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| {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:0956A" PROPOSED CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNIT NOS.1 AND 2'I TECHNICAL SPECIFICATIONS 860i280i24 860i27 PDR ADOCN 050003iS P~DR TABLE 3.3-3 (Continued) | | {{#Wiki_filter:}} |
| ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION 3.CONTAINMENT ISOLATION a.Phase"A" Isolation 1)Manual 2)From Safety Injection Automatic Actuation Logic 1,2,3,4 1,2,3,4 18 b.Phase"B" Isolation 1)Manual 2)Automatic Actuation Logic ,3)Containment Pressure-High-High 2 2 1,2,3,4 1,2,3,4 1,2,3 18 13 16 c.Purge and Exhaust Isolation*
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| 1)Manual 2)Containment Radioactivity-High Train A (VRS 1101~ERS 1301~ERS 1305)3)Containment Radioactivity-High Train B (VRS 1201~ERS 1401~ERS 1405)1,2,3,4 1,2,3,4 1,2,3,4 17 17 17*This specification only applies during purge.
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| I f l.
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| TABLE 3.3-4 (Continued)
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| ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT 2.Containment Radioactivity-High Train A (VRS-1101, ERS-1301, ERS-1305)TRIP SETPOINT See Table 3.3-6 ALLOWABLE VALUES Not Applicable 3.Containment Radioactivity-High Train B (VRS-1201, ERS-1401, ERS-1405)See Table 3.3-6 Not Applicable 4.STEAM LINE ISOLATION a.Manual b.Automatic Actuation Logic c.Containment Pressure-High-High d.Steam Flow In Two Steam Lines--High Coincident with T ava Low-Low or Steam Line iressure Low Not Applicable Not Applicable
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| +2.9 psig 1.42 x 10 lbs/hr from 0%6 load to 2(%load.Linear from 1.42 x 10 1)s/hr at 20%load to 3.88 x 10 lbs/hr at 100%load.Not Applicable Not Applicable 3 psst g 1.56 x 10 lbs/hr from 0%6 load to 20%logd.Linear from 1.56 x 10 lbs/hg at 20%load to 3.93 x 10 lbs/hr at 100%load.T>541 F avg 600 psig steam line pressure T>539 F avg-+580 psig steam line pressure 5.TURBINE TRIP AND FEEDWATER ISOLATION a.Steam Generator Water Level--High-High 67%of narrow-range instrument
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| 'pan each steam generator~68%of narrow-range instrument span each steam generator A)
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| TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
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| OPERATION MODE/INSTRUMENT MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT ACTION 1.Modes 1, 2, 3, 6 4 A)Area Monitors i)Upper Containment (VRS 1101/1201)
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| N/A C 54 mR/hr 21 B)Process Monitors i)Particulate Channel (ERS 1301/1401)
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| N/A C 2.52 uCi 20 ii)Noble Gas Channel (ERS 1305/1405)
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| N/A~4.4 x 10 uCi CC 20 C)Noble Gas Effluent Monitors i)Unit Vent Effluent Monitor a)Low Range (VRS 1505)(See T/S Section 3.3.3.10) l.~l TABLE 3.3-6 (Cont'd)RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
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| O 8 OPERATION MODE/INSTRUMENT MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT ACTION C R M ii)Gland Steam Condenser Vent Monitor a)Low Range (SRA 1805)(See T/S Section 3.3.3.10)iii)Steam Jet Air Ejector Vent Monitor a)Low Range (SRA 1905)(See T/S Section 3.3.3.10)2.Mode 6 A)Train A~I any 2/3 channels 22 i)Containment Area Radiation Channel (VRS 1101)N/A<54 mR/hr ii)Particulate Channel (ERS 1301)iii)Noble Gas Channel (ERS 1305)N/A N/A~2.52 uCi 4.4 x 10 uCi 3 CC B)Train B any 2/3 channels 22 S ft 0 i)Containment Area Radiation Channel (VRS 1201)ii)Particulate Channel (ERS 1401)4 N/A N/A~54 mR/hr 2.52 uCi fi'(1 TABLE 3.3-6 (Cont')O O 0 I g OPERATION MODE/INSTRUMENT iii)Noble Gas Channel (ERS 1405)MINIMUM CHANNELS OPERABLE ALARM SETPOINT N/A RADIATION MONITORING INSTRUMENTATION (OPERABILITY.
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| BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
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| TRIP SETPOINT+4.4 x 10 uCi CC ACTION 22 3 Mode***A)Spent Fuel Storage (RRC-330)15 mR/hr 15 mR/hr~***With fuel in storage pool or building.+This specification applies only during purge.0
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| TABLE 3.3-6 (Continued)
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| TABLE NOTATION ACTION 20-With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply.with the ACTION requirements of Specification 3.4.6.1.ACTION 21-With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.ACTION 22-Wi'th the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9.This ACTION is not required during the performance of containment integrated leak rate test.D.C.COOK-UNIT 1 3/4 3-37 Amendment No.
