the assumption that Xe-135 is the controlling radio-isotope and its MPC in air (submersion) was converted to an equivalentconcentration in water using the International Commission on RadiologicalProtection (ICRP) Publication 2.3/4.11.1.2 DOSEThis specification is provided to implement the requirements ofSections II.A, III.A and IV.A of Appendix I, 10 CFR Part 5a. The LimitingCondition for Operation implements the guides set forth in Section II.A ofAppendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.Aof Appendix I to assure that the releases of radioactive material inliquid effleunts will be kept "as low as is reasonably achievable". Also,for fresh water sites with drtnking water supplies which can be potentiallyeffected by plant operations, there is reasonable assurance that theoperation of the facility will not result in radionuclide concentrationsin the finished drinking water that are in excess of the requirements of40 CFR 141. The Surveillance Requirements implement the requirements inSection III.A of Appendix I that conformance with the guides of AppendixI be shown by calculatiohal procedures based on models and data suchthat the actual exposure of an Individual through appropriate pathwaysIs unlikely to be substantially underestimated. The equations specifiedin the Surveillance Requirements for calculating the doses due to theactual release rates of radioactive materials in liquid effluents weredeveloped from the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50,Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113,"Estimating Aquatic Dispersion of Effluents from Accidental and Routine1eactor Releases for the

Purpose

of Implementing Appendix I," April1977.PWR-STS-IB 3/4 11-1 RADIOACTIVE EFFLUENTSBASESThis specification applies to the release of liquid effluents fromeach reactor at the site. For units with shared radwaste treatmentsystems, the liquid effluents from the shared system are proportionedamong the units sharing that system.The OPERABILITY of the liquid radwaste treatment system ensures thatthis system will be available for use whenever liquid effluents requiretreatment prior to release to the environment. The requirement that theappropriate portions of this system be used when specified provides assur-ance that the releases of radioactive materials in liquid effluents willbe kept "as low as is reasonably achievable". This specification imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60of Appendix A to 10 CFR Part 50 and the design objectives of Appendix Ito 10 CFR Part 50. The specified limits governing the use of appropriateportions of the liquid radwaste treatment system were specified as asuitable fraction of the guide set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.3/4.11.1.4 LIQUID HOLDUP TANKSRestricting the quantity of radioactive material contained in thespecified tanks provides assurance that in the event of an uncontrolledrelease of the tank's contents, the resulting dose or dose commitment toan individual in an unrestricted area will not exceed 0.5 rem.3/4.11.2 GASEOUS EFFLUENTS3/4.11.2.1 DOSEThis specification is provided to ensure that the dose at theunrestricted area boundary from gaseous effluents from all units on thesite will be within the annual dose limits of 10 CFR Part 20. Theannual dose limits are the doses associated with the concentrations of10 CFR Part 20, Appendix B, Table II. These limits provide reasonableassurance that radioactive material discharged in gaseous effluents willnot result in the exposure of an individual either within or outside the.unrestricted boundary, to annual average concentrations exceeding thelimits specified in Appendix B, Table II of 10 CFR Part 20 CIO CFRPart 20.106(b)l. For individuals who may at times be within theunrestricted boundary, the occupancy of the individual will be sufficientlylow to compensate for any increase in the atmospheric diffusion factorabove that for the nearest unrestricted area. The specified releaserate limits restrict, at all times, the corresponding gamma and beta dosePWR-STS-IB 3/4 11-2 RADIOACTIVE EFFLUENTSBASESrates.:above.background to an individual at or beyond the unrestrictedboundary to < (500) mrem/ year to the total body or to < (3000) mrem/yearto the skin. These release rate limits also restrict, it all times, thecorresponding thyroid dose rate above background to an infant via thecow-milk-infant pathway to < 15Q0 mrem/year for the nearest cow to theplant.This specification applies to the release of gaseous effluents fromeach reactor at the site. For units with shared radwaste treatmentsystems, the gaseous effluents from the shared system are proportionedamong the units sharing that system.3/4.11.2.2 DOSE, NOBLE GASESThis specification is provided to implement the requirements ofSections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The LimitingCondition for Operation implements the guides set forth in Section II.Bof Appendix I. The ACTION statements provide the required operatingflexibility and at the same time implement the guides set forth inSection IV.A of Appendix I to assure that the releases of radioactivematerial in gaseous effluents will be kept "as low as is reasonablyachievable". The Surveillance Requirements implement the requirementsin Section III.A of Appendix I that conformance with the guides ofAppendix I be shown by calculational procedures based on models and datasuch that the actual exposure of an individual through appropriatepathways is unlikely to be substantially underestimated. The equationsspecified in the Surveillance Requirements for calculating the doses dueto the actual release rates of radioactive noble gases in gaseous effluentswere developed from the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the

Purpose

of Evaluating Compliance with 10 CFR Part 50,Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methodsfor Estimating Atmospheric Transport and Dilspersl.on of Gaseous Effluentsin Routine Releases from Light-Water Cooled Reactors," Revtsion 1, July1977. The specified equations provide for determining the air doses atthe unrestricted area boundary based upon the historical average atmosphericconditions.3/4.11.2.3 DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORMAND RADIONUCLIDES OTHER THAN NOBLE GASESThis specification is provided to Implement the requirements ofSections II.C, III.A and IV.A of Appenditx 1, 10 CFR Part 50. The LimitingPWR-STS-IB 3/4 11-3 RADIOACTIVE EFFLUENTSBASESCondition for Operation are the guides set forth in Section II.C ofAppendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in SectionIV.A of Appendix I to assure that the releases of radioactive materialsin gaseous effluents will be kept "as low as is reasonably achievable".The Surveillance Requirements implement the requirements in Section III.Aof Appendix I that conformance with the guides of Appendix I be shown bycalculational procedures based on models and data such that the actualexposure of an individual through appropriate pathways is unlikely to besubstantially underestimated. The equations specified in the SurveillanceRequirements for calculating the doses due to the actual release ratesof the subject materials were also developed using the methodologyprovided in Regulatory Guide 1.10%, "Calculation of Annual Doses to Manfrom Routine Releases of Reactor Effluents for the

