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| issue date = 07/30/2015 | | issue date = 07/30/2015 | ||
| title = Supplemental Information Regarding TSTF-425 License Amendment Request | | title = Supplemental Information Regarding TSTF-425 License Amendment Request | ||
| author name = Gellrich G | | author name = Gellrich G | ||
| author affiliation = Exelon Generation Co, LLC | | author affiliation = Exelon Generation Co, LLC | ||
| addressee name = | | addressee name = | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:~Exet~on Generation George H. Gellrich Site Vice President Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5200 Office 717 497 3463 Mobile w~ww~exeloncoro~com george.gellrich@exeloncorp.com 10 CFR 50.90 July 30, 2015 U. S. Nuclear Regulatory Commission ATTN: Document ControJ Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 | {{#Wiki_filter:~Exet~on Generation George H. Gellrich Site Vice President Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5200 Office 717 497 3463 Mobile w~ww~exeloncoro~com george.gellrich@exeloncorp.com 10 CFR 50.90 July 30, 2015 U. S. Nuclear Regulatory Commission ATTN: Document ControJ Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 | ||
==Subject:== | ==Subject:== | ||
Supplemental Information Regardincq TSTF-425 License Amendment Reqiuest | |||
==References:== | ==References:== | ||
: 1. Letter from G. H. Gellinch (Exelon) to Document Control Desk (NRC), dated May 1, 2014, License Amendment Request: Adoption of Technical Specification Task Force Traveler (TSTF) - 425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative Sb | |||
: 2. Letter from N. S. Morgan (NRC) to G. H. GellInch (Exelon), dated October 21, 2014, Issuance of Amendments Regarding Enhancements to Diesel Generator Surveillance Requirements | |||
: 3. Letter from A. N. Chereskin (NRC) to G. H. Gellinch (Exelon), dated July 23, 2015, Amendment Regarding New Technical Specification 3.7.18 for Atmospheric Dump Valves Reference 1 submitted a license amendment request to adopt TSTF-425. Since the submittal of Reference 1, two license amendments have been issued by the Nuclear Regulatory Commission that each include an additional Surveillance Requirement. Reference 2 added Surveillance Requirement SR 3.8.1.17 which requires diesel generator operation for 24 hours. | |||
Reference 3 added Surveillance Requirement SR 3.7.18.1 which requires cycling of the atmospheric 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, we request their inclusion in this license amendment request. The marked up Technical Specification and Technical Specification Bases pages are included as Attachment (2). These marked up pages conform to TSTF-425, Revision 3. | |||
This additional information does not change the No Significant Hazards Determination provided in Reference 1. No regulatory commitments are contained in this letter. | |||
Aocil | |||
Document Control Desk July 30, 2015 Page 2 Should 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. Gelrinch Site Vice President GHG/PSF/bjm Attachments: (1) Comparison Matrix (2) Marked up Technical Specification and Technical Specification Bases Pages cc: NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert Cliffs NRC Regional Administrator, Region I S. Gray, MD-DNR | |||
(1) Comparison Matrix (2) Marked up Technical Specification and Technical Specification Bases Pages cc: NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert Cliffs NRC Regional Administrator, Region I S. Gray, MD-DNR | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Calvert Cliffs Nuclear Power Plant July 30, 2015 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP ShtdwnMrgn SD)3.1.1 3.1.1 Verify _____SDM___within____limits___SR 3.1.1.1 SR 3.1.1.1 Rea_____ti___ity_____Balan______e__3.1.2 CEA_______Ali___________e____t___3.1.4 3.1.4 Verify indicated position within 7 inches SR 3.1.4.1 SR 3.1 .4.1 Verify motion inhibit is Operable SR 3.1.4.2 SR 3.1.4.2 Verify deviation circuit is Operable SR 3.1.4.3 SR 3.1 .4.3 Verify CEA freedom of movement SR 3.1.4.4 SR 3.1.4.4 Perform Channel Functional Test SR 3.1.4.5 SR 3.1.4.5 Shutdown CEA Insertion Limits 3.1.5 3.1.5 Verify CEA is withdrawn SR 3.1.5.1 SR 3.1.5.1 Regulating CEA Insertion Limits 3.1.6 3.1.6 Verify CEA group position is within limits SR 3.1.6.1 SR 3.1.6.1 Verify CEA insertion times SR 3.1 .6.2 SR 3.1 .6.2 Verify PDIL alarm circuit is Operable SR 3.1.6.3 SR 3.1.6.3 STE-SDM 3.1.7 3.1.7 Verify CEA insertion is within acceptance criteria SR 3.1.7.1 SR 3.1.7.1 STE-Modes 1 and 2 