ML15086A188

Technical Requirements Manual/Trm Revision 128/Trm343

ML15086A188
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Site:	Waterford
Issue date:	03/10/2015
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
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ML15086A176	List: ML15086A157 ML15086A181 ML15086A182 ML15086A183 ML15086A186 ML15086A187 ML15086A188 ML15086A189 ML15086A203 ML15086A204 ML15086A205 ML15086A206 ML15086A208 ML15086A209 ML15086A210 ML15086A211 W3F1-2015-0023, Technical Requirements Manual/Trm Revision 128/Trm3412
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3/4 3-1AMENDMENT NO. 58, 119(DRN 02-912)3/4.3 INSTRUMENTATION3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION(DRN 02-912)(EC-22790, Am. 119)LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be operable. APPLICABILITY: As shown in Table 3.3-1. ACTION: As shown in Table 3.3-1. SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.4.3.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation. 4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per function such that all channels are tested at least once every N time 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1. (EC-22790, Am. 119)(EC-22790, Am. 119)The Reactor Trip System Response Times appearing in Table 3.3-2 are the response times that are applicable to Technical Specification Surveillance Requirement 4.3.1.3 and Technical Requirements Manual Surveillance Requirement 4.3.1.3.(EC-22790, Am. 119) 3/4 3-1a AMENDMENT NO. 119(EC-22790, Am. 119)TABLE 3.3-1REACTOR PROTECTIVE INSTRUMENTATIONFUNCTIONAL UNIT TOTAL NO. OF CHANNELSCHANNELSTO TRIP MINIMUMCHANNELSOPERABLEAPPLICABLEMODES ACTIONS 1. Steam Generator Level - High 4/SG 2/SGa3/SG 1, 2 1b, 2b TABLE NOTATION(a) High steam generator level trip may be manually bypassed in Modes 1 and 2 at 20% power and below. (b) The provisions of Specification 3.0.4 are not applicable. (EC-22790, Am. 119) 3/4 3-1b AMENDMENT NO. 119(EC-22790, Am. 119) TABLE 3.3-1 (Continued) ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is bypassed, the desireability of maintaining this channel in the bypassed condition shall be document by the On-Site Safety Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN. With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below: Process Measurement Circuit Functional Unit Bypassed/Tripped 1. Steam Generator Level *TS Steam Generator Level - Low Steam Generator Level - High

ACTION 2 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, STARTUP and/or POWER OPERATOR may continue provided the following conditions are satisfied:

a. Verify that one of the inoperable channels has been bypassed and place the other channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and b. All functional units affected by the bypassed/tripped channel shall also be placed in the bypassed/tripped condition as listed below: Process Measurement Circuit Functional Unit Bypassed/Tripped 1. Steam Generator Level *TS Steam Generator Level - Low Steam Generator Level - High

• The Technical Specification functional units are included for completeness to ensure these affected units are not omitted. The Technical Requirements Manual does not supercede the Technical Specifications. (EC-22790, Am. 119)

3/4 3-2AMENDMENT NO. 43,99TABLE 3.3-2REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMESFUNCTIONAL UNITRESPONSE TIME1.Manual Reactor TripNot Applicable 2.Linear Power Level - High 0.40 second* 3.Logarithmic Power Level - High 0.40 second* 4.Pressurizer Pressure- High 0.90 second 5.Pressurizer Pressure - Low 0.90 second 6.Containment Pressure - High 1.70 seconds 7.Steam Generator Pressure - Low 0.90 second 8.Steam Generator Level - Low 0.90 second 9.Local Power Density - High(DRN 04-1244, Am. 99)a.Neutron Flux Power from Excore Neutron Detectors 0.191 second*b.CEA Positions 0.186 second**c.CEA Positions:CEAC Penalty Factor #1Channel A 0.271 secondChannel B0.236 secondChannel C 0.236 secondChannel D 0.236 secondd.CEA Positions: CEAC Penalty Factor #2Channel A 0.236 secondChannel B 0.236 secondChannel C 0.236 secondChannel D 0.271 second10.DNBR- Lowa.Neutron Flux Power from Excore Neutron Detectors 0.191 second*b.CEA Positions 0.186 second** c.Cold Leg Temperature 0.285 second#d.Hot Leg Temperature 0.285 second# e.Primary Coolant Pump Shaft Speed 0.185 second** f.Reactor Coolant Pressure from Pressurizer 0.186 second## (DRN 04-1244, Am. 99) 3/4 3-3AMENDMENT NO. 99,119TABLE 3.3-2 (Continued)REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMESFUNCTIONAL UNIT RESPONSE TIME(DRN 04-1244, Am. 99) g. CEA Positions: CEAC Penalty Factor #1 Channel A 0.271 second Channel B 0.236 second Channel C 0.236 second Channel D 0.236 second h. CEA Positions: CEAC Penalty Factor #2 Channel A 0.236 second Channel B 0.236 second Channel C 0.236 second Channel D 0.271 second (DRN 04-1244, Am. 99)(EC-22790, Am. 119) 11.TRM Steam Generator Level - High Not Applicable (EC-22790, Am. 119) 12. Reactor Protection System Logic Not Applicable 13. Reactor Trip Breakers Not Applicable 14. Core Protection Calculators Not Applicable 15. CEA Calculators Not Applicable

16. Reactor Coolant Flow - Low 0.70 second _____________________

• Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel. **Response time shall be measured from the time the CPC/CEAC receives an input signal until the electrical power is interrupted to the CEA drive mechanism. #Response time shall be measured from the output of the sensor. RTD response time for all the RTDs shall be measured at least once per 18 months. The measured Pt of the slowest RTD shall be less than or equal to 8 seconds (Pt assumed in the safety analysis). ##Response time shall be measured from the output of the pressure transmitter. The transmitter response time shall be less than or equal to 0.70 second.

3/4 3-3a AMENDMENT NO. 119(EC-22790, Am. 119)TABLE 4.3-1REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTSFUNCTIONAL UNIT CHANNEL CHECK CHANNELCALIBRATIONCHANNELFUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE IS REQUIRED1. Steam Generator Level - High S R Q 1, 2 (EC-22790, Am. 119) 3/4 3-4 AMENDMENT NO. 58, 119(DRN 02-912) INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM (DRN 02-912) (EC-22790, Am. 119) ACTION STATEMENTS The following functional units are applicable to the Technical Specification action statements 19 and 20. Process Measurement Circuit Functional Unit Bypassed/Tripped 1. Steam Generator Level *TS Steam Generator Level - Low Steam Generator Level - High

• The Technical Specification functional units are included for completeness to ensure these affected units are not omitted. The Technical Requirements Manual does not supercede the Technical Specifications. (EC-22790, Am. 119)

