ML15212A902

Calvert Cliffs, Units 1 and 2 - Supplemental Information Regarding TSTF-425 License Amendment Request

ML15212A902
Person / Time
Site:	Calvert Cliffs
Issue date:	07/30/2015
From:	Gellrich G H Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TSTF-425
Download: ML15212A902 (16)

Text

~Exet~on GenerationGeorge H. GellrichSite Vice PresidentCalvert Cliffs Nuclear Power Plant1650 Calvert Cliffs ParkwayLusby, MD 20657410 495 5200 Office717 497 3463 Mobilew~ww~exeloncoro~comgeorge.gellrich@exeloncorp.com10 CFR 50.90July 30, 2015U. S. Nuclear Regulatory CommissionATTN: Document ControJ DeskWashington, DC 20555Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2Renewed Facility Operating License Nos. DPR-53 and DPR-69NRC Docket Nos. 50-317 and 50-318

References:

Supplemental Information Regardincq TSTF-425 License Amendment Reqiuest1. Letter from G. H. Gellinch (Exelon) to Document Control Desk (NRC), datedMay 1, 2014, License Amendment Request: Adoption of TechnicalSpecification Task Force Traveler (TSTF) -425, Revision 3, RelocateSurveillance Frequencies to Licensee Control -RITSTF Initiative Sb2. Letter from N. S. Morgan (NRC) to G. H. GellInch (Exelon), datedOctober 21, 2014, Issuance of Amendments Regarding Enhancements toDiesel Generator Surveillance Requirements3. Letter from A. N. Chereskin (NRC) to G. H. Gellinch (Exelon), dated July 23,2015, Amendment Regarding New Technical Specification 3.7.18 forAtmospheric Dump ValvesReference 1 submitted a license amendment request to adopt TSTF-425. Since the submittal ofReference 1, two license amendments have been issued by the Nuclear RegulatoryCommission that each include an additional Surveillance Requirement. Reference 2 addedSurveillance Requirement SR 3.8.1.17 which requires diesel generator operation for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Reference 3 added Surveillance Requirement SR 3.7.18.1 which requires cycling of theatmospheric dump valves. These Surveillance Requirements fall within the scope of TSTF-425,Revision 3 as shown on the attached Comparison Matrix in red [Attachment (1)]. Therefore, werequest their inclusion in this license amendment request. The marked up TechnicalSpecification and Technical Specification Bases pages are included as Attachment (2). Thesemarked up pages conform to TSTF-425, Revision 3.This additional information does not change the No Significant Hazards Determination providedin Reference 1. No regulatory commitments are contained in this letter.Aocil Document Control DeskJuly 30, 2015Page 2Should you have questions regarding this matter, please contact Mr. Larry D. Smith at(410) 495-5219.I declare under penalty of perjury that the foregoing is true and correct. Executed on July 30,2015.Respectfully,George H. GelrinchSite Vice PresidentGHG/PSF/bjmAttachments: (1) Comparison Matrix(2) Marked up Technical Specification and Technical Specification BasesPagescc: NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert CliffsNRC Regional Administrator, Region I S. Gray, MD-DNR ATTACHMENT (1)COMPARISON