3.1.8 3.1.8 Verify Thermal Power is within test power plateau SR 3.1.8.1 SR 3.1.8.1 LHR 3.2.1 3.2.1 Verify ASI alarm setpoints SR 3.2.1.1 SR 3.2.1.2 Verify incore detector local power density alarms SR 3.2.1.2 SR 3.2.1.3 Verify incore local power density alarm setpoints SR 3.2.1 3 SR 3.2.1.4 Fxy 3.2.2 Fr 3.2.3 3.2.3 Verify value of Fr SR 3.2.3.1 SR 3.2.3.1 Tq 3.2.4 3.2.4 Verify value of Tq SR 3.2.4.1 SR 3.2.4.1 ASI 3.2.5 3.2.5 Verify ASI is within limits SR 3.2.5.1 SR 3.2.5.1 RPS Instrumentation -Operating 3.3.1 3.3.1 Perform Channel Check SR 3.3.1.1 SR 3.3.1.1 Perform calibration of excore and dT power channels SR 3.3.1.2 SR 3.3.1.2 Calibrate power range excores using incore detectors SR 3.3.1.3 SR 3.3.1.3 Perform Channel Functional Test SR 3.3.1.4 SR 3.3.1.4 Perform Channel Calibration on excore power range channels SR 3.3.1.5 SR 3.3.1.5 Perform Channel Functional Test on automatic bypass removal SR 3.3.1 .7 Perform Channel Calibration of each RPS channel SR 3.3.1.8 SR 3.3.1 .8 Verify RPS response times SR 3.3.1.9 SR 3.3.1.9 RPS Instrumentation - Shutdown 3.3.2 3.3.2 Perform Channel Check of wide range power channel SR 3.3.2.1 SR 3.3.2.1 Perform Channel Functional Test of power rate of change trip SR 3.3.2.2 Perform Channel Functional Test of automatic bypass removal SR 3.3.2.3 SR 3.3.2.3 Perform Channel Calibration, including bypass functions SR 3.3.2.4 SR 3.3.2.4 RPS Logic and Tri Initiation 3.3.3 3.3.3 Perform Channel Functional Test on RTCB channel SR 3.3.3.1 SR 3.3.3.1 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Functional Test on RPS logic SR 3.3.3.2 SR 3.3.3.2 Perform Channel Functional Test with undervoltage and shunt trips SR 3.3.3.4 ESFAS Instrumentation 3.3.4 3.3.4 Perform Channel Check on each ESFAS channel SR 3.3.4.1 SR 3.3.4.1 Perform Channel Functional Test on each ESFAS channel SR 3.3.4.2 SR 3.3.4.2 Perform Channel Functional Test on automatic block removal SR 3.3.4.3 Perform Channel Calibration of ESFAS channels, including block SR 3.3.4.4 SR 3.3.4.4 removal Verify ESF response time in limits SR 3.3.4.5 SR 3.3.4.5 ESFAS Logic and Manual Trip/Actuation 3.3.5 3.3.5 Perform Channel Functional Test on ESFAS Logic channel SR 3.3.5.1 SR 3.3.5.1 Perform Channel Functional Test on ESFAS trip/actuation channel SR 3.3.5.2 SR 3.3.5.2 DG-LOVS 3.3.6 3.3.6 Perform Channel Check SR 3.3.6.1 Perform Channel Functional Test SR 3.3.6.2 SR 3.3.6.1 Perform Channel Calibration SR 3.3.6.3 SR 3.3.6.2 CPIS/CRS 3.3.7 3.3.7 Perform Channel Check on radiation monitors SR 3.3.7.1 SR 3.3.7.1 Perform Channel Functional Test on radiation monitor channel SR 3.3.7.2 SR 3.3.7.3 Perform Channel Functional Test on actuation logic channel SR 3.3.7.3 SR 3.3.7.2 Perform Channel Calibration on radiation monitor channel SR 3.3.7.4 SR 3.3.7.4 Perform Channel Functional Test on manual trip/actuation channel SR 3.3.7.5 SR 3.3.7.5 Verify response time is within limits SR 3.3.7.6 SR 3.3.7.6 CRIS/CR RS 3.3.8 3.3.8 Perform Channel Check on radiation monitor channel SR 3.3.8.1 SR 3.3.8.1 Perform Channel Functional Test on the radiation monitor channel SR 3.3.8.2 SR 3.3.8.2 Perform Channel Functional Test on actuation logic channel SR 3.3.8.3 Perform Channel Calibration on the radiation monitor channel SR 3.3.8.4 SR 3.3.8.3 Perform Channel Functional Test on the manual trip channel SR 3.3.8.5 Verify response times are within limits SR 3.3.8.6 CVCS Isolation Signal 3.3.9 3.3.9 Perform Channel Check SR 3.3.9.1 SR 3.3.9.1 Perform Channel Functional Test on CVCS isolation channels SR 3.3.9.2 SR 3.3.9.2 Perform Channel Calibration on CVCS sensor channels SR 3.3.9.3 SR 3.3.9.3 Verify response time is within limits SR 3.3.9.4 Shield Building Filtration Actuation Signal 3.3.10 PAM Instrumentation 3.3.11 3.3,10 Perform Channel Check for normally energized channels SR 3.3.11.1 SR 3.3.10.1 Perform Channel Calibration SR 3.3.11.2 SR 3.3.10.3 Remote Shutdown System/Instrumentation 3.3.12 3.3.11 Perform Channel Check for normally energized channels SR 3.3.12.1 SR 3.3.11.1 Verify control circuit and transfer switch works SR 3.3.12.2 Perform Channel Calibration for each channel SR 3.3.12.3 SR 3.3.11.2 Perform Channel Functional Test SR 3.3.12.4 Power Monitoring Channels/Wide Range Logarithmic Neutron 3.3.13 3.3.12 Flux Monitor Channels Perform Channel Check SR 3.3.13.1 SR 3.3.12.1 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Functional Test SR 3.3.13.2 Perform Channel Calibration SR 3.3.13.3 SR 3.3.12.3 RCS Pressure, Temperature and Flow DNBR Limits 3.4.1 3.4.1 Verify pressurizer pressure is within limits