Purpose

of EvaluatingCompliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transportand Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. As with the equationsused in Specification 4.2.2.2.1, these equations also provide for determiningthe actual doses based upon the historical average atmospheric conditions.The release rate specifications for radioiodines, radioactive materialin particulate form and radionuclides other than noble gases are dependenton the existing radionuclide pathways to man, in the unrestricted area.The pathways which were examined in the development of these specificationswere: 12 individual inhalation of airborne radionuclides, 21 depositionof radionuclides onto green leafy vegetation with subsequent consumptionby man, 3) deposition onto grassy areas where mtilk animals and meatproducing animals graze with consumption of the mtlk and meat by man,and 41 deposition on the ground with subsequent exposure of man.3/4.11.2.4 GASEOUS WASTE TREATMENTThe OPERABILITY of the gaseous radwaste treatment system ensures thatthe system will be available for use whenever gaseous effluents requiretreatment prior to release to the environment. The requirement that theappropriate portions of this system be used when specified provides reason-able assurance that the releases of radioactive, materials in liquideffluents will be kept "as low as ts reasonably achievable". This specifi-cation implements the requirements of 10 CFR Part 50.36a, General DesignCriterion 60 of Appendix A to 10 CFR Part 50, and the design objectivesof Appendix I to 10 CFR Part 50. The specified limits governing the useof appropriate portions of the gaseous radwaste treatment system werespecified as a suttable fraction of the guide set forth in Sections II.Band II.C of Appendix I, l0 CFR Part 5Q, for gaseous effluents.PWR-STS-IB 3/4 11 -4 K>RADIOACTIVE EFFLUENTSBASES3/4.11.2.5 EXPLOSIVE GAS MIXTUREThis specification is provided to ensure that the concentration ofpotentially explosive gas mixtures contained in the waste gas holdupsystem is maintained below the flammability limits of hydrogen and oxygen.(Automatic control features are included in the system to prevent thehydrogen and oxygen concentrations from reaching these flammability limits.These automatic control features include isolation of the source ofhydrogen and/or oxygen, automatic diversion to recombiners, or injectionof dilutants to reduce the concentration below the flammability limits.)Maintaining the concentration of hydrogen and oxygen below their flam-mability limits provides assurance that the releases of radioactivematerials will be controlled in conformance with the requirements ofGeneral Design Criterion 60 of Appendix A to 10 CFR Part 50.3/4.11.2.6 GAS STORAGE TANKSRestricting the quantity of radioactivity contained in each gasstorage tank provides assurance that in the event of an uncontrolledrelease of the tanks contents, the resulting total body exposure to anindividual at the nearest exclusion area boundary will not exceed 0.5 rem.This is consistent with Standard Review Plan 15.7.1, "Waste Gas SystemFailure".3/4.11.3 SOLID RADIOACTIVE WASTEThe OPERABILITY of the solid radwaste system ensures that the systemwill be available for use whenever solid radwastes require processing andpackaging prior to being shipped offsite. This specification implementsthe requirements of 10 CFR Part 50.36a and General Design Criteria 60 ofAppendix A to 10 CFR Part 50. The process parameters included in establish-ing the PROCESS CONTROL PROGRAM may include, but are not limited to wastetype, waste pH, waste/lIquid/solIdification agent/catalyst ratios, wasteoil content, waste principal chemical constituents, mixing and curingtimes.PWR-STS-IB 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.1 MONITORING PROGRAMThe radiological monitoring program required by this specificationprovides measurements of radiation and of radioactive materials inthose exposure pathways and for those radionuclides, which lead to thehighest potential radiation exposures of individuals resulting fromthe station operation. This monitoring program thereby supplements theradiological effluent monitoring program by verifying that the measur-able concentrations of radioactive materials and levels of radiation arenot higher than expected on the basis of the effluent measurements andmodeling of the environmental exposure pathways. The initially specifiedmonitoring program will be effective for at least the first three yearsof commercial operation. Following this period, program changes may beinitiated based on operational experience.The detection capabilities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories.The specified lower limits of detection for 1-131 in water, milk and otherfood products correspond to approximately one-quarter of the Appendix Ito 10 CFR Part 50 design objective dose-equivalent of 15 mrem/year foratmospheric releases and 10 mrem/year for liquid releases to the mostsensitive organ and individual. They are based on the assumptions givenin Regulatory Guide 1.109, "Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluents for the