MATRIXCalvert Cliffs Nuclear Power PlantJuly 30, 2015 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPShtdwnMrgn SD)3.1.1 3.1.1Verify _____SDM___within____limits___SR 3.1.1.1 SR 3.1.1.1Rea_____ti___ity_____Balan______e__3.1.2CEA_______Ali___________e____t___3.1.4 3.1.4Verify indicated position within 7 inches SR 3.1.4.1 SR 3.1 .4.1Verify motion inhibit is Operable SR 3.1.4.2 SR 3.1.4.2Verify deviation circuit is Operable SR 3.1.4.3 SR 3.1 .4.3Verify CEA freedom of movement SR 3.1.4.4 SR 3.1.4.4Perform Channel Functional Test SR 3.1.4.5 SR 3.1.4.5Shutdown CEA Insertion Limits 3.1.5 3.1.5Verify CEA is withdrawn SR 3.1.5.1 SR 3.1.5.1Regulating CEA Insertion Limits 3.1.6 3.1.6Verify CEA group position is within limits SR 3.1.6.1 SR 3.1.6.1Verify CEA insertion times SR 3.1 .6.2 SR 3.1 .6.2Verify PDIL alarm circuit is Operable SR 3.1.6.3 SR 3.1.6.3STE-SDM 3.1.7 3.1.7Verify CEA insertion is within acceptance criteria SR 3.1.7.1 SR 3.1.7.1STE-Modes 1 and 2 3.1.8 3.1.8Verify Thermal Power is within test power plateau SR 3.1.8.1 SR 3.1.8.1LHR 3.2.1 3.2.1Verify ASI alarm setpoints SR 3.2.1.1 SR 3.2.1.2Verify incore detector local power density alarms SR 3.2.1.2 SR 3.2.1.3Verify incore local power density alarm setpoints SR 3.2.1 3 SR 3.2.1.4Fxy 3.2.2Fr 3.2.3 3.2.3Verify value of Fr SR 3.2.3.1 SR 3.2.3.1Tq 3.2.4 3.2.4Verify value of Tq SR 3.2.4.1 SR 3.2.4.1ASI 3.2.5 3.2.5Verify ASI is within limits SR 3.2.5.1 SR 3.2.5.1RPS Instrumentation -Operating 3.3.1 3.3.1Perform Channel Check SR 3.3.1.1 SR 3.3.1.1Perform calibration of excore and dT power channels SR 3.3.1.2 SR 3.3.1.2Calibrate power range excores using incore detectors SR 3.3.1.3 SR 3.3.1.3Perform Channel Functional Test SR 3.3.1.4 SR 3.3.1.4Perform Channel Calibration on excore power range channels SR 3.3.1.5 SR 3.3.1.5Perform Channel Functional Test on automatic bypass removal SR 3.3.1 .7Perform Channel Calibration of each RPS channel SR 3.3.1.8 SR 3.3.1 .8Verify RPS response times SR 3.3.1.9 SR 3.3.1.9RPS Instrumentation -Shutdown 3.3.2 3.3.2Perform Channel Check of wide range power channel SR 3.3.2.1 SR 3.3.2.1Perform Channel Functional Test of power rate of change trip SR 3.3.2.2Perform Channel Functional Test of automatic bypass removal SR 3.3.2.3 SR 3.3.2.3Perform Channel Calibration, including bypass functions SR 3.3.2.4 SR 3.3.2.4RPS Logic and Tri Initiation 3.3.3 3.3.3Perform Channel Functional Test on RTCB channel SR 3.3.3.1 SR 3.3.3.1 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPPerform Channel Functional Test on RPS logic SR 3.3.3.2 SR 3.3.3.2Perform Channel Functional Test with undervoltage and shunt trips SR 3.3.3.4ESFAS Instrumentation 3.3.4 3.3.4Perform Channel Check on each ESFAS channel SR 3.3.4.1 SR 3.3.4.1Perform Channel Functional Test on each ESFAS channel SR 3.3.4.2 SR 3.3.4.2Perform Channel Functional Test on automatic block removal SR 3.3.4.3Perform Channel Calibration of ESFAS channels, including block SR 3.3.4.4 SR 3.3.4.4removalVerify ESF response time in limits SR 3.3.4.5 SR 3.3.4.5ESFAS Logic and Manual Trip/Actuation 3.3.5 