SR 3.4.1.1 SR 3.4.1.1 Verify cold leg ternperatures are within limits SR 3.4.1.2 SR 3.4.1.2 Verify RCS total flow SR 3.4.1.3 SR 3.4.1.3 Verify heat balance/measured RCS flow is within limits SR 3.4.1.4 SR 3.4.1.4 RCS Minimum Temperature for Criticality 3.4.2 RCS P/T Limits 3.4.3 3.4.3 Verify RCS temperature, pressure, rates are within limits SR 3.4.3.1 SR 3.4.3.1 RCS Loops - Modes 1 and 2 3.4.4 3.4.4 Verify RCS loops in operation SR 3.4.4.1 SR 3.4.4.1 RCS Loops - Mode 3 3.4.5 3.4.5 Verify RCS loop is in operation SR 3.4.5.1 SR 3.4.5.1 Verify secondary side SG water level SR 3.4.5.2 SR 3.4.5.2 Verify correct breaker alignment SR 3.4.5.3 SR 3.4.5.3 RCS Loops - Mode 4 3.4.6 3.4.6 Verify one RCS/SDC in operation SR 3.4.6.1 SR 3.4.6.1 Verify secondary side SG water level SR 3.4.6.2 SR 3.4.6.2 Verify correct breaker alignment SR 3.4.6.3 SR 3.4.6.3 RCS Loops - Mode 5, Loops Filled 3.4.7 3.4.7 Verify SDC train is in operation SR 3.4.7.1 SR 3.4.7.1 Verify secondary side SG water level SR 3.4.7.2 SR 3.4.7.2 Verify correct breaker alignment SR 3.4.7.3 SR 3.4.7.3 RCS Loops - Mode 5, Loops not Filled 3.4.8 3.4.8 Verify SDC train is in operation SR 3.4.8.1 SR 3.4.8.1 Verify correct breaker alignment SR 3.4.8.2 SR 3.4.8.2 Pressurizer 3.4.9 3.4.9 Verify pressurizer water level SR 3.4.9.1 SR 3.4.9.1 Verify capacity of heaters SR 3.4.9.2 SR 3.4.9.2 Verify heaters are powered from emergency power SR 3.4.9.3 Pressurizer PORVs 3.4.11 3.4.11 Perform Channel Functional Test of PORVs SR 3.4.11.1 Perform cycle of block valves SR 3.4.11.1 SR 3.4.11.2 Perform cycle of PORVs SR 3.4.11.2 SR 3.4.11.3 Perform Channel Calibration of PORVs SR 3.4.11.4 Perform cycle of control valve and check valve on PORV SR 3.4.11.3 Verify PORVs and block valves are powered from emergency power SR 3.4.11.4 LTOP System 3.4.12 3.4.12 Verify one HPSI capable of RCS injection SR 3.4.12.1 SR 3.4.12.1 Verify one charging pump capable of RCS injection SR 3.4.12.2 Verify SITs are isolated SR 3.4.12.3 Verify HPSI MOVs are capable of manual alignment SR 3.4.12.2 Verify RCS vent is open SR 3.4.12.4 SR 3.4.12.3 Verify PORV block valve is open SR 3.4.12.5 SR 3.4.12.4 Perform Channel Functional Test for PORVs SR 3.4.12.6 SR 3.4.12.5 3 | |||
ATTACHMENT (1) | |||
of engine parameters should be performed during This SR is modified by a Note. Note 1 states that momentary transients due to changing bus loads do not invalidate this test. Similarly, momentary power factor transients above the limit will not invalidate the test.REFERENCES | COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Calibration on PORVs SR 3.4.12.7 SR 3.4.12.6 RCS Operational Leakage 3.4.13 3.4.13 Verify leakage is within limits SR 3.4.13.1 SR 3.4.13.1 Verify primary to secondary leakage is within limits SR 3.4.13.2 SR 3.4.13.2 RCS PIV Leakage 3.4.14 RCS Leakage Detection Instrumentation 3.4.15 3.4.14 Perform Channel Check of radiation monitor SR 3.4.15.1 SR 3.4.14.1 Perform Channel Functional Test of radiation monitor SR 3.4.15.2 SR 3.4.14.2 Perform Channel Calibration of sump monitor SR 3.4.15.3 SR 3.4.14.3 Perform Channel Calibration of radiation monitor SR 3.4.15.4 SR 3.4.14.4 Perform Channel Calibration of condensate flow monitor SR 3.4.15.5 RCS Specific Activity 3.4.16 3.4.15 Verify gross reactor coolant activity SR 3.4.16.1 SR 3.4.15.1 Verify reactor coolant specific activity SR 3.4.16.2 SR 3.4.15.2 Determine E SR 3.4.16.3 SR 3.4.15.3 STE-RCS Loops, Mode 2 3.4.17 3.4.16 Verify thermal power SR 3.4.17.1 SR 3.4.16.1 STE-RCS Loops, Modes 4 & 5 3.4.17 Verify charging pumps are de-energized SR 3.4.17.2 Verify charging flow path is isolated SR 3.4.17.3 Perform SR 3.1.1.1 SR 3.4.17.4 SITs 3.5.1 3.5.1 Verify isolation valves are open SR 3.5.1.1 SR 3.5.1.1 Verify borated water volume in SITs SR 3.5.1.2 SR 3.5.1.2 Verify nitrogen pressure in SITs SR 3.5.1.3 SR 3.5.1.3 Verify boron concentration in SITs SR 3.5.1.4 SR 3.5.1.4 Verify power is removed from SIT isolation valves SR 3.5.1.5 SR 3.5.1.5 EGCS-Operating 3.5.2 3.5.2 Verify specified valve position SR 3.5.2.1 SR 3.5.2.1 Verify valves are in the correct position SR 3.5.2.2 SR 3.5.2.2 Verify ECCS piping is full of water SR 3.5.2.3 Verify valves actuate to correct position SR 3.5.2.6 SR 3.5.2.5 Verify ECCS pumps start on signal SR 3.5.2.7 SR 3.5.2.6 Verify LPSI pump stops on signal SR 3.5.2.8 SR 3.5.2.7 Verify throttle valves stop in correct position SR 3.5.2.9 Verify containment sump is not blocked by debris SR 3.5.2.10 SR 3.5.2.8 Verify SOC interlock works SR 3.5.2.9 RWT 3.5.4 3.5.4 Verify water temperature SR 3.5.4.1 