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| 4 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATION MODE/INSTRUMENT 1.Modes 1, 2, 3, a 4 A)Area Monitors CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED i)Upper Containment (VRS 1101/1201) 1, 2, 3, 4 B)Process Monitors i)Particulate Channel (ERS 1301/1401)
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| $*1, 2, 3, 4 ii)Noble Gas Channel (ERS 1305/1405)
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| M 1, 2, 3, 4 C)Noble Gas Effluent Monitors i)Unit Vent Effluent Monitors a)Iow Range (VRS 1505)(See Table 4.3-9, Item 3.a, 4a, 5a) 0 k TABLE 4.3-3 (Cont'd)RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS C R H OPERATION MODE/INSTRUMENT ii)Gland Steam Condenser Vent Monitor CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST'MODES FOR WHICH SURVEILLANCE RE UIRED a)Low Range (SRA 1805)(See Table 4.3-9 Item 6.a)iii)Steam Jet Air Ejector Vent Monitor a)Low Range (SRA 1905)(See Table 4.3-9, Item 2.a)2.Mode 6 A)Train A i)Containment Area Radiation Channel (VRS 1101)h ii)Particulate Channel (ERS 1301)$*iii)Noble Gas Channel (ERS 1305)S*h1 B)Train B i)Containment Area Radiation Channel (VRS 1201)R 0 ii)Particulate Channel (ERS 1401) 0~'
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| TABLE 4.3-3 (Cont'd)RADIATION MONITORING XNSTRUMENTATION SURVEILLANCE RE UIREMENTS O O 0 I C R M OPERATION MODE/INSTRUMENT iii)Noble Gas Channel (ERS 1405)CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED 2.Mode**A)Spent Fuel Storage (RRC-330)M 9 8 Q ft 0*To include SOURCE CHECK per T/S Section 1.27.**With fuel in storage pool or building.
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| ~I 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1)the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2)the specified coincidence logic is maintained, 3)sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4)sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
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| The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
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| The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.
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| The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
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| The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.No credit was taken in the analyses for those channels with response times indicated as not applicable.
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| Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.Sensor response time verification may be demonstrated by either 1)in place, onsite or offsite test measurements or 2)utilizing replacement sensors with certified response times.3/4.3.3 MONITORING INSTRUMENTATION 3/4.3'.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1)the radiation levels are continually measured in the areas served by the individual channels and 2)the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.D.C.COOK-UNIT 1 B 3/4 3-1 Amendment No.
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| E~'
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| INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
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| Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed.INSTRUMENT ALARM/TRIP SETPOINT MEASUREMENT RANGE*1)Area Monitor-Upper Containment (VRS 1101/1201)
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| The monitor trip setpoint is based on 10 CFR 20 limits.A homogeneous mixture of the containment atmosphere is assumed.The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.10 R/hr to 10R/hr.2)Process Monitor Particulate (ERS 1301/1401) 3)Process Monitor Noble Gas (ERS 1305/1405)
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| -4 The monitor trip setpoint 1.5 x 10 uCi to 7.5 is based on 10 CFR 20 uCi.The setpoint.was determined using the Noble gas setpoint and historical monitor.data of the ratio of particulates to Noble gases.-7 The monitor trip setpoint 1 x 10 2 uCi/cc to is based on 10 CFR 20 4 x 10 uCi/cc limits.A homogeneous mixture of the containment atmosphere is assumed.The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate.*This is the minimum required sensitivity of the instrument.
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| Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
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| D.C.COOK-UNIT 1 B 3/4 3-la Amendment No.
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| INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
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| INSTRUMENT ALARM/TRIP SETPOINT MEASUREMENT RANGE*4)Noble Gas Unit Vent Monitors a)Low Range (VRS 1505)See Bases Section 3/4.3.3.10 2 lx10 uCi/cc to 4xl0 uCi/cc.5)Gland Steam Condenser Vent Noble Gas Monitor a)Low Range (SRA 1805)6)Steam Jet Air Ejector Vent Noble Gas Monitor a)Low Range (SRA 1905)See Bases Section 3/4.3.3.10 See Bases Section 3/4.3.3.10 2 lx10 uCi/cc to 4x10 uCi/cc.-7-2 lx10 uCi/cc to 4x10 uCi/cc.*This is the minimum required sensitivity of the instrument.
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| Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
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| D.C.COOK-UNIT 1 B 3/4 3-lb Amendment No.
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| 1 1 INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
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| INSTRUMENT 7)Spent Fuel, Storage (RRC-330)ALARM/TRIP SETPOINT The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a)(2)MEASUREMENT RANGE*-1 4 lx10 mR/hr to lxl0 mR/hr The Radiation Monitoring Instrumentation Surveillance Requirements per Table 4.3-3 are based on the following interpretation:
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| 1)The CHANNEL FUNCTIONAL TEST is successfully accomplished by the injection of a simulated signal into the channel, as close to the detector as practical, to verify the channel'.s alarm and/or trip function only.2)The CHANNEL CALIBRATION as defined in T/S Section 1.9 permits the"known values" generated from radioactive calibration sources to be substituted with"known values" represented by simulated signals for that subset of"known values" required for calibration and not practical to generate using the radioactive calibration sources.*This is the minimum required sensitivity of the instrument.
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| .Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
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| D.C.COOK-UNIT 1 B 3/4 3-lc Amendment No.