3.3.5Perform Channel Functional Test on ESFAS Logic channel SR 3.3.5.1 SR 3.3.5.1Perform Channel Functional Test on ESFAS trip/actuation channel SR 3.3.5.2 SR 3.3.5.2DG-LOVS 3.3.6 3.3.6Perform Channel Check SR 3.3.6.1Perform Channel Functional Test SR 3.3.6.2 SR 3.3.6.1Perform Channel Calibration SR 3.3.6.3 SR 3.3.6.2CPIS/CRS 3.3.7 3.3.7Perform Channel Check on radiation monitors SR 3.3.7.1 SR 3.3.7.1Perform Channel Functional Test on radiation monitor channel SR 3.3.7.2 SR 3.3.7.3Perform Channel Functional Test on actuation logic channel SR 3.3.7.3 SR 3.3.7.2Perform Channel Calibration on radiation monitor channel SR 3.3.7.4 SR 3.3.7.4Perform Channel Functional Test on manual trip/actuation channel SR 3.3.7.5 SR 3.3.7.5Verify response time is within limits SR 3.3.7.6 SR 3.3.7.6CRIS/CR RS 3.3.8 3.3.8Perform Channel Check on radiation monitor channel SR 3.3.8.1 SR 3.3.8.1Perform Channel Functional Test on the radiation monitor channel SR 3.3.8.2 SR 3.3.8.2Perform Channel Functional Test on actuation logic channel SR 3.3.8.3Perform Channel Calibration on the radiation monitor channel SR 3.3.8.4 SR 3.3.8.3Perform Channel Functional Test on the manual trip channel SR 3.3.8.5Verify response times are within limits SR 3.3.8.6CVCS Isolation Signal 3.3.9 3.3.9Perform Channel Check SR 3.3.9.1 SR 3.3.9.1Perform Channel Functional Test on CVCS isolation channels SR 3.3.9.2 SR 3.3.9.2Perform Channel Calibration on CVCS sensor channels SR 3.3.9.3 SR 3.3.9.3Verify response time is within limits SR 3.3.9.4Shield Building Filtration Actuation Signal 3.3.10PAM Instrumentation 3.3.11 3.3,10Perform Channel Check for normally energized channels SR 3.3.11.1 SR 3.3.10.1Perform Channel Calibration SR 3.3.11.2 SR 3.3.10.3Remote Shutdown System/Instrumentation 3.3.12 3.3.11Perform Channel Check for normally energized channels SR 3.3.12.1 SR 3.3.11.1Verify control circuit and transfer switch works SR 3.3.12.2Perform Channel Calibration for each channel SR 3.3.12.3 SR 3.3.11.2Perform Channel Functional Test SR 3.3.12.4Power Monitoring Channels/Wide Range Logarithmic Neutron 3.3.13 3.3.12Flux Monitor ChannelsPerform Channel Check SR 3.3.13.1 SR 3.3.12.1 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPPerform Channel Functional Test SR 3.3.13.2Perform Channel Calibration SR 3.3.13.3 SR 3.3.12.3RCS Pressure, Temperature and Flow DNBR Limits 3.4.1 3.4.1Verify pressurizer pressure is within limits SR 3.4.1.1 SR 3.4.1.1Verify cold leg ternperatures are within limits SR 3.4.1.2 SR 3.4.1.2Verify RCS total flow SR 3.4.1.3 SR 3.4.1.3Verify heat balance/measured RCS flow is within limits SR 3.4.1.4 SR 3.4.1.4RCS Minimum Temperature for Criticality 3.4.2RCS P/T Limits 3.4.3 3.4.3Verify RCS temperature, pressure, rates are within limits SR 3.4.3.1 SR 3.4.3.1RCS Loops -Modes 1 and 2 3.4.4 3.4.4Verify RCS loops in operation SR 3.4.4.1 SR 3.4.4.1RCS Loops -Mode 3 3.4.5 3.4.5Verify RCS loop is in operation SR 3.4.5.1 SR 3.4.5.1Verify secondary side SG water level SR 3.4.5.2 SR 3.4.5.2Verify correct breaker alignment SR 3.4.5.3 SR 3.4.5.3RCS Loops -Mode 4 3.4.6 