The Engineered Safety Features Response Times appearing in Table 3.3-5 are the response times applicable to Technical Specification Surveillance Requirement 4.3.2.3 3/43-5TABLE3.3-5ENGINEEREDSAFETYFEATURESRESPONSETIMESINITIATINGSIGNALANDFUNCTIONRESPONSETIMEINSECONDS1.Manuala.SIASSafetyInjection(ECCS)NotApplicableShieldBuildingFiltrationSystemNotApplicableb.CSASContainmentSprayNotApplicablec.CIASContainmentIsolationNotApplicabled.MSISMainSteamIsolationNotApplicablee.RASSafetyInjectionSystemSumpRecirculationNotApplicablef.EFASEmergencyFeedwaterPumpsNotApplicable 3/4 3-6AMENDMENT NO. 25, 38, 41,82,99TABLE 3.3-5 (Continued)ENGINEERED SAFETY FEATURES RESPONSE TIMESINITIATING SIGNAL AND FUNCTIONRESPONSE TIME IN SECONDS2.Pressurizer Pressure-Low(DRN 04-1244, Am. 99)a.Safety Injection (ECCS)(1) High Pressure Safety Injection27.0*/18.5**(2) Low Pressure Safety Injection 42.5*/34.0**(DRN 04-1244, Am. 99)b.Containment Isolation 23.5*/12.0**c.Containment Cooling 31.0*/19.5**3.Containment Pressure-High(DRN 04-1244, Am. 99)a.Safety Injection (ECCS)(1) High Pressure Safety Injection27.0*/18.5**(2) Low Pressure Safety Injection 42.5*/34.0**(DRN 04-1244, Am. 99)b.Containment Isolation 23.5*/12.0**c.Main Steam Isolation 8.0*/8.0**d.Main Feedwater Isolation ### 6.0*/6.0**e.Containment Cooling 31.0*/19.5**4.Containment Pressure--High-Higha.Containment Spray Pump 15.2*/4.6**b.Containment Spray Valves 10.4*/10.4**(DRN 03-168, Am. 82)c.CCW to RCP Valves(CC-641, CC-710 & CC-713) 5.0, 50.0* / 5.0, 50.0**(DRN 03-168, Am. 82)5.Containment Area Radiation-High #Containment Purge Valves Isolation 6.2*/6.2**6.Steam Generator Pressure-Lowa.Main Steam Isolation 8.0*/8.0**b.Main Feedwater Isolation ### 6.0*/6.0**7.Refueling Water Storage Pool-LowSafety Injection Sump 50.0##Recirculation Valves Open8.4.16 kV Emergency Bus Undervoltage (Loss of Voltage)Loss of Power (0 volts) 2***9.480V Emergency Bus Undervoltage (Loss of Voltage)Loss of Power (0 volts)N.A.10.4.16 kV Emergency Bus Undervoltage (Degraded Voltage)Loss of Power 14***

3/43-7AMENDMENTNO.25,31,38TABLE3.3-5(Continued)ENGINEEREDSAFETYFEATURESRESPONSETIMESINITIATINGSIGNALANDFUNCTIONRESPONSETIMEINSECONDS11.SteamGeneratorLevel-LowEmergencyFeedwaterPump60.0*/50.0**EmergencyFeedwaterBlockValves25.0*/25.0**12.WideRangeSteamGeneratorLevel-LowEmergencyFeedwaterControlValves25.0*/25.0**TABLENOTATIONS*LossofOffsitePower.DieselgeneratorstartingdelaysanddieselgeneratorsequenceloadingdelaysincludedinaccordancewiththeESFASResponseTime definitioninTechnicalSpecification1.12.**OffsitePowerAvailable.DieselgeneratorstartingdelaysanddieselgeneratorsequenceloadingdelaysnotincludedinaccordancewiththeESFAS ResponseTimedefinitioninTechnicalSpecification1.12.***Responsetimemeasuredfromthesensingrelaytothechanneloutputonly.#Responsetimedoesnotincludethedetector.##ResponsetimebasedonensuringuninterruptedflowduringtransferofsuctionfromRWSPtoSafetyInjectionSump.###Pertainstoclosureduringdesignbasisaccidentconditions,usingtheSGFPstofeedthesteamgenerators.Duringauxiliaryfeedwaterpumpoperation,a30secondclosuretimeisallowedduringthefeedwaterlinebreakscenario.

3/4 3-7a AMENDMENT NO. 50, 91 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable. b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6. (DRN 04-1191, Am. 91) c. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

3/4 3-7bAMENDMENT NO. 50TABLE 3.3-6RADIATION MONITORING INSTRUMENTATIONINSTRUMENTMINIMUMCHANNELS OPERABLEAPPLICABLEMODESALARM/TRIPSETPOINTMEASUREMENTRANGEACTION1.AREA MONITORSa.Fuel Storage Pool AreaFuel Handling Building Ventilation System Isolation2*< 100 mR/h10 104mR/h24__________________________________________*With irradiated fuel in the storage pool.

3/4 3-7cAMENDMENT NO. 50TABLE 3.3-6 (Continued)ACTION STATEMENTSACTION 24 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, comply with the ACTION requirements of Requirement 3.9.12.

3/4 3-7dAMENDMENT NO. 50TABLE 4.3-3RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSINSTRUMENTCHANNELCHECKCHANNELCALIBRATIONCHANNELFUNCTIONALTESTMODES FOR WHICHSURVEILLANCEIS REQUIRED1.AREA MONITORSa.Fuel Storage PoolArea FuelHandling Building Ventilation System IsolationSRQ*___________________________*With irradiated fuel in the storage pool.

3/4 3-8 AMENDMENT NO. 33, 83, 91 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION/INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a. At least 75% of all incore detector locations,

b. A minimum of two quadrant symmetric incore detector locations per core quadrant, and c. At least 75% of all incore detectors operable with at least one incore detector in each quadrant at each level. (DRN 03-1608, Am. 83) (DRN 03-1608, Am. 83) (DRN 03-1608, Am. 83) d. At least one incore detector location in each 4x4 array of adjacent fuel assemblies with at least three functional rhodium detectors (one each at any three of the five axial levels).

Except for Item 3.3.3.2.d above, an OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERABLE rhodium detectors. (DRN 03-1608, Am. 83)

APPLICABILITY: When the incore detection system is used for monitoring:

a. AZIMUTHAL POWER TILT,

b. Radial Peaking Factors,

c. Local Power Density,

d. DNB Margin.

ACTION:

a. With the incore detection system inoperable do not use the system for the above applicable monitoring or calibration functions. (DRN 04-1191, Am.91) b. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91) (DRN 03-1608, Am. 83) c. If requirement 3.3.3.2.d above is not satisfied, then perform one of the following actions: 1. During initial startup testing for a cycle, perform CEA symmetry checks prior to exceeding 50% power for at least one CEA group having a CEA in the 4x4 array of fuel assemblies for each 4x4 array not in compliance with Item 3.3.3.2.d above; or (DRN 03-1608, Am. 83)(DRN 03-1608, Am. 83)3/4 3-8aAMENDMENT NO. 833/4.3 INSTRUMENTATION3/4.3.3 MONITORING INSTRUMENTATION/INCORE DETECTORS (Continued)2.Perform an evaluation within 7 EFPD to determine the ability of the incore detector system to detect an average power asymmetry of at least 10%

between quadrant 4x4 arrays of assemblies with the actual operable incore detector pattern and suitable adjustments to COLSS and CPCS are installed to assure conservative predictions of the DNBR and Peak Linear Heat Rate margins. During initial startup testing for a cycle, if fuel symmetry verification testing has not been successfully completed as required, then this evaluation must be completed prior to exceeding 50% power.(DRN 03-1608, Am. 83)SURVEILLANCE REQUIREMENTS4.3.3.2 The incore detection system shall be demonstrated OPERABLE:a.Byperformance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to itsuse and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margin:b.At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.