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| C INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained form use of this system accurately represent the spatial neutron flux distribution of the reactor core.3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important'to safety.This capability is required to permit comparison of the measured response to that used in the design basis for the facility.3/4.3.3.4 METEOROLCGICAL INSTRUMENTATION The OPERABILiTY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a re'suit of routine or accidental release of radioactive materials to the atmosphere.
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| This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.D.C.COOK-UNIT 1 B 3/4 3-2 Amendment No.
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| i (
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| TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Operable Applicability Action 1.Gross Radioactivity Monitors Providing Automatic Release Termination a.Liquid Radwaste Effluent Line (1-R-18)At times of release 23 b.Steam Generator Blowdown Line (1-R-19)At times of release 24 c.Steam Generator Blowdown Treatment Effluent (1-R-24)At times of release 24 2.Gross Radioactivity Monitors Not Providing Automatic Release Termination a.Service Water System Effluent Line (1<<R-20, 1-R-28)3.Continuous Composite Sampler Flow Monitor (1)per train At a'1 times 25 a.Turbine Building Sump Effluent Line At all times 25 4.Flow Rate Measurement Devices a.Liquid Radwaste Line(RFI-285) b.Discharge Pipes*c.Steam Generator Blowdown Treatment Effluent (1-DFI-353)
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| At times of release At all times At times of release 26 NA 26*Pump curves and valve settings may be utilized to estimate flow;in such cases, Action Statement 26 is not applicable.
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| D.C.COOK-UNIT 1 3/4 3-58 Amendment No.
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| l s' TABLE 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument (Instrument 5)Minimum Channels Operable A plicabilit Action 1.Waste Gas Holdup System Explosive Gas Monitoring System a.Hydrogen Monitor (QC-31)b.Oxygen Monitor (QC-31, QC-370)(1)(2)30 29 2.Condenser Evacuation System a.Noble Gas Activity Monitor (SRA-1905) b.Flow Rate Monitor (SFR-401)(1-MR-0543 and/or.SRA-1910)
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| (1)(1)=(1)28 27 27 3~Unit Vent, Auxiliary Building Ventilation System a.Noble Gas Activity Monitor (VRS-1505) b.Iodine Sampler Cartridge for VRS-1503 c.Particulate Sampler Filter for VRS-1501 d.Effluent'System Flow Rate Measuring Device (VFR-315)(1-MR-054 and/or VRS-1510)e.Sampler Flow Rate Measuring Device (VFS-1521) 28 32 32 27 27 27 4.Containment Purge System a.Aux.Building Vent.System Noble Gas Activity Monitor (VRS-1505) b.Aux.Building Vent.System Particulate Sampler for VRS-1501 32 5.Waste Gas Holdup System a.Noble Gas Activity Monitor Providing Alarm and Termination of Gas Decay Tank Releases (VRS-1505) 33 6.Gland Seal Exhaust a.Noble Gas Activity Monitor (SRA-1805)
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| (1).b.Flow Rate Monitor (SFR-201)(1)(1-MR-054 and/or SRA-1810)(1)28 27 27 D.C.COOK-UNIT 1 3/4 3-63 Amendment No.
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| I TABLE 3.3-13 (Cont)*At all times**During waste gas holdup system operation (treatment for primary system gases)****During releases via this pathway.1 For purge purposes only.See Technical Specifications 3.3.3.10, Table 3.3-13 and Table 4.3-9 (Items 3a, Sa)for other requirements associated with this instrument.
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| 2 For gas decay tank releases only, see Item 3 (Unit Vent, Auxiliary Building Ventilation System)for additional requirements.
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| D.C.COOK-UNIT 1 3/4 3-64 Amendment No.
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| J 1 TABLE 4.3-9 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Re uirements Instrument (Instrument 5)Channel Check Source Check Channel Calibration Channel Functional Test 1.Waste Gas Holdup System Explosive Gas Monitoring System a.Hydrogen Monitor (QC-31)b.Oxygen Monitor (QC-31)c.Oxygen Monitor (Alt.(QC-370)NA NA NA Q(3)Q(4)Q(4)M-2.Condenser Evacuation System a.Noble Gas Activity Monitor (SRA-1905) b.System Effluent Flow Rate (SFR-401, 2-MR-054, SRA-1910)D**D**NA R(2)Q(1)3.Auxiliary Building Ventilation System a.Noble Gas Activity Monitor (VRS-1505) b.Iodine Sampler (For VRS-1505)c.Particulate Sampler (For VRS-1501)d.System Effluent Flow Rate Measurement Device (VFR-315, 2-MR-054, VRS-1510)e.Sampler Flow Rate Measurement Device (VFS-1521)
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| D*W*D*D*M~NA NA NA NA R(2)NA NA Q(1)NA NA 4.Containment Purge System a.Aux.Building Vent.System Noble Gas Activity D**Monitor (VRS-1505) b.Aux.Building Vent.System Particulate Sampler'W**(For VRS-1501)NA R(2)NA Q(5)NA 5.Waste Gas Holdup System a.Noble Gas Activity Monitor Providing Alarm 6 Termination of Gas Decay Tank Release (VRS>>1505)
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| R(2)Q(>>D.C.COOK-UNIT 1 3/4 3-66 Amendment No.