3.4.6Verify one RCS/SDC in operation SR 3.4.6.1 SR 3.4.6.1Verify secondary side SG water level SR 3.4.6.2 SR 3.4.6.2Verify correct breaker alignment SR 3.4.6.3 SR 3.4.6.3RCS Loops -Mode 5, Loops Filled 3.4.7 3.4.7Verify SDC train is in operation SR 3.4.7.1 SR 3.4.7.1Verify secondary side SG water level SR 3.4.7.2 SR 3.4.7.2Verify correct breaker alignment SR 3.4.7.3 SR 3.4.7.3RCS Loops -Mode 5, Loops not Filled 3.4.8 3.4.8Verify SDC train is in operation SR 3.4.8.1 SR 3.4.8.1Verify correct breaker alignment SR 3.4.8.2 SR 3.4.8.2Pressurizer 3.4.9 3.4.9Verify pressurizer water level SR 3.4.9.1 SR 3.4.9.1Verify capacity of heaters SR 3.4.9.2 SR 3.4.9.2Verify heaters are powered from emergency power SR 3.4.9.3Pressurizer PORVs 3.4.11 3.4.11Perform Channel Functional Test of PORVs SR 3.4.11.1Perform cycle of block valves SR 3.4.11.1 SR 3.4.11.2Perform cycle of PORVs SR 3.4.11.2 SR 3.4.11.3Perform Channel Calibration of PORVs SR 3.4.11.4Perform cycle of control valve and check valve on PORV SR 3.4.11.3Verify PORVs and block valves are powered from emergency power SR 3.4.11.4LTOP System 3.4.12 3.4.12Verify one HPSI capable of RCS injection SR 3.4.12.1 SR 3.4.12.1Verify one charging pump capable of RCS injection SR 3.4.12.2Verify SITs are isolated SR 3.4.12.3Verify HPSI MOVs are capable of manual alignment SR 3.4.12.2Verify RCS vent is open SR 3.4.12.4 SR 3.4.12.3Verify PORV block valve is open SR 3.4.12.5 SR 3.4.12.4Perform Channel Functional Test for PORVs SR 3.4.12.6 SR 3.4.12.53 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPPerform Channel Calibration on PORVs SR 3.4.12.7 SR 3.4.12.6RCS Operational Leakage 3.4.13 3.4.13Verify leakage is within limits SR 3.4.13.1 SR 3.4.13.1Verify primary to secondary leakage is within limits SR 3.4.13.2 SR 3.4.13.2RCS PIV Leakage 3.4.14RCS Leakage Detection Instrumentation 3.4.15 3.4.14Perform Channel Check of radiation monitor SR 3.4.15.1 SR 3.4.14.1Perform Channel Functional Test of radiation monitor SR 3.4.15.2 SR 3.4.14.2Perform Channel Calibration of sump monitor SR 3.4.15.3 SR 3.4.14.3Perform Channel Calibration of radiation monitor SR 3.4.15.4 SR 3.4.14.4Perform Channel Calibration of condensate flow monitor SR 3.4.15.5RCS Specific Activity 3.4.16 3.4.15Verify gross reactor coolant activity SR 3.4.16.1 SR 3.4.15.1Verify reactor coolant specific activity SR 3.4.16.2 SR 3.4.15.2Determine E SR 3.4.16.3 SR 3.4.15.3STE-RCS Loops, Mode 2 3.4.17 3.4.16Verify thermal power SR 3.4.17.1 SR 3.4.16.1STE-RCS Loops, Modes 4 & 5 3.4.17Verify charging pumps are de-energized SR 3.4.17.2Verify charging flow path is isolated SR 3.4.17.3Perform SR 3.1.1.1 SR 3.4.17.4SITs 3.5.1 3.5.1Verify isolation valves are open SR 3.5.1.1 SR 3.5.1.1Verify borated water volume in SITs SR 3.5.1.2 SR 3.5.1.2Verify nitrogen pressure in SITs SR 3.5.1.3 SR 3.5.1.3Verify boron concentration in SITs SR 3.5.1.4 SR 3.5.1.4Verify power is removed from SIT isolation valves SR 3.5.1.5 SR 3.5.1.5EGCS-Operating 3.5.2 3.5.2Verify specified valve position SR 3.5.2.1 SR 3.5.2.1Verify valves are in the correct position SR 