Purpose

of EvaluatingCompliance with 10 CFR Part 50, Appendix I," March 1976, except thechange for an infant consuming 330 liters/year of drinking water insteadof 510 liters/year.3/4.12.2 LAND USE CENSUSThis specification is provided to ensure that changes in the useof unrestricted areas are identified and that modifications to themonitoring program are made if required by the results of this census.This census satisfies the requirements of Section IV.B.3 of Appendix Ito 10 CFR Part 50. Restricting the census to gardens of greater than500 square feet provides assurance that significant exposure pathways vialeafy vegetables will be identified and monitored since a garden of thissize is the minimum required to produce the quantity (26 kg/year) of leafyvegetables assumed in Regulatory Guide 1.109 for consumption by a child.To determine this minimum garden size, the following assumptions wereused, 1) that 20% of the garden was used for growing broad leaf vegetation(i.e., similar to lettuce and cabbage), and 2) a vegetation yield of2 kg/square meter.PWR-STS-I B 3/4 12-1 K>RADIOLOGICAL ENVIRONMENTAL MONITORINGBASES3/4.12.3 CROSSCHECK PROGRAMThe requirement for participation in the EPA crosscheck program isprovided to ensure that independent checks on the precision and accuracyof the measurements of radioactive material in environmental sample matricesare performed as part of the quality assurance program for environmentalmonitoring in order to demonstrate that the results are reasonably valid.IPWR-STS-1B 3/4 12-2 PWR-STS- ISTANDARDTECHNICAL SPECIFICATIONSSECTION 6.0ADMINISTRATIVE CONTROLS I>6.0 ADMINISTRATIVE CONTROLS6.1 RESPONSIBILITY6.1.1 The (Plant Superintendent) shall be responsible for overallunit operation and shall delegate in writing the succession to thisresponsibility during his absence.6.2 ORGANIZATIONOFFSITE6.2.1 The offsite organization for unit management and technicalsupport shall be as shown on Figure 6.2-1.UNIT STAFF6.2.2 The unit organization shall be as shown on Figure 6.2-2 and:a. Each on duty shift shall be composed of at least the minimumshift crew composition shown in Table 6.2-1.b. At least one licensed Operator shall be in the control roomwhen fuel is in the reactor.c. At least two licensed Operators shall be present in thecontrol room during reactor start-up, scheduled reactorshutdown and during recovery from reactor trips.d. An individual qualified in radiation protection proceduresshall be on site when fuel is in the reactor.e. All CORE ALTERATIONS shall be directly supervised by either alicensed Senior Reactor Operator or Senior Reactor OperatorLimited to Fuel Handling who has no other concurrent responsi-bilities during this operation.f. A site Fire Brigade of at least 5 members shall be maintainedonsite at all times. The Fire Brigade shall not include (3)members of the minimum shift crew necessary for safe shutdownof the unit and any personnel required for other essentialfunctions during a fire emergency.PWR-STS-I61 This figure shall show the organizational structureand lines of responsibility for the offsite groupsthat provide technical and management support forthe unit. The organizational arrangement forperformance and monitoring Quality Assurance activ-ities should also be indicated.Figure 6.2-1OFFSITE ORGANIZATIONPWR-STS-I6-2 This figure shall show the organizational structureand lines of responsibility for the unit staff.Positions to be staffed by licensed personnel shouldbe indicated.Figure 6.2-2N.-UNIT ORGANIZATIONPWR-STS-I6-3 Ki'TABLE 6.2-1MINIMUM SHIFT CREW COMPOSITION#LICENSE APPLICABLE MODESCATEGORY 1, 2, 3 & 4 5 & 6SOL 'I 1*OL 2 1Non-Licensed 2 1*Does not includeReactor OperatorALTERATIONS.the licensed Senior Reactor Operator or SeniorLimited to Fuel Handling, supervising CORE#Shift crew composition may be less than the minimum requirementsfor a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodateunexpected absence of on duty shift crew members provided immediateaction is taken to restore the shift crew composition to within theminimum requirements of Table 6.2-1.PWR-STS-I6-4