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| l TABLE 4.3-9 (Cont)Instrument (Instrument I)Channel Check Source Check Channel Calibration Channel Functional Test 6.Gland Seal Exhaust a.Noble Gas Activity (SRA-1805) b.System Effluent Flow Rate (SFR-201, 1-MR-054, SRA-1810)'D****NA R(2)Q(1)*At all times**During release via this pathway***During waste gas holdup system operation (treatment for primary system offgases)D.C.COOK-UNIT 1 3/4 3-67 Amendment No.
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| ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTiON PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.6.12 HIGH RADIATION AREA 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
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| a.A radiation monitoring device which continuously indicates the radiation dose rate in the area.b.A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.c~An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.In addition, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
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| *Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.D.C.COOK-UNIT 1 6-21 Amendment No.
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| I~
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| t TABLE 4.11-2 t RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (uci/ml)P Each Tank a.Waste Gas Storage Tank Grab Sample P Each Tank Principal Gamma Emitters e 1 X 10 Principal Gamma Emitters e 1X10 b.Containment Purge Each Purge b Grab Sample Each Purge H-3 1 X 10 W c.Condenser Evacuation Grab System and Gland Seal Sample Exhaust M Particulate Sample M Principal Gamma e Emitters H-3 1 X 10 1X10 M Iodine Adsorbing/
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| Media I-131 1X10 d Continuous Noble Gas Monitor Noble Gases 1 X 10 d.Auxiliary Building Vent Continuous d W Iodine Adsorbing/
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| Media I-131 1X10 d Continuous W Particulate Sample Principal Gamma Emitters e 1X 10 d Continuous M Composite Particulate Sample Gross Alpha 1X10 d Continuous M Composite H-3 1X10 d Continuous Q Composite Particulate Sample Sr-89, Sr-90 1 X 10 d Continuous Noble Gas Monitor Noble Gases 1X10 D.C.COOK-UNIT 1 3/4 11-8 Amendment No.
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| 3/4.11 RADIOACTXVE EFFLUENTS BASES 3/4.11.1 LI UID EFFLUENTS 3/4.11.1.1 CONCENTRATION.
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| This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR part 20, Appendix B, Table II.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1)the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.
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| The concentration limit for noble gases is based upon the~assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological protection (ICRP)Publication 2.3/4.'11.1.2 DOSE.This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.The ACTION statements provide the required operating flexibility and at the same time releases of radioactive material in liquid effluents will be kept"as low as is reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
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| The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 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 Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.This specification applies to the release of liquid effluents from each reactor at the site.The liquid effluents from the shared system are proportioned among the units sharing the system.D.C.COOK-UNIT 1 B 3/4 11-1 Amendment No.
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| RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT.
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| The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
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| The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept"as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C.Cook Nuclear Plant, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ZZ.A of Appendix I, 10 CFR Part 50, for liquid effluents.
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| 3/4.11.1.4 LIQUID HOLDUP TANKS.Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.This specification is provided to ensure that the dose rate any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure, of an individual in an UNRESTRICTED AREA, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
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| For individuals who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1500 mrem/year for the nearest cow to the Plant.Iodine adsoxbing media refers to silver zeolite cartridges in Table 4.11-2 or the industry standard.This specification applies to the release of gaseous effluents from all reactors at the site.The gaseous effluents from the shared system are proportioned among the units sharing that system.D.C.COOK-UNIT 1 B 3/4 11-2 Amendment No.
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| 1 L
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| ~r J TABLE 3.12-1 t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Samples Sam le Locations Sampling and Collection Fre uency Type a Frequency of Analysis l.Airborne a.Radioiodine s Particulates Al-A6 (Site)New Buffalo South Bend, Dowagiac, and Coloma are Background Continuous operation of sampler with Sample Collection as required by Dust Loading but at least once per 7 days Radioiodine canister Analyze: Weekly for I-131 Particulate sample Gross Beta Rad-ioactivity following Filter Change a composite (by loca-tion)for gamma isotopic quarterly 2.Direct Radiation a)Tl-T9 (Site)b)New Buffalo South Bend Dowagiac Coloma At least once per 92 days Gamma Dose.At least once per 92 days 3.Waterborne a.Surface c)10 TLD Monitor Locations in the Five Mile Radius Ll, L2, L3 Composite*
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| sample'ver one-month period Gamma Isotopic Analysis monthly.Composite for tritium analysis-quarterly.
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| b.Ground Wl-W7 Quarterly Gamma Isotopic and Tritium analysis quarterly.
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| c.Drinking St.Joseph Lake Township Composite sample collected over a period of~31 days Composite*
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| sample over a 2-week period if I-131 analysis is performed Gross Beta and Gamma Isotopic Analysis of each composite sample.Tritium Analysis of composite Quarterly.