3.5.2.2 SR 3.5.2.2Verify ECCS piping is full of water SR 3.5.2.3Verify valves actuate to correct position SR 3.5.2.6 SR 3.5.2.5Verify ECCS pumps start on signal SR 3.5.2.7 SR 3.5.2.6Verify LPSI pump stops on signal SR 3.5.2.8 SR 3.5.2.7Verify throttle valves stop in correct position SR 3.5.2.9Verify containment sump is not blocked by debris SR 3.5.2.10 SR 3.5.2.8Verify SOC interlock works SR 3.5.2.9RWT 3.5.4 3.5.4Verify water temperature SR 3.5.4.1 SR 3.5.4.1Verify water temperature SR 3.5.4.1 SR 3.5.4.2Verify water volume SR 3.5.4.2 SR 3.5.4.3Verify boron concentration SR 3.5.4.3 SR 3.5.4.4TSP/STB 3.5.5 3.5.5Verify baskets contain TSP/STB SR 3.5.5.1 SR 3.5.5.1Verify pH adjustment of water SR 3.5.5.2 SR 3.5.5.24 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification TitlelSurveillance Description TSTF-425 CCNPPContainment Air Locks 3.6.2 3.6.2Verify only one door open at a time SR 3.6.2.2 SR 3.6.2.2Containment Isolation Valves 3.6.3 3.6.3Verify purge valves are closed SR 3.6.3.1Verify vent valves are closed SR 3.6.3.2 SR 3.6.3.1Verify isolation valves are closed SR 3.6.3.3 SR 3.6.3.2Verify isolation time of valves SR 3.6.3.5Perform leak rate test of purge valves SR 3.6.3.6Verify valves actuate to correct position SR 3.6.3.7 SR 3.6.3.5Verify purge valve is blocked SR 3.6.3.8Containment Pressure 3.6.4 3.6.4Verify pressure is within limits SR 3.6.4.1 SR 3.6.4.1Containment Air Temperature 3.6.5 3.6.5Verify temperature is within limits SR 3.6.5.1 SR 3.6.5.1Containment Spray and Cooling System 3.6,6A 3.6.6Verify containment spray valves are in the correct position SR 3.6.6A.1 SR 3.6.6,1Operate cooling train fan SR 3.6.6A.2 SR 3.6.6.2Verify cooling water flow rate SR 3.6.6A.3 SR 3.6.6.3Verify containment spray pipe is full of water SR 3.6.6A.4-Verify valves actuate to their correct position SR 3.6.6A.6 SR 3.6.6.5Verify containment spray pump starts SR 3.6.6A.7 SR 3.6.6.6Verify cooling train starts SR 3.6.6A.8 SR 3.6.6.7Verify spray nozzle is unobstructed SR 3.6.6A.9-Spray Additive System 3.6.7Shield Building Exhaust Air Cleanup System 3.6.8HMS 3.6.9 ..Iodine Cleanup System/Iodine Removal System 3.6.10 3.6.8Operate each train SR 3.6.10.1 SR 3.6.8.1Verify each train actuates SR 3.6.10.3 SR 3.6.8.3Verify bypass damper can be opened SR 3.6.10.4 ..Shield Building 3.6.11 ..MSlVs 3.7.2 3.7.2MFIVs 3.7.3 3.7.15ADVs 3.7.4 3.7.18Verify complete cycle of ADVs 3.7.4.1 3.7.18.1AFW System 3.7.5 3.7.3Verify valves are in the correct position SR 3.7.5.1 SR 3.7.3.1Verify valves actuate to the correct position SR 3.7.5.3 SR 3.7.3.4Verify the AFW pumps start automatically SR 3.7.5.4 SR 3.7.3.5Verify the AFW system can provide minimum flow SR 3.7.3.6Condensate Storage Tank 3.7.6 3,7.4Verify CST level/volume SR 3.7.6.1 SR 3.7.4.1CCW/CC System 3.7.7 3.7.5Verify valves are in the correct position SR 3.7.7.1 SR 3.7.5.1Verify valves actuate to the correct position SR 3.7.7.2 SR 3.7.5.2Verify pumps start automatically SR 3.7.7.3 SR 3.7.5.35 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPSWS/SRW 3.7.8 3.7.6Verify valves are in the correct