3/4 3-9 AMENDMENT NO. 91 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION/SEISMIC LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument(s) to OPERABLE status. (DRN 04-1191, Am. 91) b. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91) SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event (one or more basemat accelerations of 0.05 g or greater) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days. Data shall be retrieved from the accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety. Each of the above seismic monitoring instruments which is actuated during a seismic event (one or more basemat accelerations of 0.05 g or greater) but is not accessible during power operation shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below. A supplemental report shall then be prepared and submitted to the Commission within 10 days pursuant to Specification 6.9.2 describing the additional data from these instruments.

3/4 3-10 AMENDMENT NO. 71 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE

1. Triaxial Time-History Accelerograph System

a. Accelerometer (YT-SM 6000) Adjacent to RB -35 ft MSL 0.02-1.0 g 1 b. Accelerometer (YT-SM 6001) RB +46 ft MSL 0.02-1.0 g 1

c. Accelerometer (YT-SM 6002) Free Field Yard Area 0.02-1.0 g 1

d. Starter Unit (YS-SM 6000) Adjacent to RB

-35 ft MSL 0.01-0.02 g 1

e. Starter Unit (YS-SM 6001) RB +51 ft MSL 0.01-0.02 g 1

f. Recorder (YR-SM 6000) Control Room RAB +46 ft MSL 0.02-1.0 g 1

g. Control Unit (YZ-SM 6000) Control Room RAB +46 ft MSL 0.02-1.0 g 1*

h. Playback Unit (YR-SM 6001) Control Room RAB +46 ft MSL 0.02-1.0 g 1

2. Triaxial Peak Accelerographs

a. YR-SM 6020 RB +56 ft MSL 0-2 g 1

b. YR-SM 6021 RB 23 ft MSL 0-2 g 1

c. YR-SM 6022 RAB +21 ft MSL 0-2 g 1

3. Triaxial Seismic Switches (DRN 02-1931) a. Seismic Switch (YS-SM 6060) RB -34 ft MSL 0.1-0.25 g 1 (DRN 02-1931) b. Control Unit (YZ-SM 6060) Control Room RAB +46 ft MSL 0.1-0.25 g 1*

4. Triaxial Response-Spectrum Recorders (DRN 02-1931) a. YR-SM 6040 RB +50 ft MSL 1-32 Hz, 0-2 g 1 b. YR-SM 6041 RAB -34 ft MSL 1-32 Hz, 0-2 g 1

c. YR-SM 6042 RAB +22 ft MSL 1-32 Hz, 0-2 g 1

d. Peak Shock Annunciator (YR-SM 6045)

RB -34 ft MSL 1-32 Hz, 0-2 g 1 (DRN 02-1931) e. Peak Shock Annunciator Control Unit (YZ-SM 6045) Control Room RAB +46 ft MSL 1-32 Hz, 0-2 g 1

____________________

• With reactor control room annunciation.

3/4 3-11 AMENDMENT NO. 71, 94 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST

1. Triaxial Time-History Accelerograph System

a. Accelerometer (YT-SM 6000) Adjacent to RB -35 ft MSL N.A. R SA

b. Accelerometer (YT-SM 6001) RB

+46 ft MSL N.A. R SA

c. Accelerometer (YT-SM 6002) Free Field Yard Area N.A. R SA

d. Starter Unit (YS-SM 6000) Adjacent to RB -35 ft MSL M R SA

e. Starter Unit (YS-SM 6001) RB

+51 ft MSL M R SA

f. Recorder (YR-SM 6000) Control Room RAB +46 ft MSL M R SA g. Control Unit (YZ-SM 6000) Control Room RAB +46 ft MSL M R SA*

h. Playback Unit (YR-SM 6001) Control Room RAB +46 ft MSL N.A. R SA

2. Triaxial Peak Accelerographs

a. YR-SM 6020 RB +56 ft MSL N.A. R N.A.

b. YR-SM 6021 RB 23 ft MSL N.A. R N.A. c. YR-SM 6022 RAB +21 ft MSL N.A. R N.A.

3. Triaxial Seismic Switches (DRN 02-1931) a. Seismic Switch YS-SM 6060 RB -34 ft MSL M R SA (DRN 02-1931) b. Control Unit YZ-SM 6060 Control Room RAB +46 ft MSL M R SA*

4. Triaxial Response-Spectrum Recorders (DRN 02-1931) a. YR-SM 6040 RB +50 ft MSL N.A. R N.A. b. YR-SM 6041 RAB -34 ft MSL N.A. R N.A.

c. YR-SM 6042 RAB +22 ft MSL N.A. R N.A.

d. Peak Shock Annunciator YR-SM 6045 RB -34 ft MSL N.A. R N.A. (DRN 02-1931) (DRN 04-1309, Am. 94) e. Peak Shock Annunciator Control Unit YZ-SM 6045 Control Room RAB

+46 ft MSL N.A. N.A. SA (DRN 04-1309, Am. 94)

_________________

• With reactor control room annunciation.

3/4 3-12 AMENDMENT NO. 91 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION/METEOROLOGICAL LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY : At all times.

ACTION :

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status. (DRN 04-1191, Am. 91) b. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91) SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

3/43-13TABLE3.3-8METEOROLOGICALMONITORINGINSTRUMENTATIONMINIMUMLOCATIONINSTRUMENTSINSTRUMENT*(NominalElevation)OPERABLE1.WINDSPEEDa.Primary33ft(10m)1-(aorb)b.Secondary33ft(10m) c.Primary199ft(60m)12.WINDDIRECTION(SIGMATHETA)**a.Primary33ft(10m)1-(aorb)b.Secondary33ft(10m) c.Primary199ft(60m)13.TEMPERATUREDIFFERENCEa.Primary33ft-199ft(10m-60m)1-(a,b,orc)b.Secondary33ft-199ft(10m-60m)c.Primary33ft-199ft(10m-60m)____________________*Primary,Secondary-Referstothetoweronwhichinstrumentislocated,seeSpecification5.5.**Derivedfrominstantaneouswinddirectionmeasurements.

3/43-14TABLE4.3-5METEOROLOGICALMONITORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTSLOCATIONCHANNELCHANNELINSTRUMENT*(NominalElevation)CHECKCALIBRATION1.WINDSPEEDa.Primary33ft(10m)DSAb.Secondary33ft(10m)DSA c.Primary199ft(60m)DSA2.WINDDIRECTION(SIGMATHETA)**a.Primary33ft(10m)DSAb.Secondary33ft(10m)DSA c.Primary199ft(60m)DSA3.TEMPERATUREDIFFERENCEa.Primary33ft-199ft(10m-60m)DSAb.Secondary33ft-199ft(10m-60m)DSAc.Primary33ft-199ft(10m-60m)DSA___________________*Primary,Secondary-Referstothetoweronwhichinstrumentislocated,seeSpecification5.5.**Derivedfrominstantaneouswinddirectionmeasurements.