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| I-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year.*Composite samples shall be collected by collecting an aliquot at intervals not exceeding 24 hours.D.C.COOK-UNIT 1 3/4 12-3 Amendment No.
| |
| 'J TABLE 3.3-3 (Continued)
| |
| ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION n 8 FUNCTIONAL UNIT I 3.CONTAINMENT ISOLATION R a.Phase"A" Isolation H 1)Manual 2)From Safety Injection Automatic Actuation Logic MINIMUM TOTAL NO.CHANNELS CHANNELS OF CHANNELS TO TRIP~OPERABLE APPLICABLE MODES 1,2,3,4 1,2,3,4 ACTION 18 13 b.Phase"B" Isolation 1)Manual 2)Automatic Actuation Logic 3)Containment Pressure-High-High 1,2,3,4 1,2,3,4 1I2I3 18 13 16 c.Purge and Exhaust Isolation*
| |
| 4)I CO 1)Manual 2)Containment Radioactivity-High Train A (VRS 2101 g ERS 2301 g ERS 2305)3)Containment Radioactivity-High Train B (VRS 220 1 g ERS 240 1~ERS 2405)1,2,3,4 1,2,3;4 1,2,3,4 17 17 0*This specification only applies during purge.
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| 1 P TABLE 3.3-4 (Continued)
| |
| ENGINEERED SAFETY FEATURE ACTUATION SYSTFM INSTRUMENTATION TRIP SETPOINTS O 0 0 I C R M FUNCTIONAL UNIT 2.CONTAINMENT SPRAY a.Manual Initiation b.Automatic Actuation Logic c.Containment Pressure-High-High TRIP SETPOINT Not Applicable Not Applicable 2.9 psig ALLOWABLE VALUES Not Applicable Not Applicable 3.0 psig 3.CONTAINMENT ISOLATION a.Phase"A" Isolation 1.Manual Not Applicable Not Applicable 2.From Safety Injection Automatic Actuation Logic b.Phase"B" Isolation 1.Manual 2.Automatic Actuation Logic 3.Containment Pressure-High-High c.Purge and Exhaust Isolation Not Applicable Not Applicable 2.9 psig Not Applicable Not Applicable 3.0 psig 1.Manual Not Applicable Not Applicable 2.Containment Radioactivity
| |
| -High Train A (VRS-2101, ERS-2301, ERS-2305)See Table 3.3-6 Not Applicable 0 3.Containment Radioactivity
| |
| -High Train B (VRS-2201, ERS-2401, ERS-2405)See Table 3.3-6 Not Applicable I 1 O 0 0 I OPERATION MODE/INSTRUMENT 1.Modes 1, 2, 3, 6 4 MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
| |
| ACTION A)Area Monitors i)Upper Containment (VRS 2101/2201)
| |
| B)Process Monitors N/A 54 mR/hr 21 i)Particulate Channel (ERS 2301/2401)
| |
| N/A 2.52 uCi 20 ii)Noble Gas Channel (ERS 2305/2405)
| |
| N/A C-3 44x 10 uCi CC 20 C)Noble Gas Effluent Monitors i)Unit Vent Effluent Monitor a)Low Range (VRS 2505)(See T/S Section 3.3.3.10)
| |
| | |
| TABLE 3.3-6 (Cont'd)n RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
| |
| A O O I C R H OPERATION MODE/INSTRUMENT ii)Gland Steam Condenser Vent Monitor MINIMUM CHANNELS OPERABLE ALARM SETPOINT TRIP SETPOINT ACTION a)Low Range (SRA 2805)(See T/S Section 3.3.3.10)iii)Steam Jet Air Ejector Vent Monitor a)Low Range (SRA 2905)(See T/S Section 3.3.3'0)2.Mode 6 A)Train A i)Containment Area Radiation Channel (VRS 2101)ii)Particulate Channel (ERS 2301)iii)Noble Gas Channel (ERS 2305)any 2/3 channels N/A N/A N/A 54 mR/hr+2.52 uCi (3 4.4 x 10 uCi CC 22 B)Train B any 2/3 channels 22 i)Containment Area Radiation Channel (VRS 2201)N/A 54 mR/hr R 0 ii)Particulate Channel (ERS 2401)N/A 2.52 uCi
| |
| ~[
| |
| TABLE 3.3-6 (Cont'd)n O 0 I C R H OPERATION MODE/INSTRUMENT iii)Noble Gas Channel (ERS 2405)MINIMUM CHANNELS OPERABLE ALARM SETPOINT N/A RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)
| |
| TRIP SETPOINT-3 4.4 x 10, uCi CC ACTION 22 3 Mode***A)Spent Fuel Storage (RRC-330)15 mR/hr 15 mR/hr 21 Q o 8 Q R 0***With fuel in storage pool or building.+This specification applies only during purge.