A .I..V.rTflnt CALMINLZI5IKA I lV W I UL~a6.3 UNIT STAFF QUALIFICATIONSMinimum qualifications for members of the unit staff may be specifiedby use of an overall qualification statement referencing ANSI N18.1-1971or alternately by specifying individual position qualifications. Gener-ally, the first method is preferable; however, the second method isadaptable to those unit staffs requiring special qualification statementsbecause of a unique organizational structure.6.3.1 Each member of the unit staff shall meet or exceed the minimumqualifications of ANSI N18.1-1971 for comparable positions, except forthe (Radiation Protection Manager) who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.6.4 TRAINING6.4.1 A retraining and replacement training program for the unit staffshall be maintained under the direction of the (position title) andshall meet or exceed the requirements and recommendations of Section 5.5of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.6.4.2 A training program for the Fire Brigade shall bethe direction of the (position title) and shall meet orments of Section 27 of the NFPA Code -1975, except fortraining sessions which shall be held at least once per6.5 REVIEW AND AUDITmaintained underexceed the require-Fire Brigade92 days.The method by which independent review and audit of facility operationsis accomplished may take one of several forms. The licensee may eitherassign this function to an organizational unit separate and independentfrom the group having responsibility for unit operation or may utilizea standing committee composed of individuals from within and outside thelicensee's organization.Irrespective of the method used, the licensee shall specify the detailsof each functional element provided for the independent review and auditprocess as illustrated in the following example specifications.6.5.1 UNIT REVIEW GROUP (URG)FUNCTION6.5.1.1 The (Unit Review Group) shallSuperintendent) on all matters relatedfunction to advise the (Plantto nuclear safety.PWR-STS-I6-5 ADMINISTRATIVE CONTROLSCOMPOSITION6.5.1.2 The (Unit Review Group) shall be composed of the:Chairman: (Plant Superintendent)Member: (Operations Supervisor)v Member: (Technical Supervisor)Member: (Maintenance Supervisor)Member: (Plant Instrument and Control Engineer)Member: (Plant Nuclear Engineer)Member: (Health Physicist)ALTERNATES6.5.1.3 All alternate members shall be appointed in writing by the(URG) Chairman to serve on a temporary basis; however, no more than twoalternates shall participate as voting members in CURG) activities atany one time.MEETING FREQUENCY6.5.1.4 The (URG) shall meet at least once per calendar month and asconvened by the (URG) Chairman or his designated alternate.QUORUM6.5.1.5 The minimum quorum of the (URG) necessary for the performance ofthe (URG) responsibility and authority provisions of these technicalspecifications shall consist of the Chairman or his designated alternateand four members including alternates.RESPONSIBILITIES6.5.1.6 The (Unit Review Group) shall be responsible for:a. Review of 1) all procedures required by Specification 6.8 andchanges thereto, 2) any other proposed procedures or changesthereto as determined by the (Plant Superintendent) to affectnuclear safety.b. Review of all proposed tests and experiments that affectnuclear safety.PWR-STS-I6-6 AnTurTCTDATTvv mPJTDnlinuR1L s &aIF~nn Iu a I. %%#I I W_c. Review of all proposed changes to Appendix "A" TechnicalSpecifications.d. Review of all proposed changes or modifications to unit systemsor equipment that affect nuclear safety.e. Investigation of all violations.of the Technical Specificationsincluding the preparation and forwarding of reports coveringevaluation and recommendations to prevent recurrence to the(Superintendent of Power Plants) and to the (Company NuclearReview and Audit Group).f. Review of events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification tothe Commission.g. Review of unit operations to detect potential nuclear safetyhazards.h. Performance of special reviews, investigations or analyses andreports thereon as requested by the (Plant Superintendent) orthe (Company Nuclear Review and Audit Group).i. Review of the Security Plan and implementing procedures andshall submit recommended changes to the (Company Nuclear Reviewand Audit Group).J. Review of the Emergency Plan and implementing procedures andshall submit recommended changes to the (Company Nuclear Reviewand Audit Group).AUTHORITY6.5.1.7 The (Unit Review Group) shall:a. Recommend to the (Plant Superintendent) written approval ordisapproval of items considered under 6.5.1.6(a) through (d)above.b. Render determinations in writing with regard to whether or noteach item considered under 6.5.1.6(a) through (e) aboveconstitutes an unreviewed safety question.c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the (Super-intendent of Power Plants) and the (Company Nuclear Review andAudit Group) of disagreement between the (URG) and the (PlantSuperintendent); however, the (Plant Superintendent) shallhave responsibility for resolution of such disagreementspursuant to 6.1.1 above.PWR-STS-I6-7 AnUrTmtrCTDTTWV rnNTfln 4rW1ILI'SLaI F~ IL V L %,FeII. JRECORDS6.5.1.8 The (Unit Review Group) shall maintain written minutes of each(URG) meeting that, at a minimum, document the results of all (URG)activities performed under the responsibility and authority provisionsof these technical specifications. Copies shall be provided to the(Superintendent of Power Plants) and the (Company Nuclear Review andAudit Group).6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNRAG)FUNCTION6.5.2.1 The (Company Nuclear Review and Audit Group) shall function toprovide independent review and audit of designated activities in theareas of:a. nuclear power plant operationsb. nuclear engineeringc. chemistry and radiochemistryd. metallurgye. instrumentation and controlf. radiological safetyg. mechanical and electrical engineeringh. quality assurance practicesi. (other appropriate fields associated with the unique char-acteristics of the nuclear power plant)PWR-STS-I6-8 ADMINISTRATIVE CONTROLSCOMPOSITION6.5.2.2 The (CNRAG) shall be composed of the:Director: Position Title)Member: Position Title)Member: Position Title)Member: Position Title)Member: (Position Title)ALTERNATES6.5.2.3 All alternate members shall be appointed in writing by the(CNRAG) Director to serve on a temporary basis; however, no more thantwo alternates shall participate as voting members in (CNRAG) activitiesat any one time.CONSULTANTS6.5.2.4 Consultants shall be utilized as determined by the (CNRAG)Director to provide expert advice to the (CNRAG).MEETING FREQUENCY6.5.2.5 The (CNRAG) shall meet at least once per calendar quarterduring the initial year of unit operation following fuel loading andat least once per six months thereafter.QUORUM6.5.2.6 The minimum quorum of the (CNRAG) necessary for the performanceof the (CNRAG) review and audit functions of these technical specifica-tions shall consist of the Director or his designated alternate and (atleast 4 CNRAG) members including alternates. No more than a minorityof the quorum shall have line responsibility for operation of the facility.PWR-STS- I6-9 ADMINISTRATIVE CONTROLSREVIEW6.5.2.7 The (CNRAG) shall review:a. The safety evaluations for 1) changes to procedures, equipmentor systems and 2) tests or experiments completed under theprovision of Section 50.59, 10 CFR, to verify that such actionsdid not constitute an unreviewed safety question.b. Proposed changes to procedures, equipment or systems whichinvolve an unreviewed safety question as defined in Section50.59, 10 CFR.c. Proposed tests or experiments which involve an unreviewedsafety question as defined in Section 50.59, 10 CFR.d. Proposed changes to Technical Specifications or this OperatingLicense.e. Violations of codes, regulations, orders, Technical Specifications,license requirements, or of internal procedures or instructionshaving nuclear safety significance.f. Significant operating abnormalities or deviations from normaland expected performance of unit equipment that affect nuclearsafety.g. Events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Commission.h. All recognized indications of an unanticipated deficiency insome aspect of design or operation of structures, systems,or components that could affect nuclear safety.i. Reports and meetings minutes of the (Unit Review Group).PWR-STS-I6-10

al ., y £l e i sar jfnSj lns eADJMlNlZbAl M 1L oUtI MUL-2AUDITS6.5.2.8 Audits of unit activities shall be performed under the cognizanceof the (CNRAG). These audits shall encompass:a. The conformance of unit operation to provisions containedwithin the Technical Specifications and applicable licenseconditions at least once per 12 months.b. The performance, training and qualifications of the entireunit staff at least once per 12 months.c. The results of actions taken to correct deficiencies occurringin unit equipment, structures, systems or method of operationthat affect nuclear safety at least once per 6 months.d. The performance of activities required by the OperationalQuality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.e. The Emergency Plan and implementing procedures at least onceper 24 months.f. The Security Plan and implementing procedures at least onceper 24 months.g. Any other area of unit operation considered appropriate bythe (CNRAG) or the (Vice President Operations).h. The Fire Protection Program and implementing procedures atleast once per 24 months.i. An independent fire protection and loss prevention inspectionand audit shall be performed annually utilizing either qualifiedoffsite licensee personnel or an outside fire protection firm.J. An inspection and audit of the fire protection and loss preven-tion program shall be performed by an outside qualified fireconsultant at intervals no greater than 3 years.1. The radiological environmental monitoring program and theresults there of at least once per 12 months.PWR-STS-I6-11