position SR 3.7.8.1 SR 3.7.6.1Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.6.2Verify pumps start automatically SR 3.7.8.3 SR 3.7.6.3SWS/SW 3.7.8 3.7.7Verify valves are in the correct position SR 3.7.8.1 SR 3.7.7.1Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.7.2Verify pumps start automatically SR 3.7.8.3 SR 3.7.7.3UHS 3.7.9ECW 3.7.10 ..CREACS/CREVS 3.7.11 3.7.8Operate filter train SR 3.7.11.1 SR 3.7.8.1Verify each train actuates on a signal SR 3.7.11.3 SR 3.7.8.3Verify positive pressure can be maintained SR 3.7.11.4CREATS/CRETS 3.7.12 3.7.9Verify heat load can be removed/temperature can be maintained SR 3.7.12.1 SR 3.7.9.1ECCS PREACS 3.7.13 ....___FBACS/SFPEVS 3.7.14 3.7.11Operate each train SR 3.7.14.1Verify a train is in operation SR 3.7.11.1Verify each train actuates on a signal SR 3.7.14.3Verify a train can maintain a negative pressure SR 3.7.14.4 SR 3.7.11.3Verify the bypass damper can be opened SR 3.7.14.5PREACSIPREVS 3.7.15 3.7.12Operate each train SR 3.7.15.1 SR 3.7.12.1Verify each train actuates on a signal SR 3.7.15.3 SR 3.7.12.3Verify a train can maintain a negative pressure SR 3.7.15.4Verify the bypass damper can be opened SR 3.7.15.5Fuel Storage Pool Water Level/ SFP Water Level 3.7.16 3.7.13Verify water level in pool SR 3.7.16.1 SR 3.7.13.1FSP Boron Concentration/SFP Boron Concentration 3.7.17 3.7.16Verify boron concentration in pool SR 3.7.17.1 SR 3.7.16.1Secondary Specific Activity 3.7.19 3.7.14Verify secondary specific activity is within limits SR 3.7.19.1 SR 3.7.14.1AC Sources-Operating 3.8.1 3.8.1Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.1Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.2Verify DG standby start SR 3.8.1.2 SR 3.8.1.3Verify DG is loaded and operate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SR 3.8.1.3 SR 3.8.1.4Verify day tank volume SR 3.8.1.4 SR 3.8.1.5Check for water in the day tank SR 3.8.1.5 SR 3.8.1.6Verify fuel oil transfer system operates SR 3.8.1.6 SR 3.8.1.7Verify DG standby start (fast start) SR 3.8.1.7 SR 3.8.1.9Verify manual transfer of AC sources SR 3.8.1.8 SR 3.8.1.10Verify single load reject SR 3.8.1.9 SR 3.8.1.12Verify full load reject SR 3.8.1.106 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPVerify DG start and operation on a loss of offsite power SR 3.8.1.11Verify DG start and operation on an ESF signal SR 3.8.1.12Verify non-critical trips are bypassed SR 3.8.1.13 SR 3.8.1.13Verify DG operation at appropriate power factor and for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.8.1.14 SR 3.8.1.11SR 3.8.1.17Verify hot restart of the DG SR 3.8.1.15Verify DG synchronizes to offsite power SR 3.8.1.16 SR 3.8.1.14Verify ESF signal overrides DG test mode SR 3.8.1 .17-Verify load sequencer operation SR 3.8.1.18 SR 3.8.1.8Verify DG start and operation on an ESE/LOOP signal SR 3.8.1.19 SR 3.8.1.15Verify DG operation during simultaneous start SR 3.8.1.20Diesel Fuel Oil, Lube Oil and Starting Air/Diesel Fuel Oil 3.8.3 3.8.3Verify volume of diesel fuel oil SR 3.8.3.1 SR 3.8.3.1Verify lube oil inventory SR 3.8.3.2Verify air