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| ,~
| |
| TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS O O 8 OPERATION MODE/INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED 1.Modes 1, 2, 3, s 4 A)Area Monitors i)Upper Containment (VRS 2101/2201)
| |
| $*1, 2, 3, 4 B)Process Monitors i)Particulate Channel (ERS 2301/2401) ii)Noble Gas Channel (ERS 2305/2405)
| |
| R 1, 2, 3, 4 1, 2, 3, 4 C)Noble Gas Effluent Monitors i)Unit Vent Effluent Monitors a)Low Range (VRS 2505)(See Table 4.3-9, Item 3.a.4a.Sa)
| |
| ~lg I a TABLE 4.3-3 (Cont')RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE9UIREMENTS 8 OPERATION MODE/INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED ii)Gland Steam Condenser Vent Monitor a)Low Range (SRA 2805)(See Table 4.3-9 Item 6.a)iii)Steam Jet Air Ejector Vent Monitor a)Low.Range (SRA 2905)(See Table 4.3-9, Item 2.a)2.Mode 6 A)Train A i)Containment Area Radiation Channel (VRS 2101)ii)Particulate Channel (ERS 2301)$*M iii)Noble Gas Channel (ERS 2305)B)Train B 9 8 0 i)Containment Area Radiation Channel (VRS 2201)ii)Particulate Channel (ERS 2401)S*M 1
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| TABLE 4.3-3 (Cont'd)RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATION MODE/INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE RE UIRED iii)Noble Gas Channel (ERS 2405)S*2.Mode**A)Spent Fuel Storage (RRC-330)*To include SOURCE CHECK per T/S Section 1.27.**With fuel in storage pool or building.
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| I<g~
| |
| TABLE 3.3-6 (Continued)
| |
| TABLE NOTATION ACTION 20-With the number of channels OPERABLE less than required by the.Minimum Channels Ope'rable requirement, comply with the ACTION requirements of Speci ication 3.4.6.1.ACTION 21-With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.ACTION 22-With the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9.This ACTION is not required during the performance of containment integrated leak rate test.D.C.COOK-UNIT 2 3/4 3-36 Amendment No.
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| | |
| 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED'SAFETY FEATURES (ESF)INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1)the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2)the specified coincidence logic'is maintained, 3)sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4)sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
| |
| The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
| |
| The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.The surveillance requirements specified for these systems ensurethat the overall system functional capability is maintained comparable to the original design standards.
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| The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability., The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.No credit was taken in the analyses for those channels with response times indicated as not applicable.
| |
| Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.Sensor response time verification may be demonstrated by either 1)in place, onsite or offsite test measurements or 2)utilizing replacement sensors with certified response times.3/4.3 3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION, The OPERABILITY of the radiation monitoring channels ensures that 1)the radiation levels are continually measured in the areas served by the individual channels and 2)the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.D.C.COOK-UNIT 2 B 3/4 3-1 Amendment"No i%~
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| INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
| |
| Table 3.3-6 is based on the following Alarm/Trip Setpoints and Measurement Ranges for each instrument listed.INSTRUHENT ALARH/TRIP SETPOINT HEASUREMENT RANGE*1)Area Honitor-Upper Containment (VRS 2101/2201)
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| The monitor trip setpoint is based on 10 CFR 20 limits.A homogeneous mixture of the containment atmosphere is assumed.The setpoint value is defined as the monitor reading when the purge is operating at, the maximum flow rate.10 R/hr to 10R/hr.2)Process Monitor Particulate (ERS 2301/2401) 3)Process Monitor Noble Gas (ERS 2305/2405)
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| -4 The monitor trip setpoint 1.5 x 10 uCi to 7.5 based on 10 CFR 20 limits.uCi.The setpoint was determined using the Noble gas setpoint and historical monitor data of the ratio of particulate to Noble gases.-7 The monitor trip setpoint 1 x 10 2 uCi/cc to is based on 10 CFR 20 4 x 10 uCi/cc limits.A homogeneous mixture of the containment atmosphere is assumed.The setpoint value is defined as the monitor reading when the purge is operating at the maximum flow rate." This is the minimum required sensitivity of the instrument.
| |
| Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
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| D.C.COOK-UNIT 2 B 3/4 3-la Amendment No.
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| | |
| INSTRUMENTATION BASES Radiation Monitoring Instrumentation (Continued)
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| INSTRUMENT ALARM/TRIP SETPOINT MEASUREMENT RANGE*4)Noble Gas Unit Vent Monitors a)Low Range (VRS 2505)See Bases Section 3/4.3.3.10 2 lx10 uCi/cc to 4x10 uCi/cc.5)Gland Steam Condenser Vent Noble Gas Monitor a)Low Range (SRA 2805)See Bases Section 3/4.3.3.10
| |
| -7"2 lx10 uCi/cc to 4x10 uCi/cc.6)Steam Jet Air Ejector Vent Noble Gas Monitor a).Low Range (SRA 2905)See Bases Section 3/4.3.3.10 2 lx10 uCi/cc to 4x10 uCi/cc.*This is the minimum required sensitivity of the instrument.
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| Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.'.
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| C.COOK-UNIT 2 B 3/4 3-lb Amendment No.
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| C s INSTRUMENTATION BASES Radiation Monitoring Instrumentat ion (Continued)
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| INSTRUMENT ALAR 1/TRIP SETPOINT l IEASUREMENT RANGE*7)Spent Fuel Storage (RRC-330)The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a)(2)
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| -1 4 1x10 mR/hr to lx10 mR/hr The Radiation Monitoring Instrumentation Surveillance Requirements per Table 4.3-3 are based on the following interpretation:
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| 1)The CHANNEL FUNCTIONAL TEST is successfully accomplished by the injection of a simulated signal into the channel, as close to the detector as practical, to verify the channel's alarm and/or trip function only.2)The CHANNEL CALIBRATION as defined in T/S Section 1.9 permits the"known values" generated from radioactive calibration sources to be substituted with"known values" represented by simulated signals for that subset of"known values" required for calibration and not practical to generate using the radioactive calibration sources.*This is the minimum required sensitivity of the instrument.