.-.-.. n a ,r ihnaTrilr cAPUMr4LlRKlAVrL %u#IIVL4AUTHORITY6.5.2.9 The (CNRAG) shall report to and advise the (Vice PresidentOperations) on those areas of responsibility specified in Sections6.5.2.7 and 6.5.2.8.RECORDS6.5.2.10 Records of (CNRAG) activities shall be prepared, approved anddistributed as indicated below:a. Minutes of each (CNRAG) meeting shall be prepared, approvedand forwarded to the (Vice President-Operations) within 14days following each meeting.b. Reports of reviews encompassed by Section 6.5.2.7 above, shallbe prepared, approved and forwarded to the (Vice President-Operations) within 14 days following completion of the review.c. Audit reports encompassed by Section 6.5.2.8 above, shall beforwarded to the (Vice President-Operations) and to themanagement positions responsible for the areas audited within30 days after completion of the audit.6.6 REPORTABLE OCCURRENCE ACTION6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:a. The Commission shall be notified and/or a report submittedpursuant to the requirements of Specification 6.9.b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notificationto the Commission shall be reviewed by the (URG) and submittedto the (CNRAG) and the (Superintendent of Power Plants).PWR-STS-I6-12 ADMINISTRATIVE CONTROLS6.7 SAFETY LIMIT VIOLATION6.7.1 The following actions shall be taken in the event a Safety Limitis violated:a. The unit shall be placed in at least HOT STANDBY withinone hour.b. The Safety Limit violation shall be reported to the Commission,the (Superintendent of Power Plants) and to the (CNRAG) within24 hours.c. A Safety Limit Violation Report shall be prepared. The reportshall be reviewed by the (URG). This report shall describe(1) applicable circumstances preceding the violation, (2)effects of the violation upon facility components, systems orstructures, and (3) corrective action taken to prevent recurrence.d. The Safety Limit Violation Report shall be submitted to theCommission, the (CNRAG) and the (Superintendent of PowerPlants) within 14 days of the violation.6.8 PROCEDURES6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:a. The applicable procedures recommended in Appendix "A" ofRegulatory Guide 1.33, Revision 2, February 1978.b. The radiological environmental monitoring program.c. Refueling operations.d. Surveillance and test activities of safety related equipment.e. Security Plan implementation.f. Emergency Plan implementation.g. Fire Protection Program implementation.h. Offsite releases of gaseous and liquid effluents containingradioactive materials.i. The PROCESS CONTROL PROGRAM for solidification of radioactivewaste.PWR-STS-I6-13