start receiver pressure SR 3.8.3.4Remove accumulated water from storage tank SR 3.8.3.5 SR 3.8.3.3DC Sources -Operating 3.8.4 3.8.4Verify battery terminal voltage SR 3.8.4.1 SR 3.8.4.1Verify battery charger provides adequate voltage SR 3.8.4.2 SR 3.8.4.6Verify battery capacity SR 3.8.4.3 SR 3.8.4.7Verify no visible corrosion .... SR 3.8.4.2Verify no physical damage --SR 3.8.4.3Remove visible corrosion SR 3.8.4.4Verify battery connection resistance .... SR 3.8.4.5Battery ParameterslBattery Cell Parameters 3.8.6 3.8.6Verify float current/voltage SR 3.8.6.1 SR 3.8.6.1Verify battery cell voltage SR 3.8.6.2 SR 3.8.6.2Verify electrolyte level SR 3.8.6.3 SR 3.8.6.1Verify battery temperature SR 3.8.6.4 SR 3.8.6.3Verify cell voltage SR 3.8.6.5 SR 3.8.6.2Verify battery capacity -discharge test SR 3.8.6.6 SR 3.8.4.8Inverters-Operating 3.8.7 3.8.7Verify correct voltage SR 3.8.7.1 SR 3.8.7.1Inverters-Shutdown 3.8.8 3.8.8Verify correct voltage SR 3.8.8.1 SR 3.8.8.1Distribution Systems-Operating 3.8.9 3.8,9Verify correct breaker alignments SR 3.8.9.1 SR 3.8.9.1Distribution Systems-Shutdown 3.8.10 3.8.10Verify correct breaker alignments SR 3.8.10.1 SR 3.8.10.1Boron Concentration 3.9.1 3.9.1Verify boron concentration SR 3.9.1.1 SR 3.9.1.1Nuclear Instrumentation 3.9.2 3.9.2Perform Channel Check SR 3.9.2.1 SR 3.9.2.1Perform Channel Calibration SR 3.9.2.2 SR 3.9.2.2Containment Penetrations 3.9.3 3.9.3Verify containment penetrations are in correct status SR 3.9.3.1 SR 3.9.3.1Verify containment purge actuates on a signal SR 3.9.3.2 SR 3.9.3.27 ATTACHMENT (1)COMPARISON MATRIXTechnical Specification Title/Surveillance Description TSTF-425 CCNPPSDC and Coolant Circulation-High Water Level 3.9.4 3.9.4__erify __o__eSDC__loop__is__in__oeratio____SR 3.9.4.1 SR 3.9.4.1SDC and Coolant Circulation-Low Water Level 3.9.5 3.9.5Verfy DC oos ae oeraleSR 3.9.5.1 SR 3.9.5.1Verify correct breaker alignment SR 3.9.5.2 SR 3.9.5.3Verify flow rate of SDC loop SR 3.9.5.2Refueling Water Level/Refueling Pool Water Level 3.9.6 3.9.6Verify water level SR 3.9.6.1 SR 3.9.6.18 ATTACHM ENT (2)MARKED UP TECHNICAL SPECIFICATION AND TECHNICALSPECIFICATION BASES PAGESCalvert Cliffs Nuclear Power PlantJuly 30, 2015Calvert Cliffs Nuclear Power PlantJuly 30, 2015 AC Sources-Operating3.8.1SURVEILLANCE REQUIREMENTS (continued) _________SURVEILLANCE FREQUENCYSR 3.8.1.16 For the LCO 3.8.1.c AC electrical sources, In accordanceSR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.3, with applicableSR 3.8.1.5, SR 3.8.1.6, and SR 3.8.1.7 are Surveillancerequired to be performed. RequirementsSR 3.8.1.17-----------NOTE--- ------Momentary transients outside the load andpower factor limits do not invalidate thistest.Verify each DG operates for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: ~ fl~~a. For 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the test loaded to4200 kW for DG IA, and 3150 kW and3300 kW for DGs lB, 2A, and 2B, andb. For the remaining hours of the testloaded to 3600 kW for DG IA, and2700 kW and 3000 kW for DGs lB, 2A,and 2B.CALVERT CLIFFS -UNIT 1CALVERT CLIFFS -UNIT 23 .8. 