3/4 3-15 AMENDMENT NO. 123 3/4.3 INSTRUMENTATION 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8.1 As a minimum, the fire detection instrumentation for each fire detection zone shown shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

NOTE: For Fire Detection Instruments located inside the Containment, notify the SS/CRS to initiate investigation of a possible fire in the event of:

1. Any unexplainable Containment Fan Cooler intake temperature increase,

2. Containment Fan Cooler (average) intake temperatures increase beyond the specified limit of 120F, as based in Technical Specification 3.6.1.5.

NOTE: If FP-601A or FP-601B are closed, FPM-1 and FPM-2 Low Supervisory Air signal(s) should not be relied upon for indication of Containment conditions or system operation.

NOTE: Containment temperature recording is compensatory action for fire detection instrumentation and is based on observance of unexpected temperature increases being indication of a potential fire condition. Additional, indications may be, but are not limited to, equipment performance (motor amps, vibration, etc.) and abnormal indication from installed instrumentation and controls.

ACTION: (EC-25884, Am. 123) a. With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown inoperable, restore the inoperable instrument(s) to OPERABLE STATUS within 14 days or within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor and record air temperature at least once per hour at each of the operable Containment Fan Cooler Air Intakes. b. With more than one-half of the Function A fire detection instruments in any fire zone shown inoperable, or with any Function B fire detection instruments shown inoperable, or with any two or more adjacent fire detection instruments shown inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor air temperature at least once per hour at each of the operable Containment Fan Cooler Air Intakes.

(EC-25884, Am. 123) 3/4 3-16 AMENDMENT NO. 21, 91, 123 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued) (EC-25884, Am. 123) (EC-25884, Am. 123) (DRN 04-1191, Am. 91) d. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 12 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 12 months.

4.3.3.8.2 The NFPA Standard 72D supervised circuit supervision associated with the detector alarms of each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months. Circuits which are not accessible during plant operation shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

3/4 3-17Next page is 3/4 21AMENDMENT NO. 03, 58(DRN 02-912)TABLE 3.3-11FIRE DETECTION INSTRUMENTS(DRN 02-912)Fire Detection Instruments previously listed on pages 3/4 3 20were removed from this document with the completion of DC 3268.

3/4 3-21 AMENDMENT NO. 22, 126TABLE 3.3-11 FIRE DETECTION INSTRUMENTS FIRE ELEVATION HEAT SMOKE AREA ROOM NAME/NUMBER (ft) *(x/y) *(x/y) 1. REACTOR AUXILIARY BUILDING RAB 1A Main Control Panels 1,2,3,4,6,7, +46 10/0 8,18,35,36 (EC-1939, Am. 126) RAB 1A Control Room Proper +46 18/0(EC-1939, Am. 126) RAB 1B Emergency Equip. H&V Room +46 0/4 (EC-1939, Am. 126) RAB 1C Control Room Emergency Living Quarters +46 9/0(EC-1939, Am. 126) RAB 1D Computer Room (above raised floor) +46 5/0 Computer Room (below raised floor) +46 7/0 RAB 2 Ventilation Equip. Room +46 0/25 RAB 3 RAB Corridor to Relay Room +35 0/5 RAB HVAC Switchgear Equip. Room +46 0/4 RAB 3A RAB Battery Exhaust Fan Room +69 0/3 Elevator Vestibule +21 1/0 RAB 1E Cable Vault +35 0/17 RAB 5 Electrical Penetration Area "A" +35 0/12 RAB 6 Electrical Penetration Area "B" +35 0/10 RAB 7 Relay Room +35 0/7 Isolation Panel (9 Compartments) +35 18/0 RAB 8A High Voltage Switchgear Room "A" +21 1/11 RAB 8B Electrical Equip. Room and High +21 3/19 Voltage Switchgear Room "B" 480V Switchgear 3AB2 Room CEA M/G Set Room RAB 8C High Voltage Switchgear Room "A-B" +21 0/8 RAB 9 Remote Shutdown Panel Room +21 1/0 RAB 11 Battery Room "B" +21 1/0 RAB 12 Battery Room "AB" +21 1/0 RAB 13 Battery Room "A" +21 1/0 RAB 15 Emergency Diesel Gen. "B" Room +21 0/3 RAB 15A Emergency Diesel Gen. "B" Feed Tk +46 0/1 Room RAB 16 Emergency Diesel Gen. "A" Room +21 0/3 RAB 16A Emergency Diesel Gen. "A" Feed Tk. +46 0/1 Room RAB 17 CCW Heat Exchanger "B" +21 0/3 RAB 18 CCW Heat Exchanger "A" +21 0/3 RAB 19 CCW Pump "A" +21 0/2 RAB 20 CCW Pump "AB" +21 0/2 RAB 21 CCW Pump "B" +21 1/0 3/4 3-21a AMENDMENT NO. 22, 52, 63, 88, 89, 115, 123, 126TABLE 3.3-11 (Continued) FIRE DETECTION INSTRUMENTS FIRE ELEVATION HEAT SMOKE AREA ROOM NAME/NUMBER (ft) *(x/y) *(x/y) 1. REACTOR AUXILIARY BUILDING (Continued) RAB 22 Drumming Station +21 0/5 RAB 23 Corridor to CCW Pumps, Corridor +21 0/18 to CCW Heat Exchangers and Corridor to Emergency Diesel Gen. RAB 24 Hot Machine Shop +21 17/0 RAB 25 Equip. Access Area Wing Area +21 12/0RAB 27 H&V Room +7 0/4 (DRN 02-818, Am. 63) Electrical Area and Health Physics +7 0/31 (DRN 02-818, Am. 63) Offices I&C Room +7 0/5 (DRN 04-450, Am. 88) Communications Equip. Room +7 1/0 (DRN 04-956, Am. 89) (DRN 02-450, Am. 88) (DRN 04-956, Am. 89) (DRN 06-876, Am. 115) RAB 30 Administration Area (HP) - 4 32/0 (DRN 06-876, Am. 115) RAB 31 Corridors and Passageways 0/17 RAB 32 Wing Area - Auxiliary Component -35 22/0 Cooling Water Pump -4 21/0 RAB 33 S/D Cooling Heat Exchangers A&B -35 0/9 RAB 34 Valve Gallery Room A&B "A" -15.5 5/0 RAB 35 Safety Injection Pump Room B -35 5/0 RAB 36 Safety Injection Pump Room A -35 6/0 RAB 37 Motor-Driven Emergency Feedpump "A" -35 0/1 RAB 38 Motor-Driven Emergency Feedpump "B" -35 1/0 (EC-1939, Am. 126) RAB 39 Corridors & General Equip. Areas 8/22(EC-1939, Am. 126) RAB 40 Diesel Storage Tank "A" -35 1/0 RAB 41 Diesel Storage Tank "B" -35 1/0 2. REACTOR CONTAINMENT BUILDING** (DRN 02-238, Am. 52) (DRN 02-238, Am. 52) (EC-25884, Am. 123) (EC-25884, Am. 123) RCB Electrical Penetration Area A&B +21 44/0 RCB Reactor Cable Trays +46 16/0 CTA Cooling Tower "A" 16/0 1/0 CTB Cooling Tower "B" 2/0 1/0 3/4 3-21b AMENDMENT NO. 21, 123 TABLE 3.3-11 (Continued) FIRE DETECTION INSTRUMENTS FIRE ELEVATION HEAT SMOKE AREA ROOM NAME/NUMBER (ft) *(x/y) *(x/y)