SR 3.5.4.1 Verify water temperature SR 3.5.4.1 SR 3.5.4.2 Verify water volume SR 3.5.4.2 SR 3.5.4.3 Verify boron concentration SR 3.5.4.3 SR 3.5.4.4 TSP/STB 3.5.5 3.5.5 Verify baskets contain TSP/STB SR 3.5.5.1 SR 3.5.5.1 Verify pH adjustment of water SR 3.5.5.2 SR 3.5.5.2 4 | ||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification TitlelSurveillance Description TSTF-425 CCNPP Containment Air Locks 3.6.2 3.6.2 Verify only one door open at a time SR 3.6.2.2 SR 3.6.2.2 Containment Isolation Valves 3.6.3 3.6.3 Verify purge valves are closed SR 3.6.3.1 Verify vent valves are closed SR 3.6.3.2 SR 3.6.3.1 Verify isolation valves are closed SR 3.6.3.3 SR 3.6.3.2 Verify isolation time of valves SR 3.6.3.5 Perform leak rate test of purge valves SR 3.6.3.6 Verify valves actuate to correct position SR 3.6.3.7 SR 3.6.3.5 Verify purge valve is blocked SR 3.6.3.8 Containment Pressure 3.6.4 3.6.4 Verify pressure is within limits SR 3.6.4.1 SR 3.6.4.1 Containment Air Temperature 3.6.5 3.6.5 Verify temperature is within limits SR 3.6.5.1 SR 3.6.5.1 Containment Spray and Cooling System 3.6,6A 3.6.6 Verify containment spray valves are in the correct position SR 3.6.6A.1 SR 3.6.6,1 Operate cooling train fan SR 3.6.6A.2 SR 3.6.6.2 Verify cooling water flow rate SR 3.6.6A.3 SR 3.6.6.3 Verify 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 3.6.6.5 Verify containment spray pump starts SR 3.6.6A.7 SR 3.6.6.6 Verify cooling train starts SR 3.6.6A.8 SR 3.6.6.7 Verify spray nozzle is unobstructed SR 3.6.6A.9-Spray Additive System 3.6.7 Shield Building Exhaust Air Cleanup System 3.6.8 HMS 3.6.9 .. | |||
Iodine Cleanup System/Iodine Removal System 3.6.10 3.6.8 Operate each train SR 3.6.10.1 SR 3.6.8.1 Verify each train actuates SR 3.6.10.3 SR 3.6.8.3 Verify bypass damper can be opened SR 3.6.10.4 .. | |||
Shield Building 3.6.11 .. | |||
MSlVs 3.7.2 3.7.2 MFIVs 3.7.3 3.7.15 ADVs 3.7.4 3.7.18 Verify complete cycle of ADVs 3.7.4.1 3.7.18.1 AFW System 3.7.5 3.7.3 Verify valves are in the correct position SR 3.7.5.1 SR 3.7.3.1 Verify valves actuate to the correct position SR 3.7.5.3 SR 3.7.3.4 Verify the AFW pumps start automatically SR 3.7.5.4 SR 3.7.3.5 Verify the AFW system can provide minimum flow SR 3.7.3.6 Condensate Storage Tank 3.7.6 3,7.4 Verify CST level/volume SR 3.7.6.1 SR 3.7.4.1 CCW/CC System 3.7.7 3.7.5 Verify valves are in the correct position SR 3.7.7.1 SR 3.7.5.1 Verify valves actuate to the correct position SR 3.7.7.2 SR 3.7.5.2 Verify pumps start automatically SR 3.7.7.3 SR 3.7.5.3 5 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP SWS/SRW 3.7.8 3.7.6 Verify valves are in the correct position SR 3.7.8.1 SR 3.7.6.1 Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.6.2 Verify pumps start automatically SR 3.7.8.3 SR 3.7.6.3 SWS/SW 3.7.8 3.7.7 Verify valves are in the correct position SR 3.7.8.1 SR 3.7.7.1 Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.7.2 Verify pumps start automatically SR 3.7.8.3 SR 3.7.7.3 UHS 3.7.9 ECW 3.7.10 .. | |||
CREACS/CREVS 3.7.11 3.7.8 Operate filter train SR 3.7.11.1 SR 3.7.8.1 Verify each train actuates on a signal SR 3.7.11.3 SR 3.7.8.3 Verify positive pressure can be maintained SR 3.7.11.4 CREATS/CRETS 3.7.12 3.7.9 Verify heat load can be removed/temperature can be maintained SR 3.7.12.1 SR 3.7.9.1 ECCS PREACS 3.7.13 .... ___ | |||
FBACS/SFPEVS 3.7.14 3.7.11 Operate each train SR 3.7.14.1 Verify a train is in operation SR 3.7.11.1 Verify each train actuates on a signal SR 3.7.14.3 Verify a train can maintain a negative pressure SR 3.7.14.4 SR 3.7.11.3 Verify the bypass damper can be opened SR 3.7.14.5 PREACSIPREVS 3.7.15 3.7.12 Operate each train SR 3.7.15.1 SR 3.7.12.1 Verify each train actuates on a signal SR 3.7.15.3 SR 3.7.12.3 Verify a train can maintain a negative pressure SR 3.7.15.4 Verify the bypass damper can be opened SR 3.7.15.5 Fuel Storage Pool Water Level/ SFP Water Level 3.7.16 3.7.13 Verify water level in pool SR 3.7.16.1 SR 3.7.13.1 FSP Boron Concentration/SFP Boron Concentration 3.7.17 3.7.16 Verify boron concentration in pool SR 3.7.17.1 SR 3.7.16.1 Secondary Specific Activity 3.7.19 3.7.14 Verify secondary specific activity is within limits SR 3.7.19.1 SR 3.7.14.1 AC Sources-Operating 3.8.1 3.8.1 Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.1 Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.2 Verify DG standby start SR 3.8.1.2 SR 3.8.1.3 Verify DG is loaded and operate for 1 hour SR 3.8.1.3 SR 3.8.1.4 Verify day tank volume SR 3.8.1.4 SR 3.8.1.5 Check for water in the day tank SR 3.8.1.5 SR 