1-17Amendment No. 307Amendment No. 285 ADV s3.7.18SURVEILLANCE REQUIREMENTS _________SURVEILLANCE FREQUENCYSR 3.7.18.1 Verify one complete cycle of each ADV.CALVERT CLIFFS -UNIT 1CALVERT CLIFFS -UNIT 23.7.,18-2Amendment No. 311Amendment No. 289 ADVsB 3.7.18BASESC.I and C.2If the ADV lines cannot be restored to OPERABLE statuswithin the associated Completion Time, the unit must beplaced in a MODE in which the LCO does not apply. Toachieve this status, the unit must be placed in at leastMODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4, without reliance uponthe steam generator for heat removal, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Theallowed Completion Times are reasonable, based on operatingexperience, to reach the required unit conditions from fullpower conditions in an orderly manner and withoutchallenging unit systems.SURVEILLANCE SR 3.7.18.1REQUIREMENTSTo perform a cooldown of the RCS, the ADVs must be able tobe opened through their full range. This SR ensures theADVs are tested through a full cycle at least once per fuelcycle. This test is performed using the manual handwheelassembly. Any use of an ADV using the manual handwheelREFERECS1 USAScin0.CALVERT CLIFFS -UNITS 1 & 2 B 3.7.18-3 Revision XXICALVERT CLIFFS -UNITS 1 & 2B 3.7.18-3Revision XX I AC Sources-OperatingB 3.8.1BASESSR 3.8.1.17Reference 13 requires demonstration that the DGs can startand run continuously at full load capability for an intervalof not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of which is at a loadequivalent to 105-110% of the continuous service rating andthe remainder of the time at a load equivalent to 90-100% ofthe continuous service rating. For the Nos. lB, 2A, and 2BDGs the SR reflects these loading ranges. For the No. IADG, since the post accident loading is significantly lessthan the continuous service rating, the post accidentloading (<4000 kW) is used instead of the continuousservice rating. Actual testing is performed at a loadhigher than the post accident loading.The DG starts for this Surveillance can be performed eitherfrom standby or hot conditions. The provisions forprelubricating and warmup, discussed in SR 3.8.1.3 and forgradual loading, discussed in SR 3.8.1.4 are applicable tothis SR.~The load band is provided to avoid routine overloading ofmo('+/-. the 0G. Routine overloading may result in more frequentF:::M lS~r l teardown inspections in accordance with vendorin order to maintain DG OPERABILITY.L (c. In addition, the post-accident load for No. IA DG is__ S significantly lower than the continuous rating of No. 1A DG.ITo ensure No. 1A DG performance is not degraded, routineb j _ of engine parameters should be performed duringThis SR is modified by a Note. Note 1 states that momentarytransients due to changing bus loads do not invalidate thistest. Similarly, momentary power factor transients above thelimit will not invalidate the test.REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteriafor Nuclear Power Plants"CALVERT CLIFFS -UNITS 1 & 2B 3,8.1-32Revision 52