3. FUEL HANDLING BUILDING

FHB General Area -35 12/0 Purification Pump Room, Fuel Pool +1 Pump "A", Fuel Pool Pump "B", +1 Fuel Pool Heater Exchanger and +1 Access Area +1 Emergency Filter Train Unit +1 Emergency Elect. Equip. Room +1 8/0 Operating Floor +46 1/0 Corridors +21 4/0 Truck Bay +18 1/0

TABLE NOTATIONS

• (x/y): x is the number of Function A (early warning fire detection and notification only) instruments.

y is the number of Function B (actuation of fire suppression systems and early warning and notification) instruments.

• • The fire detection instruments located within the containment are not required to be operable during the performance of Type A containment leakage rate tests.

(EC-25884, Am. 123) (EC-25884, Am. 123) 3/4 3-22 AMENDMENT NO. 91, 1203/4.3 INSTRUMENTATION3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATIONLIMITING CONDITION FOR OPERATION 3.3.3.9 The loose-part detection system shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTION:(EC-26965, Am. 120)a. With one or more loose-part detection system channels inoperable, restore within 30 days. Otherwise, enter the condition into the Corrective Action Program and obtain Condition Review Group approval of the corrective action plan. (EC-26965, Am. 120)(DRN 04-1191, Am. 91)b. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)SURVEILLANCE REQUIREMENTS 4.3.3.9 Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of: a. a CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. a CHANNEL FUNCTIONAL TEST at least once per 31 days, and c. a CHANNEL CALIBRATION at least once per 18 months.

3/4 3-23AMENDMENT NO. 28, 51 (DRN 02-216)3/4.3 INSTRUMENTATION (See note below) (DRN 02-216)3/4.3.3 MONITORING INSTRUMENTATION3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENTLIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Requirement 3.11.1.1 are not exceeded during releases to the environment. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).APPLICABILITY: At all times.ACTION:a.With radioactive liquid effluent monitoring instrumentation channelalarm/trip setpoint less conservative than required by the above Requirement, immediately suspend release to the environment of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.b.With less than the minimum number of radioactive liquid effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days if release to the environment are in progress or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.SURVEILLANCE REQUIREMENT 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8. (DRN 02-216)NOTE: TRM Specifications 3.3.3.10 and 4.3.3.10 are part of the Offsite Dose Calculation Manual(ODCM), reference UNT-005-014. Revision of these TRM Specifications requires the approval ofthe General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-24AMENDMENT NO. 04, 28, 51, (DRN 02-216)TABLE 3.3-12 (See note below) (DRN 02-216)RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSRELEASEINSTRUMENTOPERABLEINFORMATIONACTION1. BORON WASTE MANAGEMENT SYSTEM (BWMS):a. Radioactivity Monitor Providing Alarm and Automatic1Batch1 Termination of Release(PRM-IRE-0627)Release fromBoric Acidb. Waste (Process) Flow Rate Measurement Device1Condensate2 (BM-IFT-0627)Tanks2. LIQUID WASTE MANAGEMENT SYSTEM DISCHARGE (LWMS):a. Radioactivity Monitor Providing Alarm and Automatic1Batch1 Termination of Release (PRM-IRE-0647)Release fromLiquid Wasteb. Waste (Process) Flow Rate Measurement Device1Management2 (LWM-IFT-0647)Tanks (DRN 02-216)NOTE: TRM Table 3.3-12 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tablerequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-25AMENDMENT NO. 04, 51 (DRN 02-216)TABLE 3.3-12 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSRELEASEINSTRUMENTOPERABLEINFORMATIONACTION3. DRY COOLING TOWER SUMPS (DCTS):a. Radioactivity Monitor Providing Alarm and Automatic1/sumpRelease3 Termination of ReleasePath is [PRM-IRE-6775 (DCTS#1) and PRM-IRE-6776(DCTS#2)]NOT Alignedto LWMSb. Waste (Process) Flow Rate Measurement DeviceN/A(see Note #2)N/A (See Table Note. #1)4. INDUSTRIAL WASTE SUMP TURBINE BUILDING (TBIWS):a. Radioactivity Monitor Providing Alarm and Automatic1Release3 Termination of Release (PRM-IRE-6778)Path isNOT Alignedto LWMSb. Waste (Process) Flow Rate Measurement DeviceN/A(see Note #2)N/A (See Table Note. #1) (DRN 02-216)NOTE: TRM Table 3.3-12 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tablerequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-25aAMENDMENT NO. 51 (DRN 02-216)TABLE 3.3-12 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSRELEASEINSTRUMENTOPERABLEINFORMATIONACTION5. CIRCULATING WATER DISCHARGE (CWD) - BLOWDOWN AND1. Detectable ActivityBLOWDOWN HEAT EXCHANGER DISCHARGES AND AUXILIARYin Secondary Plant COMPONENT COOLING WATER PUMPS:2. During Blowdownof Steam Generatorsa. Radioactivity Monitor Providing Alarm and initiate1to CW System.4 Automatic Closure of Blowdown Valve BD-3033. During Discharge (PRM-IRE-1900)of ACCW Basins