3.8.1.6 Verify fuel oil transfer system operates SR 3.8.1.6 SR 3.8.1.7 Verify DG standby start (fast start) SR 3.8.1.7 SR 3.8.1.9 Verify manual transfer of AC sources SR 3.8.1.8 SR 3.8.1.10 Verify single load reject SR 3.8.1.9 SR 3.8.1.12 Verify full load reject SR 3.8.1.10 6 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Verify DG start and operation on a loss of offsite power SR 3.8.1.11 Verify DG start and operation on an ESF signal SR 3.8.1.12 Verify non-critical trips are bypassed SR 3.8.1.13 SR 3.8.1.13 Verify DG operation at appropriate power factor and for 24 hours SR 3.8.1.14 SR 3.8.1.11 SR 3.8.1.17 Verify hot restart of the DG SR 3.8.1.15 Verify DG synchronizes to offsite power SR 3.8.1.16 SR 3.8.1.14 Verify ESF signal overrides DG test mode SR 3.8.1 .17-Verify load sequencer operation SR 3.8.1.18 SR 3.8.1.8 Verify DG start and operation on an ESE/LOOP signal SR 3.8.1.19 SR 3.8.1.15 Verify DG operation during simultaneous start SR 3.8.1.20 Diesel Fuel Oil, Lube Oil and Starting Air/Diesel Fuel Oil 3.8.3 3.8.3 Verify volume of diesel fuel oil SR 3.8.3.1 SR 3.8.3.1 Verify lube oil inventory SR 3.8.3.2 Verify air start receiver pressure SR 3.8.3.4 Remove accumulated water from storage tank SR 3.8.3.5 SR 3.8.3.3 DC Sources - Operating 3.8.4 3.8.4 Verify battery terminal voltage SR 3.8.4.1 SR 3.8.4.1 Verify battery charger provides adequate voltage SR 3.8.4.2 SR 3.8.4.6 Verify battery capacity SR 3.8.4.3 SR 3.8.4.7 Verify no visible corrosion .... SR 3.8.4.2 Verify no physical damage -- SR 3.8.4.3 Remove visible corrosion SR 3.8.4.4 Verify battery connection resistance .... SR 3.8.4.5 Battery ParameterslBattery Cell Parameters 3.8.6 3.8.6 Verify float current/voltage SR 3.8.6.1 SR 3.8.6.1 Verify battery cell voltage SR 3.8.6.2 SR 3.8.6.2 Verify electrolyte level SR 3.8.6.3 SR 3.8.6.1 Verify battery temperature SR 3.8.6.4 SR 3.8.6.3 Verify cell voltage SR 3.8.6.5 SR 3.8.6.2 Verify battery capacity - discharge test SR 3.8.6.6 SR 3.8.4.8 Inverters-Operating 3.8.7 3.8.7 Verify correct voltage SR 3.8.7.1 SR 3.8.7.1 Inverters-Shutdown 3.8.8 3.8.8 Verify correct voltage SR 3.8.8.1 SR 3.8.8.1 Distribution Systems-Operating 3.8.9 3.8,9 Verify correct breaker alignments SR 3.8.9.1 SR 3.8.9.1 Distribution Systems-Shutdown 3.8.10 3.8.10 Verify correct breaker alignments SR 3.8.10.1 SR 3.8.10.1 Boron Concentration 3.9.1 3.9.1 Verify boron concentration SR 3.9.1.1 SR 3.9.1.1 Nuclear Instrumentation 3.9.2 3.9.2 Perform Channel Check SR 3.9.2.1 SR 3.9.2.1 Perform Channel Calibration SR 3.9.2.2 SR 3.9.2.2 Containment Penetrations 3.9.3 3.9.3 Verify containment penetrations are in correct status SR 3.9.3.1 SR 3.9.3.1 Verify containment purge actuates on a signal SR 3.9.3.2 SR 3.9.3.2 7 | |||
ATTACHMENT (1) | |||
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP SDC 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 3.9.4.1 SDC and Coolant Circulation-Low Water Level 3.9.5 3.9.5 Verfy ae oeraleSR DC oos 3.9.5.1 SR 3.9.5.1 Verify correct breaker alignment SR 3.9.5.2 SR 3.9.5.3 Verify flow rate of SDC loop SR 3.9.5.2 Refueling Water Level/Refueling Pool Water Level 3.9.6 3.9.6 Verify water level SR 3.9.6.1 SR 3.9.6.1 8 | |||
ATTACHM ENT (2) | |||
MARKED UP TECHNICAL SPECIFICATION AND TECHNICAL SPECIFICATION BASES PAGES Calvert Cliffs Nuclear Power Plant July 30, 2015 30, 2015Power Plant JulyNuclear Calvert Cliffs | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) _________ | |||
SURVEILLANCE FREQUENCY SR 3.8.1.16 For the LCO 3.8.1.c AC electrical sources, In accordance SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.3, with applicable SR 3.8.1.5, SR 3.8.1.6, and SR 3.8.1.7 are Surveillance required to be performed. Requirements SR 3.8.1.17-----------NOTE--- ------ | |||
Momentary transients outside the load and power factor limits do not invalidate this test. | |||
Verify each DG operates for Ž 24 hours: ~ fl~~ | |||
: a. For Ž 2 hours of the test loaded to | |||
Ž4200 kW for DG IA, and Ž 3150 kW and | |||
*3300 kW for DGs lB, 2A, and 2B, and | |||
: b. For the remaining hours of the test loaded to Ž 3600 kW for DG IA, and | |||
Ž2700 kW and | |||
* 3000 kW for DGs lB, 2A, and 2B. | |||
CALVERT CLIFFS - UNIT 1 3 .8. 1-17 Amendment No. 307 CALVERT CLIFFS - UNIT 2 Amendment No. 285 | |||
ADV s 3.7.18 SURVEILLANCE REQUIREMENTS _________ | |||
SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify one complete cycle of each ADV. | |||
CALVERT CLIFFS - UNIT 1 3.7.,18-2 Amendment No. 311 CALVERT CLIFFS - UNIT 2 Amendment No. 289 | |||