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| Indicated values on these instruments above or below these minimum sensitivity ranges are acceptable and indicate existing conditions not instrument inoperability.
| |
| D.C.COOK-UNIT 2 B 3/4 3-1c Amendment No.
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| | |
| TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATiON Instrument Minimum Channels Action 1.Gross Radioactivity Monitors Providing Automatic Release Termination a.Liquid Radwaste Effluent Line (2-R-18)At times of release 23 b.Steam Generator Blowdown Line (2-R-19)At times of release 24 c.Steam Generator Blowdown Treatment Effluent (2-R-24)At times of release 24 2.Gross Radioactivity Monitors Not Providing Automatic Release Termination a.Service Water System Effluent Line (2-R-20, 2-R-28)3.Continuous Composite Sampler Flow Monitor (1)per train At all times 25 a.Turbine Building Sump Effluent Line At all times 25 4.Flow Rate Measurement Devices a.Liquid Radwaste Line(RFI-285) b.Discharge Pipes*c.Steam Generator Blowdown Treatment Effluent (2-DFI-353)
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| At times of release At all times't times of release 26 NA 26*Pump curves and valve settings may be utilized to estimate flow;in such cases, Action Statement 26 is not'pplicable.
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| D.C.COOK-UNIT 2 3/4 3-54 Amendment No.
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| | |
| TABLE 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument (Instrument 5)Minimum Channels Operable A plicabilit Action 1.Waste Gas Holdup System Explosive Gas Monitoring System a.Hydrogen Monitor (QC-31)b.Oxygen Monitor (QC-31, QC-370)(1)(2)30 29 Condenser Evacuation System a.Noble Gas Activity Monitor (SRA-2905)
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| (1)b.Flow Rate Monitor (SFR-401)(1)(2-MR-054 and/or SRA-2910)(1)28 27 27 3.Unit Vent, Auxiliary Building Ventilation System a.Noble Gas Activity Monitor (VRS-2505) b.Iodine Sampler Cartridge for VRS-2503 c.Particulate Sampler Filter for VRS-2501 d.Effluent System Flow Rate Measuring Device (VFR-315)(2-MR-054 and/or VRS-2510)e.Sampler Flow Rate Measuring Device (VFS-2521) 28 32 32 27 27 27 4.Containment Purge System a.Aux.Building Vent.System Noble Gas Activity Monitor (VRS-2505) b.Aux.Building Vent.System Particulate Sampler for VRS-2501 31 32 5.Waste Gas Holdup System a.Noble Gas Activity Monitor Providing Alarm and Termination of Gas Decay Tank Releases (VRS-2505) 33 6.Gland Seal Exhaust a.Noble Gas Activity Monitor (SRA-2805)
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| (1)b.Flow Rate Monitor (SFR-201)(1)(2-MR-054 and/or SRA-2810)(1)28 27 27 D.C.COOK-UNIT 2 3/4 3-59 Amendment No.
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| C<S I TABLE 3.3-13 (Cont)*At all times**During waste gas holdup system operation (treatment for primary system gases)****During releases via this pathway.1 For purge purposes only.See Technical Specifications 3.3.3.10, Table 3.3-13 and Table 4.3-9 (Item 3a, 5a)for other non purging requirements associated with this instrument..
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| 2 For gas decay tank releases only, see Item 3 (Unit Vent, Auxiliary Building Ventilation System)for additional requirements.
| |
| D.C.COOK-UNIT 2 3/4 3-60 Amendment No.
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| )1 4 TABLE 4.3-9 Radioactive Gaseous Effluent Monitorin Instrumentation Surveillance Re uirements Channel Instrument (Instrument 0)Check Source Check Channel Channel Functional Calibration Test 1.Waste Gas Holdup System Explosive Gas Monitoring Syst: em a.Hydrogen Monitor (QC-31)b.Oxygen Monitor (QC-31)c.Oxygen Monitor (Alt.(QC-370)NA Q(3)Q(4)Q(4)2.Condenser Evacuation System a.Noble Gas Activity Monitor (SRA-2905) b.System Effluent Flow Rate (SFR-401, ,2-MR-054 i SRA-2910)D**D**NA R(2)Q(1)D*D*D*3.Auxiliary Building Ventilation System a.Noble Gas Activity Monitor (VRS-2505) b.Iodine Sampler (For VRS-2505)c.Particulate Sampler (For VRS-2501)d.System Effluent Flow Rate Measurement Device (VFR-315, 2-MR-054, VRS-2510)e.Sampler Flow Rate Measurement Device (VFS-2521)
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| NA NA NA NA R(2)NA NA'(1)NA NA 4.Containment Purge System a.Aux.Building Vent.System Noble Gas Activity D**Monitor (VRS-2505) b.Aux.Building Vent.System Particulate Sampler W,A*(For VRS-2501)NA R(2)NA Q(5)NA 5.Waste Gas Holdup System a.Noble Gas Activity Monitor Providing Alarm 6 Termination of Gas Decay Tank Release (VRS-'2505)
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| D.C.COOK-UNIT 2 3/4 3-62 R(2)Q(5)Amendment No.