b. Waste (Process) Flow Rate Measurement DeviceN/Ato CW SystemN/A (See Table Note. #1)6. STEAM GENERATOR BLOWDOWN (SGB) EFFLUENT LINEDuring BlowdownOf S / Gsa. Continuous Composite Sampler1to CW System or4Metal Waste Ponds (see Note #3) (DRN 02-216)NOTE: TRM Table 3.3-12 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tablerequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-26AMENDMENT NO. 02, 51 (DRN 02-216)TABLE 3.3-12 (Continued, See note below) (DRN 02-216)TABLE NOTATIONSNOTE #1Waste (process) Flow Measurement Devices are notinstalled on the release paths for the DCTS, TBIWS or CWD monitors. For theserelease paths, pump performance curves generated in place or some form of volumetric estimate or measurement device may be used for effluent flow rate estimates.NOTE #2DCTS and TBIWS monitor operation should be maximizedduring releases to the environment, even when detectable activity is not present inthe CCW/ACCW or secondary systems, to provide capability for release termination in the event that Primary to Secondary or Primary to CCW leakage occurs.NOTE #3The Steam Generator Blowdown Composite Sampler iscapable of sampling blowdown discharge to either the CW System or Waste Ponds.Blowdown to the Waste Ponds is not allowed unless radiation monitoring capable of release termination is added to the release path.ACTION STATEMENTSACTION 1With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that prior to initiating a release:a.At least two independent samples are analyzed in accordancewith Requirement 4.11.1.1.1 andb.At least two technically qualified members of the FacilityStaff independently verify the release rate calculations and discharge valve lineup.ACTION 2With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per FOUR hours during actual releases. Pumpperformance curves generated in place may be used to estimate flow. (DRN 02-216)NOTE: TRM Table 3.3-12 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager PlantOperations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-27AMENDMENT NO. 51 (DRN 02-216)TABLE 3.3-12 (Continued, See note below) (DRN 02-216)ACTION STATEMENTSACTION 3With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that grab samples are collected and are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection time forradioactivity at a lower limit of detection of at least 5 E-07 microcurie/ml. Sample collection and analysis is NOT required if the release path for the DCTS/TBIWS is aligned to the LWMS. The sample collection frequency is:a.At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of thesecondary coolant is greater than 0.01 microcurie/gram DOSE EQUIVALENT I-131, orb.At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of thesecondary coolant is less than or equal to 0.01 microcurie/gram DOSEEQUIVALENT I-131.ACTION 4With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that grab samples are collected and are analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection time forradioactivity at a lower limit of detection of at least 5 E-07 microcurie/ml. Sample collection and analysis is NOT required if no detectable activity exists in either the secondary plant or CCW/ACCW systems. Sampling of Steam Generator Blowdown is required during blowdown to the CW System or Waste Ponds. The sample collection frequency is:a.At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of thesecondary coolant is greater than 0.01 microcurie/gram DOSE EQUIVALENT I-131, orb.At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of thesecondary coolant is less than or equal to 0.01 microcurie/gram DOSEEQUIVALENT I-131. (DRN 02-216)NOTE: TRM Table 3.3-12 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations(GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-28AMENDMENT NO. 04, 28 45TABLE 4.3-8RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNELCHANNELSOURCECHANNELFUNCTIONALRELEASEINSTRUMENTCHECKCHECKCALIBRATIONTESTINFORMATION1. BORON WASTE MANAGEMENT SYSTEM DISCHARGE (BWMS):a. Radioactivity Monitor Providing AlarmPrior toPrior to18 Months (3)Quarterly (1)Batch and Automatic Termination of ReleaseRelease (6)Release (6)Release from (PRM-IRE-0627)Boric AcidCondensateb. Waste (Process) Flow Rate MeasurementDaily (4)N/A18 MonthsTanks Device.(BM-IFT-0627)2. LIQUID WASTE MANAGEMENT SYSTEM DISCHARGE (LWMS):a. Radioactivity Monitor Providing AlarmPrior toPrior to18 Months (3)Quarterly (1)Batch and Automatic Termination of ReleaseRelease (6)Release (6)Release from (PRM-IRE-0647)Liquid WasteManagementb. Waste (Process) Flow Rate MeasurementDaily (4)N/A18 MonthsTanks Device (LWM-IFT-0647)3. DRY COOLING TOWER SUMPS (DCTS):a. Radioactivity Monitor Providing AlarmDailyMonthly18 Months (3)Quarterly (2)Release and Automatic Termination of ReleasePath is (PRM-IRE-6775 and PRM-IRE-6776)NOT Alignedto LWMSb. Waste (Process) Flow Rate MeasurementN/AN/AN/AN/A 3/43-29AMENDMENTNO.04TABLE4.3-8(Continued)RADIOACTIVELIQUIDEFFLUENTMONITORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTSCHANNELCHANNELSOURCECHANNELFUNCTIONALRELEASEINSTRUMENTCHECKCHECKCALIBRATIONTESTINFORMATION4.INDUSTRIALWASTESUMPSTURBINEBUILDING(IWSTB):a.RadioactivityMonitorProvidingAlarmandDailyMonthly18Months(3)Quarterly(2)ReleaseAutomaticTerminationofReleasePathis(PRM-IRE-6778)NOTAlignedtoLWMSb.Waste(Process)FlowRateMeasurementN/AN/AN/AN/A5.CIRCULATINGWATERDISCHARGE(CWD)BLOWDOWNANDBLOWDOWNHEATEXCHANGER1.SteamDISCHARGEANDAUXILIARYCOMPONENTCOOLINGGeneratorsWATERPUMPS:BlowdowntoCW(TERMINATIONOFBLOWDOWNDISCHARGEONLY)Systema.RadioactivityMonitorProvidingAlarmDailyMonthly18Months(3)Quarterly(2)2.DischargeofandinitiateAutomaticClosureofACCWBasinstoBlowdownDischargeValveBD-303CWSystemb.Waste(Process)FlowRateMeasurementN/AN/AN/AN/A6.STEAMGENERATORBLOWDOWN(SGB)EFFLUENTBlowdownLINE:ofS/Gstoa.ContinuousCompositeSamplerDaily(5)N/A18MonthsQuarterlyCWSystemorMetalWastePonds 3/4 3-30AMENDMENT NO. 04TABLE 4.3-8 (Continued)TABLE NOTATIONS1. The CHANNEL FUNCTIONAL TEST for BWM and LWM shall alsodemonstrate that automatic isolation of this pathway and control room alarmannunciation occur if any of the following conditions exists.a. Instrument indicates measured levels above the alarm/trip setpoint.b. Circuit failure.

c. Instrument indicates a downscale failure.2. The CHANNEL FUNCTIONAL TEST for DCTS, TBIWS and CWD shall alsodemonstrate that automatic isolation of this pathway occurs if the instrumentindicates measured levels above the alarm/trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:a. Instrument indicates measured levels above the alarm setpoint.b. Circuit failure.

c. Instrument controls not set in operate mode.3. The initial CHANNEL CALIBRATION shall be performed using oneor more of the reference standards certified by the National Institute of Standards and Technology NIST or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system for over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.4. CHANNEL CHECK for BWM and LWM shall consist of verifyingindication of flow during periods of release. CHANNEL CHECK shall be made atleast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.5. CHANNEL CHECK for Steam Generator BlowdownComposite Samplershall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which releases are made to theCirculating Water System or Waterford 3 waste pond.6. CHANNEL CHECK for BWM and LWM shall consist of observing a satisfactorychannel source check which is also performed prior to the release.