ADVs B 3.7.18 BASES C.I and C.2 If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 4, without reliance upon the steam generator for heat removal, within 24 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. | |||
SURVEILLANCE SR 3.7.18.1 REQUIREMENTS To perform a cooldown of the RCS, the ADVs must be able to be opened through their full range. This SR ensures the ADVs are tested through a full cycle at least once per fuel cycle. This test is performed using the manual handwheel assembly. Any use of an ADV using the manual handwheel REFERECS1 USAScin0. | |||
Revision XX I CALVERT CLIFFS - UNITS | |||
- & 22 UNITS 11 & B 3.7.18-3 B 3.7.18-3 Revision XX I | |||
AC Sources-Operating B 3.8.1 BASES SR 3.8.1.17 Reference 13 requires demonstration that the DGs can start and run continuously at full load capability for an interval of not less than 24 hours, Ž 2 hours of which is at a load equivalent to 105-110% of the continuous service rating and the remainder of the time at a load equivalent to 90-100% of the continuous service rating. For the Nos. lB, 2A, and 2B DGs the SR reflects these loading ranges. For the No. IA DG, since the post accident loading is significantly less than the continuous service rating, the post accident loading (<4000 kW) is used instead of the continuous service rating. Actual testing is performed at a load higher than the post accident loading. | |||
The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelubricating and warmup, discussed in SR 3.8.1.3 and for gradual loading, discussed in SR 3.8.1.4 are applicable to this SR. | |||
~The load band is provided to avoid routine overloading of 1hE* *UrqeA mo('+/-. the 0G. Routine overloading may result in more frequent F:::M | |||
* J-1*L. llS~r teardown inspections in accordance with vendor | |||
@"*~c)*'*L*,::**A**Irecommendations in order to maintain DG OPERABILITY. | |||
+k* S*cv L (c. In addition, the post-accident load for No. IA DG is | |||
__ eV*L S A(.* significantly lower than the continuous rating of No. 1A DG. | |||
*,_* e.L.* ITo ensure No. 1A DG performance is not degraded, routine bj | |||
* _ *monitoring of engine parameters should be performed during This SR is modified by a Note. Note 1 states that momentary transients due to changing bus loads do not invalidate this test. Similarly, momentary power factor transients above the limit will not invalidate the test. | |||
REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants" CALVERT CLIFFS - UNITS 1 & 2 B 3,8.1-32 Revision 52}} | |||
Latest revision as of 09:34, 31 October 2019
| ML15212A902 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/30/2015 |
| From: | George Gellrich Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TSTF-425 | |
| Download: ML15212A902 (16) | |
Text
~Exet~on Generation George H. Gellrich Site Vice President Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5200 Office 717 497 3463 Mobile w~ww~exeloncoro~com george.gellrich@exeloncorp.com 10 CFR 50.90 July 30, 2015 U. S. Nuclear Regulatory Commission ATTN: Document ControJ Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318
Subject:
Supplemental Information Regardincq TSTF-425 License Amendment Reqiuest
References:
- 1. Letter from G. H. Gellinch (Exelon) to Document Control Desk (NRC), dated May 1, 2014, License Amendment Request: Adoption of Technical Specification Task Force Traveler (TSTF) - 425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative Sb
- 2. Letter from N. S. Morgan (NRC) to G. H. GellInch (Exelon), dated October 21, 2014, Issuance of Amendments Regarding Enhancements to Diesel Generator Surveillance Requirements
- 3. Letter from A. N. Chereskin (NRC) to G. H. Gellinch (Exelon), dated July 23, 2015, Amendment Regarding New Technical Specification 3.7.18 for Atmospheric Dump Valves Reference 1 submitted a license amendment request to adopt TSTF-425. Since the submittal of Reference 1, two license amendments have been issued by the Nuclear Regulatory Commission that each include an additional Surveillance Requirement. Reference 2 added Surveillance 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 the atmospheric 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, we request their inclusion in this license amendment request. The marked up Technical Specification and Technical Specification Bases pages are included as Attachment (2). These marked up pages conform to TSTF-425, Revision 3.
This additional information does not change the No Significant Hazards Determination provided in Reference 1. No regulatory commitments are contained in this letter.