smlrCTAIrTt~r PMKTOM CMALJ1llKM1LVC W111rUL-6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall bereviewed by the (URG) and approved by the (Plant Superintendent) priorto implementation and reviewed periodically as set forth in administrativeprocedures..6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:a. The intent of the original procedure is not altered.b. The change is approved by two members of the plant managementstaff, at least one of whom holds a Senior Reactor Operator'sLicense on the unit affected.c. The change is documented, reviewed by the (URG) and approved bythe (Plant Superintendent) within 14 days of implementation.6.9 REPORTING REQUIREMENTSROUTINE REPORTS AND REPORTABLE OCCURRENCES6.9.1 In addition to the applicable reporting requirements of Title 10,Code of Federal Regulations, the following reports shall be submittedto the Director of the Regional Office of Inspection and Enforcementunless otherwise noted.STARTUP REPORT6.9.1.1 A summary report of plant startup and power escalation testingshall be submitted following (1) receipt of an operating license, (2)amendment to the license involving a planned increase in power level,(3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that mayhave significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.6.9.1.2 The startup report shall address each of the tests identified inthe FSAR and shall include a description of the measured values of theoperating conditions or characteristics obtained during the test programand a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactoryoperation shall also be described. Any additional specific detailsrequired in license conditions based on other commitments shall be in-cluded in this report.PWR-STS-I 6-14 K>ADMINISTRATIVE CONTROLS6.9.1.3 Startup reports shall be submitted within (1) 90 days followingcompletion of the startup test program, (2) 90 days following resumptionor commencement of commercial power operation, or (3) 9 months followinginitial criticality, whichever is earliest. If the Startup Report doesnot cover all three events (i.e., initial criticality, completion ofstartup test program, and resumption or commencement of commercial poweroperation), supplementary reports shall be submitted at least everythree months until all three events have been completed.ANNUAL REPORTSY6.9.1.4 Annual reports covering the activities of the unit as describedbelow for the previous calendar year shall be submitted prior to March 1of each year. The initial report shall be submitted prior to March I ofthe year following initial criticality.6.9.1.5 Reports required on an annual basis shall include:a. A tabulation on an annual basis of the number of station,utility and other personnel (including contractors) receivingexposures greater than 100 mrem/yr and their associated manrem exposure according to work and job functions,= e.g.,reactor operations and surveillance, inservice inspection,routine maintenance, special maintenance (describe maintenance),waste processing, and refueling. The dose assignment tovarious duty functions may be estimates based on pocketdosimeter, TLD, or film badge measurements. Small exposurestotalling less than 20% of the individual total dose need notbe accounted for. In the aggregate, at least 80% of the totalwhole body dose received from external sources shall be assignedto specific major work functions.b. The results of steam generator tube inservice inspectionsperformed during the report period. (CE, W-& B&W units only).c. The results of the core barrel movement monitoring activitiesperformed during the report period. (CE units only).d. (Any other unit unique reports required on an annual basis.)YA single submittal may be made for a multiple unit station. Thesubmittal should combine those sections that are common to all unitsat the station.This tabulation supplements the requirements of 520.407 of 10 CFRPart 20.PWR-STS-I6-15 ADMINISTRATIVE CONTROLSANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT196.9.1.6 Routine radiological environmental operating reports coveringthe operation of the unit during the previous calendar year shall besubmitted prior to May 1 of each year. The initial report shall besubmitted prior to May 1 of the year following initial criticality.6.9.1.7 The annual radiological environmental operating reports shallinclude summaries, interpretations, and statistical evaluation of theresults of the radiological environmental surveillance activities forthe report period, including a comparison with preoperational studies,operational controls (as appropriate), and previous environmental surveil-lance reports and an assessment of the observed impacts of the plantoperation on the environment. The reports shall also include the resultsof land use censuses required by Specification 3.12.2. If harmful effectsor evidence of irreversible damage are detected by the monitoring, thereport shall provide an analysis of the problem and a planned course ofaction to alleviate the problem.The annual radiological environmental operating reports shall includesummarized and tabulated results in the format of Table 6.9-1 of allradiological environmental samples taken during the report period. Inthe event that some results are not available for inclusion with thereport, the report shall be submitted noting and explaining the reasonsfor the missing results. The missing data shall be submitted as soon aspossible in a supplementary report.The reports shall also include the following: a summary description ofthe radiological environmental monitoring program including sampling methodsfor each sample type, size and physical characteristics of each sampletype, sample preparation methods, analytical methods, and measuring equip-ment used; a map of all sampling locations keyed to a table giving distancesand directions from one reactor; the results of land use censuses requiredby the Specification 3.12.2; and the results of licensee participation inthe Environmental Protection Agency's Environmental Radioactivity LaboratoryIntercomparisons Studies (Crosscheck) Program required by Specification 3.12.3.SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-V6.9.1.8 Routine radioactive effluent release reports covering theoperation of the unit during the previous 6 months of operation shall besubmitted within 60 days after January 1 and July 1 of each year. Theperiod of the first report shall begin with the data of initial criticality.3/ A single submittal may be made for a multiple unit station. Thesubmittal should combine those sections that are common to allunits at the station; however, for units with separate radwastesystems, the submittal shall specify the releases of radioactivematerial from each unit.)WR-STS- I6-16 (TABLE 6.9-1ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMMARY* -oIn--Nam of FacilityDocmet No.__Location of Facility1County. Staft)Reporting Period-, Y Y V I TMedium or PathwaySaMled(Unit of Measurement)Type andTotl Numberof AndyePomedLower LimitofDetecionILLD)All Indicator L -eionsMRm If)ppbLocation wh Highest Annual MeinNeDistance and DirectionMesn (fibRanpeontrol LonsMe (f),Rngb4 4 I 44 4.C.2Ci-J a-.Ew1Air Particulates(pCi/m3)FishpCi/kg (dry weight)Gross p 4187-Spec. 32.137C.140000.0030.0030.0030.0020.00038089sr90Sr7-Spec. 8137C.40400.081200/312)(0.05-2.0)0.05(4/24)(0.03.0.13)0.03(2/24)10.01.0.08)<LLD<LLD<LLD<LLD120(314)(90.200)Middletown5 miles 340"Smithvl le2.5 miles 16Podunk4.0 miles 270QRiver Mile 35Podunk River0.10(5152)(0.082.0)0.08 (2/4)(0.03-0.13)0.05 (2/4)(0.01Q.008)<LLD<LLDSee column 40.08(8/104)(0.05-1.40)<LLD0.02(1/8)<LLD<LLD9011/4)<LLD<LLDNurnberofREPORTABLE,,OCCURRENCMI40°(00-0134Cs60Co80Nominal Lower Limit of Detaction (LLD) as defined in table notation a. of Table 4.12.1 of Specification 4.12.1.1.IIen nd rang based upon detectable measurements only. Fraction of detectable measurements at speflied lecetiona Is Indicated In parentheses. idNote: The example daft ae provided for Illustrative purposes onl ADMINISTRATIVE CONTROLS6.9.1.9 The radioactive effluent release reports shall include asummary of the quantities of radioactive liquid and gaseous effluentsand solid waste released from the unit as outlined in Regulatory Guide1.21, "Measuring, Evaluating, and Reporting Radioactivity in SolidWastes and Releases of Radioactive Materials in Liquid and GaseousEffluents from Light-Water-Cooled Nuclear Power Plants," with datasummarized on a quarterly basis following the format of Appendix Bthereof.The radioactive effluent release reports shall include a summary ofthe meteorological conditions concurrent with the release of gaseouseffluents during each quarter as outlined in Regulatory Guide 1.21,with data summarized on a quarterly basis following the format ofAppendix B thereof.The radioactive effluent release reports shall include an assessment ofthe radiation doses from radioactive effluents to individuals due totheir activities inside the unrestricted area boundary (Figure 5.1-1)during the report