3/4 3-31AMENDMENT NO. 28, 51 (DRN 02-216)3/4.3 INSTRUMENTATION (See note below) (DRN 02-216)3/4.3.3 MONITORING INSTRUMENTATION3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENTLIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Requirement 3.11.2.1 are not exceeded during releases to the environment. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).APPLICABILITY: As shown in Table 3.3-13ACTION:a.With a radioactive gaseous effluent monitoringinstrumentation channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend release to the environment of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.b.With less than the minimum number of radioactivegaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days if releases to the environment are in progress or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9. (DRN 02-216)NOTE: TRM Specifications 3.3.3.11 and 4.3.3.11 are part of the Offsite Dose Calculation Manual(ODCM), reference UNT-005-014. Revision of these TRM Specifications requires the approval of theGeneral Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 3-32AMENDMENT NO. 04,35,89TABLE 3.3-13RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIONMINIMUMCHANNELSINSTRUMENTOPERABLEAPPLICABILITYACTION1. GASEOUS WASTE MANAGEMENT SYSTEM (GWMS): a. Noble Gas Activity Monitor Providing Alarm and 1Batch Release1 Automatic Termination of Release (PRM-IRE-0648)fromWaste Gas(DRN 04-956, Am. 89)b. Waste (Process) Flow Rate Measurement1Decay Tank5 Device (GWM-IFIT-0648)(DRN 04-956, Am. 89)2. CONDENSER VACUUM PUMPS - MAIN CONDENSER EVACUATION (MCES) AND TURBINE GLAND SEALING SYSTEM:a. Noble Gas Activity Monitor (PRM-IRE-0002)1Main3Condenser isb. Iodine Sampler (see NOTE 1)1Under a vacuum4c. Particulate Sampler (see NOTE 1).1 4d. Sampler Flow Rate Monitor (see NOTE 1)1 6 3/43-33AMENDMENTNO.04TABLE3.3-13(Continued)RADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONMINIMUMCHANNELSINSTRUMENTOPERABLEAPPLICABILITYACTION3.REACTORAUXILIARYBUILDINGVENTILATIONSYSTEM(PLANTSTACK):a1.NobleGasActivityMonitorProvidingAlarmand1ContainmentPurge2AutomaticTerminationContainmentPurge(PRM-IRE-0100.1S&2S)a2.NobleGasActivityMonitor(PRM-IRE-0100.1S,2Sor0110)1AtAllTimes3 b.IodineSampler(seeNOTE1)1AtAllTimes4 c.ParticulateSampler(seeNOTE1)1AtAllTimes4 d.SamplerFlowRateMonitor(seeNOTE1)1AtAllTimes6 e.Waste(Process)FlowRateMonitor(PRM-IFT-0100-12/22)1AtAllTimes54.FUELHANDLINGBUILDINGVENTILATIONSYSTEM-(NORMALEXHAUST):a.NobleGasActivityMonitor(PRM-IRE-5107AorB)1With3 b.IodineSampler(seeNOTE1)1Irradiated4 c.ParticulateSampler(seeNOTE1)1Fuelin4 d.SamplerFlowRateMonitor(seeNOTE1)1theStorage6 e.Waste(Process)FlowRateMonitor(PRM-IFT-5107AorB)1Pool5 3/43-34AMENDMENT35TABLE3.3-13(Continued)TABLENOTATIONSNOTE1ThesamplerflowratemonitoroperabilityalsosatisfiestheparticulateandIodinesamplerrequirementsaslongasthefiltermediafortheapplicablesamplepumpisinstalled.FortheMCESandPlantStackWRGM's,thelowrangedetectorsamplepumpisnormally usedtosatisfytheserequirements.ForthePlantStackandFuelHandlingBuildingPIG'S,thefiltermedianecessarytosatisfytheparticulateandIodinesamplerisnormallyapplicabletothe Iodine/gaschannelsamplepump.ACTIONSTATEMENTSACTION1WiththenumberofchannelsOPERABLElessthanrequiredbytheMinimumChannelsOPERABLErequirement,thecontentsofthetank(s)maybereleasedtotheenvironmentprovidedbesteffortsaremadetorepairtheinstrumentandthatpriortoinitiatingtherelease:a.Atleasttwoindependentsamplesofthetank'scontentsareanalyzed,andb.Atleasttwotechnicallyqualifiedmembersofthefacilitystaffindependentlyverifythereleaseratecalculationsand dischargevalvelineup.ACTION2Withthenumberofchannelsoperablelessthanrequired,containmentpurgingofradioactiveeffluentsmustbeimmediatelysuspended.

ThisACTIONonlyappliestothenoblegaschannelsofthePlantStackPIG's(PRM-IRE-0100.1SandPRM-IRM-0100.2S).ACTION3WiththenumberofNobleGasactivitymonitorChannelsOPERABLElessthantheminimumchannelsOPERABLErequirement,effluentreleases viathispathwaymaycontinueprovidedbesteffortsaremadeto repairtheinstrumentandthatgrabsamplesaretakenatleastonce per12hoursandthesesamplesareanalyzedforgrossactivitywithin24hours.FortheMainCondenserEvacuationandTurbineGlandSealingSystems(MCES),thisACTIONonlyappliesduring releaseswithTurbineGlandSealingSystemorCondenserVacuumPumpsinOPERATION.ACTION4WiththenumberofParticulate/IodineSamplerChannelsOPERABLElessthantheminimumchannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedbesteffortsaremadetorepairtheinstrumentandthatsamplesarecontinuously collectedwithauxiliarysamplingequipmentasrequiredinTable4.11-2,withinonehourafterthechannelhasbeendeclared inoperable.FortheMCESWRGM,thisACTIONonlyappliesduring periodsofPrimarytoSecondaryleakage.

3/43-35AMENDMENT35TABLE3.3-13(Continued)TABLENOTATIONSACTION5WiththenumberofWaste(Process)flowratemonitorchannelsOPERABLElessthantheminimumchannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedbest effortsaremadetorepairtheinstrumentandthatflowrateis estimatedatleastonceeveryfourhours.Waste(Process)flowrateestimatesmaybeintheformofalogofrunningventilation equipmentwhichisupdatedatfourhourintervals.Forthewastegasholduptank,thisACTIONisapplicableonlyduringperiodsof release.ACTION6WiththenumberofSamplerFlowRateMonitorChannelsOPERABLElessthantheminimumchannelsOPERABLErequirement,effluentreleasesviathispathwaymaycontinueprovidedbesteffortsaremadetorepairtheinstrumentandflowrateisestimatedatleastonceeveryfourhours.FortheMCESWRGM,thisACTIONonlyappliesduringperiodsofPrimarytoSecondaryleakage.

3/4 3-36AMENDMENT04,35,89TABLE 4.3-9RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSCHANNELCHANNELCHANNELSOURCECHANNELFUNCTIONALRELEASEINSTRUMENTCHECKCHECKCALIBRATIONTESTINFORMATION1. GASEOUS WASTE MANAGEMENT SYSTEM (GWMS):a. Noble Gas Activity Monitor Providing AlarmPrior toPrior to18 Months (4)Quarterly (1)Batch and Automatic Termination of ReleaseRelease(6)Release(6)Release from (PRM-IRE-0648)Waste Gas(DRN 04-956, Am. 89)b. Waste (Process) Flow Rate MeasurementDaily (5)N/A18 MonthsQuarterly Device (GWM-IFIT-0648)(DRN 04-956, Am. 89)2. CONDENSER VACUUM PUMPS - MAIN CONDENSEREVACUATION (MCES) AND TURBINE GLAND SEALING SYSTEM (MCES):a. Noble Gas Activity MonitorDailyMonthly18 Months (4)Quarterly (2)Main (PRM-IRE-0002)Condenseris under ab. Iodine SamplerWeeklyN/AN/AN/Avacuumc. Particulate SamplerWeeklyN/AN/AN/A