Aocil
Document Control Desk July 30, 2015 Page 2 Should 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. Gelrinch Site Vice President GHG/PSF/bjm Attachments: (1) Comparison Matrix (2) Marked up Technical Specification and Technical Specification Bases Pages cc: NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert Cliffs NRC Regional Administrator, Region I S. Gray, MD-DNR
ATTACHMENT (1)
COMPARISON MATRIX Calvert Cliffs Nuclear Power Plant July 30, 2015
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP ShtdwnMrgn SD)3.1.1 3.1.1 Verify _____SDM___within____limits___SR 3.1.1.1 SR 3.1.1.1 Rea_____ti___ity_____Balan______e__3.1.2 CEA_______Ali___________e____t___3.1.4 3.1.4 Verify indicated position within 7 inches SR 3.1.4.1 SR 3.1 .4.1 Verify motion inhibit is Operable SR 3.1.4.2 SR 3.1.4.2 Verify deviation circuit is Operable SR 3.1.4.3 SR 3.1 .4.3 Verify CEA freedom of movement SR 3.1.4.4 SR 3.1.4.4 Perform Channel Functional Test SR 3.1.4.5 SR 3.1.4.5 Shutdown CEA Insertion Limits 3.1.5 3.1.5 Verify CEA is withdrawn SR 3.1.5.1 SR 3.1.5.1 Regulating CEA Insertion Limits 3.1.6 3.1.6 Verify CEA group position is within limits SR 3.1.6.1 SR 3.1.6.1 Verify CEA insertion times SR 3.1 .6.2 SR 3.1 .6.2 Verify PDIL alarm circuit is Operable SR 3.1.6.3 SR 3.1.6.3 STE-SDM 3.1.7 3.1.7 Verify CEA insertion is within acceptance criteria SR 3.1.7.1 SR 3.1.7.1 STE-Modes 1 and 2 3.1.8 3.1.8 Verify Thermal Power is within test power plateau SR 3.1.8.1 SR 3.1.8.1 LHR 3.2.1 3.2.1 Verify ASI alarm setpoints SR 3.2.1.1 SR 3.2.1.2 Verify incore detector local power density alarms SR 3.2.1.2 SR 3.2.1.3 Verify incore local power density alarm setpoints SR 3.2.1 3 SR 3.2.1.4 Fxy 3.2.2 Fr 3.2.3 3.2.3 Verify value of Fr SR 3.2.3.1 SR 3.2.3.1 Tq 3.2.4 3.2.4 Verify value of Tq SR 3.2.4.1 SR 3.2.4.1 ASI 3.2.5 3.2.5 Verify ASI is within limits SR 3.2.5.1 SR 3.2.5.1 RPS Instrumentation -Operating 3.3.1 3.3.1 Perform Channel Check SR 3.3.1.1 SR 3.3.1.1 Perform calibration of excore and dT power channels SR 3.3.1.2 SR 3.3.1.2 Calibrate power range excores using incore detectors SR 3.3.1.3 SR 3.3.1.3 Perform Channel Functional Test SR 3.3.1.4 SR 3.3.1.4 Perform Channel Calibration on excore power range channels SR 3.3.1.5 SR 3.3.1.5 Perform Channel Functional Test on automatic bypass removal SR 3.3.1 .7 Perform Channel Calibration of each RPS channel SR 3.3.1.8 SR 3.3.1 .8 Verify RPS response times SR 3.3.1.9 SR 3.3.1.9 RPS Instrumentation - Shutdown 3.3.2 3.3.2 Perform Channel Check of wide range power channel SR 3.3.2.1 SR 3.3.2.1 Perform Channel Functional Test of power rate of change trip SR 3.3.2.2 Perform Channel Functional Test of automatic bypass removal SR 3.3.2.3 SR 3.3.2.3 Perform Channel Calibration, including bypass functions SR 3.3.2.4 SR 3.3.2.4 RPS Logic and Tri Initiation 3.3.3 3.3.3 Perform Channel Functional Test on RTCB channel SR 3.3.3.1 SR 3.3.3.1
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Functional Test on RPS logic SR 3.3.3.2 SR 3.3.3.2 Perform Channel Functional Test with undervoltage and shunt trips SR 3.3.3.4 ESFAS Instrumentation 3.3.4 3.3.4 Perform Channel Check on each ESFAS channel SR 3.3.4.1 SR 3.3.4.1 Perform Channel Functional Test on each ESFAS channel SR 3.3.4.2 SR 3.3.4.2 Perform Channel Functional Test on automatic block removal SR 3.3.4.3 Perform Channel Calibration of ESFAS channels, including block SR 3.3.4.4 SR 3.3.4.4 removal Verify ESF response time in limits SR 3.3.4.5 SR 3.3.4.5 ESFAS Logic and Manual Trip/Actuation 3.3.5 3.3.5 Perform Channel Functional Test on ESFAS Logic channel SR 3.3.5.1 SR 3.3.5.1 Perform Channel Functional Test on ESFAS trip/actuation channel SR 3.3.5.2 SR 3.3.5.2 DG-LOVS 3.3.6 3.3.6 Perform Channel Check SR 3.3.6.1 Perform Channel Functional Test SR 3.3.6.2 SR 3.3.6.1 Perform Channel Calibration SR 3.3.6.3 SR 3.3.6.2 CPIS/CRS 3.3.7 3.3.7 Perform Channel Check on radiation monitors SR 3.3.7.1 SR 3.3.7.1 Perform Channel Functional Test on radiation monitor channel SR 3.3.7.2 SR 3.3.7.3 Perform Channel Functional Test on actuation logic channel SR 3.3.7.3 SR 3.3.7.2 Perform Channel Calibration on radiation monitor channel SR 3.3.7.4 SR 3.3.7.4 Perform Channel Functional Test on manual trip/actuation channel SR 3.3.7.5 SR 3.3.7.5 Verify response time is within limits SR 3.3.7.6 SR 3.3.7.6 CRIS/CR RS 3.3.8 3.3.8 Perform Channel Check on radiation monitor channel SR 3.3.8.1 SR 3.3.8.1 Perform Channel Functional Test on the radiation monitor channel SR 3.3.8.2 SR 3.3.8.2 Perform Channel Functional