period. All assumptions used in making theseassessments (e.g., specific activity, exposure time and location) shallbe included in these reports.The radioactive effluent release reports shall include the followinginformation for all unplanned offsite releases of radioactive materialsin gaseous and liquid effluents:a. A description of the event and equipment involved.b. Cause(sl for the unplanned release.c. Actions taken to prevent recurrence.d. Consequences of the unplanned release.The radioactive effluent release reports shall include an assessment ofradiation doses from the radioactive ltqutd and gaseous effluentsreleased from the unit during each calendar quarter as outlined in'Regulatory Gutde 1.21. In addition, the unrestricted area boundarymaximum noble gas gamma air and beta air doses shall be evaluated. Themeteorological conditions concurrent with the releases of effluentsshall be used for determining the gaseous pathway doses. The assessmentof radiation doses shall be performed in accordance with NUREG-0133.PWR-STS-I6-18 ADMINISTRATIVE CONTROLSMONTHLY REACTOR OPERATING REPORT6.9.1.10 Routine reports of operating statistics and shutdown experienceshall be submitted on a monthly basis to the Director, Office ofManagement and Program Analysis, U.S. Nuclear Regulatory Commission,Washington, D.C. 20555, with a copy to the Regional Office of Inspec-tion and Enforcement, no later than the 15th of each month followingthe calendar month covered by the report.REPORTABLE OCCURRENCES6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13below, including corrective actions and measures to prevent recurrence,shall be reported to the NRC. Supplemental reports may be required tofully describe final resolution of occurrence. In case of corrected orsupplemental reports, a licensee event report shall be completed andreference shall be made to the original report date.PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP6.9.1.12 The types of events listed below shall be reported within 24hours by telephone and confirmed by telegraph, mailgram, or facsimiletransmission to the Director of the Regional Office, or his designateno later than the first working day following the event, with a writtenfollowup report within 14 days. The written followup report shallinclude, as a minimum, a completed copy of a licensee event report form.Information provided on the licensee event report form shall be supple-mented, as needed, by additional narrative material to provide completeexplanation of the circumstances surrounding the event.a. Failure of the reactor protection system or other systemssubject to limiting safety system settings to initiate therequired protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safetysystem setting in the technical specifications or failureto complete the required protective function.b. Operation of the unit or affected systems when any parameteror operation subject to a limiting condition for operationis less conservative than the least conservative aspect of thelimiting condition for operation established in the technicalspecifications.c. Abnormal degradation discovered in fuel cladding, reactorcoolant pressure boundary, or primary containment.PWR-STS-I6-19 ADMINISTRATIVE CONTROLSd. Reactivity anomalies involving disagreement with the predictedvalue of reactivity balance under steady state conditionsduring power operation greater than or equal to 1% Ak/k; acalculated reactivity balance indicating a SHUTDOWN MARGINless conservative than specified in the technical specifica-tions; short-term reactivity increases that correspond toa reactor period of less than 5 seconds or, if subcritical,an unplanned reactivity insertion of more than 0.5% Ak/k; oroccurrence of any unplanned criticality.e. Failure or malfunction of one or more components which preventsor could prevent, by itself, the fulfillment of the functionalrequirements of system(s) used to cope with accidents analyzedin the SAR,f. Personnel error or procedural inadequacy which prevents or couldprevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed inthe SAR.g. Conditions arising from natural or man-made events that, as adirect result of the event require unit shutdown, operationof safety systems, or other protective measures required bytechnical specifications.h. Errors discovered in the transient or accident analyses or inthe methods used for such analyses as described in the safetyanalysis report or in the bases for the technical specificationsthat have or could have permitted reactor operation in a mannerless conservative than assumed in the analyses.i. Performance of structures, systems, or components that requiresremedial action or corrective measures to prevent operation ina manner less conservative than assumed in the accidentanalyses in the safety analysis report or technical specifica-tions bases; or discovery during unit life of conditions notspecifically considered in the safety analysis report ortechnical specifications that require remedial action or cor-rective measures to prevent the existence or development of anunsafe condition.J. Occurrence of an unusual or important event that causes asignificant environmental impact, that affects potentialenvironmental impact from unit operation, or that has highpublic or potential public interest concerning environmentalimpact from unit operation.k. Occurrence of radioactive material contained in liquid or gaseousholdup tanks in excess of that permitted by the limiting condi-tion for operation established in the technical specifications.PWR-STS- I6-20 ADMINISTRATIVE CONTROLSTHIRTY DAY WRITTEN REPORTS6.9.1.13 The types of events listed below shall be the subject ofwritten reports to the Director of the Regional Office within thirtydays of occurrence of the event. The written report shall include, as aminimum, a completed copy of a licensee event report form. Informationprovided on the licensee event report form shall be supplemented, asneeded, by additional narrative material to provide complete explanationof the circumstances surrounding the event.a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative thanthose established by the technical specifications but which donot prevent the fulfillment of the functional requirements ofaffected systems.b. Conditions leading to operation in a degraded mode permittedby a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.c. Observed inadequacies in the implementation of administrativeor procedural controls which threaten to cause reduction ofdegree of redundancy provided in reactor protection systemsor engineered safety feature systems.d. Abnormal degradation of systems other than those specifiedin 6.9.1.12.c above designed to contain radioactive materialresulting from the fission process.e. An unplanned offsite release of 1) more than 1 curie ofradioactive material in liquid effluents, 2) more than150 curies of noble gas in gaseous effluents, or 3) morethan 0.05 curies of radioiodine in gaseous effluents. Thereport of an unplanned offsite release of radioactivematerial shall include the following information:1. A description 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.PWR-STS-I6-21 ADMINISTRATIVE CONTROLSf. Measured levels of radioactivity in an environmental samplingmedium determined to exceed the reporting level values ofTable 6.9-2 when averaged over any calendar quarter samplingperiod. When more than one of the radionuclides in Table 6.9-2are detected in the sampling medium, this report shall besubmitted if:concentration j1) + concentration (2) + .... >1.0iMIT level (1) limit Tevel (2)When radionuclides other than those in Table 6.9-2 are detectedand are the result of plant effluents, this report shall besubmitted if the potential annual dose to an individual isequal to or greater than the calendar year limits of Specifica-tions 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is notrequired if the measured level of radioactivity was not theresult of plant effluents; however, in such an event, thecondition shall be reported and described in the AnnualRadiological Environmental Operating Report.SPECIAL REPORTSSpecial reports may be required covering inspections, test and main-tenance activities. These special reports are determined on an indi-vidual basis for each unit and their preparation and submittal aredesignated in the Technical Specifications.6.9.2 Special reports shall be submitted to the Director of the Officeof Inspection and Enforcement Regional Office within the time periodspecified for each report.PWR-STS-I6-22 C( 'NTABLE 6.9-2REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES(nI-4(AReporting Levels*9 -Airborne Particulateor Gases (pCI/M3)AnalysisWaterFish(pCi/Kg, wet)Milk(pC/l)Vegetables(pCi/Kg, wet)14 .9 4 4 4cmH-3Mn-54Fe-59Co-58Co-60Zn-65Zr-Nb-951-131Cs-134Cs-137Ba-La-l 403 x 1041 x 1034 x 1021 x 1033 x 1023 x 1024 x 102230502 x 1023 x 1041 x 1043 x 1041 x 1042 x 1041 x 1032 x 1030.91020360703 x 102I x 1021 x 1032 x 1032 x to2 3 x I 1 4