d. Sampler Flow Rate MonitorDailyN/A18 MonthsQuarterly 3/437AMENDMENTNO.040TABLE4.3-9(Continued)RADIOACTIVEGASEOUSEFFLUENTMONITORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTSCHANNELCHANNELCHANNELSOURCECHANNELFUNCTIONALRELEASEINSTRUMENTCHECKCHECKCALIBRATIONTESTINFORMATION3.REACTORAUXILIARYBUILDINGVENTILATIONSYSTEM(PLANTSTACK):a.NobleGasActivityMonitorProvidingAlarmDailyMonthly18Months(4)Quarterly(3)AtandAutomaticTerminationofRelease(PRM-IRE-0100.1Sor2S)Allb.IodineSamplerWeeklyN/AN/AN/Ac.ParticulateSamplerWeeklyN/AN/AN/ATimes d.SamplerFlowRateMonitorDailyN/A18MonthsQuarterly e.Waste(Process)FlowRateMonitorDailyN/A18MonthsQuarterly(PRM-IFT-0100-12/22)4.FUELHANDLINGBUILDINGVENTILATIONSYSTEM-(NORMALEXHAUST):a.NobleGasActivityMonitorDailyMonthly18Months(4)Quarterly(2)With(PRM-IRE-5107AorB)Irradiatedb.IodineSamplerWeeklyN/AN/AN/AFuelinc.ParticulateSamplerWeeklyN/AN/AN/AtheStoraged.SamplerFlowRateMonitorDailyN/A18MonthsQuarterlyPoole.Waste(Process)FlowRateMonitorDailyN/A18MonthsQuarterly(PRM-IFT-5107AorB) 3/438AMENDMENTNO.04TABLE4.3-9TABLENOTATIONS1.TheCHANNELFUNCTIONALTESTforWasteGasHoldupSystemshallalsodemonstratethatautomaticisolationofthispathwayandcontrolroomalarmannunciationoccursifanyofthefollowingconditionsexists:a.Instrumentindicatesmeasuredlevelsabovethealarm/tripsetpoint.b.Circuitfailure.c.Instrumentindicatesadownscalefailure.2.TheCHANNELFUNCTIONALTESTforMCESandFuelHandlingBuildingshallalsodemonstratethatcontrolroomalarmannunciationoccursifanyofthefollowingconditionsexists:a.Instrumentindicatesmeasuredlevelsabovethealarmsetpoint.b.Circuitfailure.3.TheCHANNELFUNCTIONALTESTforPlantStackshallalsodemonstratethatautomaticisolationofthispathwayoccursiftheinstrumentindicatesmeasuredlevelsabovethealarm/tripsetpointandthatcontrolroomalarmannunciationoccursifanyofthefollowingconditionsexists:a.Instrumentindicatesmeasuredlevelsabovethealarmset.b.Circuitfailure.c.Instrumentcontrolsnotsetinoperatemode.4.TheinitialCHANNELCALIBRATIONshallbeperformedusingoneormoreofthereferencestandardscertifiedbytheNationalInstituteofStandards andTechnology(NIST)orusingstandardsthathavebeenobtainedfromsuppliersthatparticipateinmeasurementassuranceactivitieswithNIST.

Thesestandardsshallpermitcalibratingthesystemoveritsintendedrangeofenergyandmeasurementrange.ForsubsequentCHANNELCALIBRATION,sourcesthathavebeenrelatedtotheinitialcalibrationmaybeusedinlieuofthereferencestandardsassociatedwiththeinitial calibration.5.CHANNELCHECKforGWMSshallconsistofverifyingindicationofflowduringperiodsofrelease.CHANNELCHECKshallbemadeatleastonceper24hoursondaysonwhichcontinuous,periodic,orbatchreleasesare made.6.CHANNELCHECKforGWMSshallconsistofobservingasatisfactorychannelsourcecheckwhichisalsoperformedpriortotherelease.

3/4 3-39 AMENDMENT NO. 91, 107 3/4.3 INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY: MODES 1, 2*, and 3*.

ACTION:

a. With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With the above required overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS (DRN 04-1191, Am. 91) 4.3.4.1 The provisions of TRM SR 4.0.4 are not applicable. (DRN 04-1191, Am. 91) 4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE: (DRN 06-723, Am. 107) a. At least once every 184 days (under direct observation) each of the following valves is cycled through at least one complete cycle from the running position. (DRN 06-723, Am. 107) 1. Four high pressure throttle valves. 2. Four high pressure governor valves.

3. Six low pressure reheat stop valves.

4. Six low pressure reheat intercept valves.

b. At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems. c. At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion. (DRN 06-723, Am. 107) d. At least once per 40 operating months by inspecting the installed light low pressure turbine discs, and not to exceed# at least once per 90 operating months by inspecting the installed heavy low pressure turbine discs. (DRN 06-723, Am. 107) ____________________ *With any main steam isolation valve and/or any main steam line isolation valve bypass valve not fully closed. (DRN 06-723, Am. 107) #The provisions of TRM SR 4.0.2 are not applicable to this requirement. (DRN 06-723, Am. 107) 3/4 3-40AMENDMENT NO. 56, 74, 75,91,99(DRN 02-677, Am. 56)3/4.3 INSTRUMENTATION3/4.3.5 ULTRASONIC FLOWMETERLIMITING CONDITION FOR OPERATION3.3.5 Two ultrasonic flowmeters (UFMs) shall be OPERABLE.(DRN 03-0247, Am. 75)APPLICABILITY: MODE 1, above 50% power*(DRN 03-0247, Am. 75)ACTION:With one or both UFMs inoperable, perform the following:(DRN 03-0247, Am. 75)a.With COLSS in service: (DRN 02-1889, Am. 74)(DRN 02-1889, Am. 74)(DRN 02-1889, Am. 74; DRN 03-247, Am. 75;DRN 04-1244, Am. 99)1.Reduce THERMAL POWER to less than or equal to 3697 MWt (99.5%)within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of last calibration factor update.2.Reduce THERMAL POWER to less than or equal to 3660 MWt (98.5%)within 31 days of last calibration factor update.b.With COLSS out of service, return the UFM to service prior to the next required CPCS calibration or reduce THERMAL POWER to less than or equal to 3660 MWt (98.5%).(DRN 02-1889, Am. 74; DRN 03-247, Am. 75;DRN 04-1244, Am. 99)(DRN 04-1191, Am. 91)The provisions of TRM LCO 3.0.3 and3.0.4 are not applicable.(DRN 04-1191, Am. 91)SURVEILLANCE REQUIREMENTS4.3.5The ultrasonic flowmeters shall be demonstrated OPERABLE:a.By the performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.b.By the performance of a CHANNEL CHECK at least once every 31 days to demonstrate continuous calibration of COLSS MSBSCAL and FWBSCAL.(DRN 02-677, Am. 56)(DRN 03-0247, Am. 75)* Following a reactor power cutback, entry is not required provided UFM is returned to service within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.(DRN 03-0247, Am. 75)