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| 4 1 TABLE 4.3-9 (Cont)Channel Instrument (Instrument 0)Check Source Check Channel Channel Functional Calibration Test D**D**6.Gland Seal Exhaust a.Noble Gas Activity (SRA-2805) b.System Effluent Flow Rate (SFR-201, 2-MR-054, SRA-2810)NA R (2)*At all times**During release via this pathway***During waste gas holdup system operation (treatment for primary system offgases)D.C.COOK-UNIT 2 3/4 3-63 Amendment No.
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| 4 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Frequency Minimum Analysis Frequency Type of Activity Analysis I Lower Limit of Detection (uci/ml)P Each Tank a.Waste Gas Storage Tank Grab Sample P Each Tank Principal Gamma e Emitters 1X10 Principal Gamma Emitters e 1X10 b.Containment Purge Each Purge Grab Sample Each Purge H-3 1X10 c.Condenser Evacuation System and Gland Seal Exhaust W Grab b Sample b H-3 b Particulate Principal Gamma Sample Emitters e 1 X 10 1 X 10 M Iodine Adsorbing/
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| Media I-131 1 X 10 d Continuous Noble Gas Monitor Noble Gases 1 X 10 d d.Auxiliary Building Vent Continuous W Iodine Adsorbing/
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| Media I-131 1X10 d Continuous W Particulate Sample Principal Gamma e Emitters 1X10 d Continuous M Composite Particulate Sample Gross Alpha 1X10 d Continuous d Continuous M Composite Q Composite Particulate Sample H-3 Sr-89, Sr-90 1 X 10 1X10 d Continuous Noble Gas Monitor Noble Gases-6 1 X 10 D.C.COOK-UNIT 2 3/4 11-8 Amendment No.
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| ~~(p 1 I I ADMINiSTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.6.12 HIGH RADIATION AREA 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more o the following:
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| a.A radiation monitoring device which continuously indicates the radiation dose rate in the area.b.A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.c~An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.In addition, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
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| *Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.D.C.COOK-UNIT 2 6-21 Amendment No.
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| I 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LI UID EFFLUENTS 3/4.11.1.1 CONCENTRATION.
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| This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR part 20, Appendix B, Table II.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1)the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.
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| The concentration limit for noble gases is based upon the.assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological protection (ICRP)Publication 2.I 3/4.11.1.2 DOSE.This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.The'imiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.The ACTION statements provide the required operating flexibility and at the same time rel'eases of radioactive material in liquid effluents will be kept"as low as is reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
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| The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent.
| |
| with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 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 Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1'13.This specification applies to the release of liquid effluents from each reactor at the site.The liquid effluents from the shared system are proportioned among the units sharing the system.D.C.COOK-UNIT 2 B'3/4 11-1 Amendment No.
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| j t RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 IIQUID WASTE TREATMENT.
| |
| The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid eff'uents require treatment prior to release to the environment.
| |
| The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept"as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C.Cook Nuclear Plant, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
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| 3/4.11.1.4 LIQUID HOLDUP TANKS.Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.This specification is provided to ensure that the dose rate any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an UNRESTRICTED AREA, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
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| For individuals who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.The specified release rate limits restrict, at all times,-the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1500 mrem/year for the nearest cow to the Plant.Iodine adsorbing media refers to silver zeolite cartridges in Table 4.11-2 or the industry standard.This specification applies to the release of gaseous effluents from all reactors at the site.The gaseous effluents from the shared system are proportioned among the units sharing that system.D.C.COOK-UNIT 2 B 3/4 11-2 Amendment No.
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| It/I TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Locations Sampling and Collection Fre uenc Type 6 Frequency of Analysis 1.Airborne a.Radioiodine 6 Particulates Al-A6 (Site)New Buffalo South Bend, Dowagiac, and Coloma are Background Continuous operation of sampler with Sample Collection as required by Dust Loading but at least once per 7 days Radioiodine canister Analyze: Weekly for I-131 Particulate sample Gross Beta Rad-ioactivity following Filter Change a composite (by loca-tion)for gamma isotopic quarterly 2.Direct Radiation a)Tl-T9 (Site)b)New Buffalo South Bend Dowagiac Coloma At least once per 92 days Gamma Dose.At least once per 92 days c)10 TLD Monitor Locations in the Five Mile Radius 3.Waterborne a.Surface Ll, L2, L3 Composite sample over one-month period Gamma Isotopic Analysis monthly.Composite for tritium analysis-quarterly.
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| b.Ground c.Drinking W1-W7 St.Joseph Lake Township Quarterly Composite*
| |
| sample collected over a period of(31 days Composite*
| |
| sample over a 2-week period if I-131 analysis is performed Gamma Isotopic and Tritium analysis quarterly.
| |
| Gross Beta and Gamma Isotopic Analysis of each composite sample.Tritium Analysis of composite Quarterly.
| |
| I-131 analysis on each composite when the dose calculated for the consumption o f the water is greater than 1 mrem per year.*Composite samples shall be collected by collecting an aliquot at intervals not exceeding 24 hours.D.C.COOK-UNIT 2 3/4 12-3 Amendment No.}}
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