&tRv&,*P-rnATriUD rnuirnn cAU~llr lllVC r~AIiIEUL06.10 RECORD RETENTIONIn addition to the applicable record retention requirements of Title 10,Code of Federal Regulations, the following records shall be retained forat least the minimum period.indicated.6.10.1 The following records shall be retained for at least five years:a. Records and logs of unit operation covering time intervalat each power level.b. Records and logs of principal maintenance activities, inspections,repair and replacement of principal items of equipment relatedto nuclear safety.c. ALL REPORTABLE OCCURRENCES submitted to the Commission.d. Records of surveillance activities, inspections and calibrationsrequired by these Technical Specifications.e. Records of changes made to the procedures required by Specifica-tion 6.8.1.f. Records of radioactive shipments.g. Records of sealed source and fission detector leak tests andresults.h. Records of annual physical inventory of all sealed sourcematerial of record.6.10.2 The following records shall be retained for the duration of theUnit Operating License:a. Records and drawing changes reflecting unit design modifica-tions made to systems and equipment described in the FinalSafety Analysis Report.b. Records of new and irradiated fuel inventory, fuel transfersand assembly burnup histories.c. Records of radiation exposure for all individuals enteringradiation control areas.d. Records of gaseous and liquid radioactive material releasedto the environs.PWR-STS -I6-24 AnUThtfTCDA'TMvr efnMTDnl Ce. Records of transient of operational cycles for those unit com-ponents identified in Table 5.7-1.f. Records of reactor tests and experiments.g. Records of training and qualification for current members ofthe unit staff.h. Records of in-service inspections performed pursuant to theseTechnical Specifications.i. Records of Quality Assurance activities required by the QAManual.J. Records of reviews performed for changes made to procedures orequipment or reviews of tests and experiments pursuant to 10CFR 50.59.k. Records of meetings of the (URG) and the (CNRAG).6.11 RADIATION PROTECTION PROGRAMProcedures for personnel radiation protection shall be prepared consistentwith the requirements of 10 CFR Part 20 and shall be approved, maintainedand adhered to for all operations involving personnel radiation exposure.6.12 HIGH RADIATION AREA (OPTIONAL)6.12.1 In lieu of the "control device" or "alarm signal" required byparagraph 20.203(c)(2) of 10 CFR 20, each high radiation area in whichthe intensity of radiation is greater than 100 mrem/hr but less than1000 mrem/hr shall be barricaded and conspicuously posted as a highradiation area and entrance thereto shall be controlled by requiringissuance of a Radiation Work Permit*. Any individual or group ofindividuals permitted to enter such areas shall be provided with oraccompanied by one or more of the following:a. A radiation monitoring device which continuously indicatesthe radiation dose rate in the area.*Health Physics personnel or personnel escorted by Health Physics per-sonnel in accordance with approved emergency procedures shall be exemptfrom the RWP issuance requirement during the performance of theirradiation protection duties, provided they comply with approved radia-tion protection procedures for entry into high radiation areas.PWR-STS-I6-25 I' a..tfl* ,A-DMINISTKAI LY LCUN I KULQb. A radiation monitoring device which continuously integrates theradiation dose rate in the area and alarms when a preset inte-grated dose is received. Entry into such areas with thismonitoring device may be made after the dose rate level in thearea has been established and personnel have been made knowl-edgeable of them.c. An individual qualified in radiation protection procedures whois equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positivecontrol over the activities within the area and shall performperiodic radiation surveillance at the frequency specified bythe facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1, above, shall also apply to each highradiation area in which the Intensity of radiation is greater than1000 mrem/hr. In addition, locked doors shall be provided to preventunauthorized entry into such areas and the keys shall be maintainedunder the administrative control of the Shift Supervisor on duty and/orthe Plant Health Physicist.PWR-STS-I6-26 ENCLOSURE NO. 2APPENDIX I TECHNICAL SPECIFICATIONSLICENSEE SUBMITTAL DATES60 DaysFarl eyHatch 1/2120 Days150 Days180 DaysBig Rock PointGinnaHaddam NeckLa CrosseOyster CreekSan OnofreSurry 1/2Yankee RoweArkansas 1Brunswick 1/2Crystal RiverDresden 1/2/3FitzPatrickIndian Point 1/2/3Millstone 1/2MonticelloNine Mile PointOconee 1/2/3Peach Bottom 2/3Pilgrim 1Quad Cities 1/2Robinson 2Turkey Point 3/4Vermont YankeeZion 1/2Beaver ValleyBrowns Ferry 1/2/3Calvert Cliffs 1/2Cook 1/2CooperDavis BesseDuane ArnoldFort CalhounHumboldt BayKewauneeMaine YankeeNorth Anna 1/2PalisadesPoint Beach 1/2Prairie Island 1/2Rancho SecoSalem 1St. Lucie 1Three Mile Island 1/2Trojan

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NRC Generic Letter 1978-25: Difference between revisions

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NRC Generic Letter 1978-25: Difference between revisions

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