Test on actuation logic channel SR 3.3.8.3 Perform Channel Calibration on the radiation monitor channel SR 3.3.8.4 SR 3.3.8.3 Perform Channel Functional Test on the manual trip channel SR 3.3.8.5 Verify response times are within limits SR 3.3.8.6 CVCS Isolation Signal 3.3.9 3.3.9 Perform Channel Check SR 3.3.9.1 SR 3.3.9.1 Perform Channel Functional Test on CVCS isolation channels SR 3.3.9.2 SR 3.3.9.2 Perform Channel Calibration on CVCS sensor channels SR 3.3.9.3 SR 3.3.9.3 Verify response time is within limits SR 3.3.9.4 Shield Building Filtration Actuation Signal 3.3.10 PAM Instrumentation 3.3.11 3.3,10 Perform Channel Check for normally energized channels SR 3.3.11.1 SR 3.3.10.1 Perform Channel Calibration SR 3.3.11.2 SR 3.3.10.3 Remote Shutdown System/Instrumentation 3.3.12 3.3.11 Perform Channel Check for normally energized channels SR 3.3.12.1 SR 3.3.11.1 Verify control circuit and transfer switch works SR 3.3.12.2 Perform Channel Calibration for each channel SR 3.3.12.3 SR 3.3.11.2 Perform Channel Functional Test SR 3.3.12.4 Power Monitoring Channels/Wide Range Logarithmic Neutron 3.3.13 3.3.12 Flux Monitor Channels Perform Channel Check SR 3.3.13.1 SR 3.3.12.1
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Functional Test SR 3.3.13.2 Perform Channel Calibration SR 3.3.13.3 SR 3.3.12.3 RCS Pressure, Temperature and Flow DNBR Limits 3.4.1 3.4.1 Verify pressurizer pressure is within limits SR 3.4.1.1 SR 3.4.1.1 Verify cold leg ternperatures are within limits SR 3.4.1.2 SR 3.4.1.2 Verify RCS total flow SR 3.4.1.3 SR 3.4.1.3 Verify heat balance/measured RCS flow is within limits SR 3.4.1.4 SR 3.4.1.4 RCS Minimum Temperature for Criticality 3.4.2 RCS P/T Limits 3.4.3 3.4.3 Verify RCS temperature, pressure, rates are within limits SR 3.4.3.1 SR 3.4.3.1 RCS Loops - Modes 1 and 2 3.4.4 3.4.4 Verify RCS loops in operation SR 3.4.4.1 SR 3.4.4.1 RCS Loops - Mode 3 3.4.5 3.4.5 Verify RCS loop is in operation SR 3.4.5.1 SR 3.4.5.1 Verify secondary side SG water level SR 3.4.5.2 SR 3.4.5.2 Verify correct breaker alignment SR 3.4.5.3 SR 3.4.5.3 RCS Loops - Mode 4 3.4.6 3.4.6 Verify one RCS/SDC in operation SR 3.4.6.1 SR 3.4.6.1 Verify secondary side SG water level SR 3.4.6.2 SR 3.4.6.2 Verify correct breaker alignment SR 3.4.6.3 SR 3.4.6.3 RCS Loops - Mode 5, Loops Filled 3.4.7 3.4.7 Verify SDC train is in operation SR 3.4.7.1 SR 3.4.7.1 Verify secondary side SG water level SR 3.4.7.2 SR 3.4.7.2 Verify correct breaker alignment SR 3.4.7.3 SR 3.4.7.3 RCS Loops - Mode 5, Loops not Filled 3.4.8 3.4.8 Verify SDC train is in operation SR 3.4.8.1 SR 3.4.8.1 Verify correct breaker alignment SR 3.4.8.2 SR 3.4.8.2 Pressurizer 3.4.9 3.4.9 Verify pressurizer water level SR 3.4.9.1 SR 3.4.9.1 Verify capacity of heaters SR 3.4.9.2 SR 3.4.9.2 Verify heaters are powered from emergency power SR 3.4.9.3 Pressurizer PORVs 3.4.11 3.4.11 Perform Channel Functional Test of PORVs SR 3.4.11.1 Perform cycle of block valves SR 3.4.11.1 SR 3.4.11.2 Perform cycle of PORVs SR 3.4.11.2 SR 3.4.11.3 Perform Channel Calibration of PORVs SR 3.4.11.4 Perform cycle of control valve and check valve on PORV SR 3.4.11.3 Verify PORVs and block valves are powered from emergency power SR 3.4.11.4 LTOP System 3.4.12 3.4.12 Verify one HPSI capable of RCS injection SR 3.4.12.1 SR 3.4.12.1 Verify one charging pump capable of RCS injection SR 3.4.12.2 Verify SITs are isolated SR 3.4.12.3 Verify HPSI MOVs are capable of manual alignment SR 3.4.12.2 Verify RCS vent is open SR 3.4.12.4 SR 3.4.12.3 Verify PORV block valve is open SR 3.4.12.5 SR 3.4.12.4 Perform Channel Functional Test for PORVs SR 3.4.12.6 SR 3.4.12.5 3
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Perform Channel Calibration on PORVs SR 3.4.12.7 SR 3.4.12.6 RCS Operational Leakage 3.4.13 3.4.13 Verify leakage is within limits SR 3.4.13.1 SR 3.4.13.1 Verify primary to secondary leakage is within limits SR 3.4.13.2 SR 3.4.13.2 RCS PIV Leakage 3.4.14 RCS Leakage Detection Instrumentation 3.4.15 3.4.14 Perform Channel Check of radiation monitor SR 3.4.15.1 SR 3.4.14.1 Perform Channel Functional Test of radiation monitor SR 3.4.15.2 SR 3.4.14.2 Perform Channel Calibration of sump monitor SR 3.4.15.3 SR 3.4.14.3 Perform Channel Calibration of radiation monitor SR 3.4.15.4 SR 3.4.14.4 Perform Channel Calibration of condensate flow monitor SR 3.4.15.5 RCS Specific Activity 3.4.16 3.4.15 Verify gross reactor coolant activity SR 3.4.16.1 SR 3.4.15.1 Verify reactor coolant specific activity SR 3.4.16.2 SR 3.4.15.2 Determine E SR 3.4.16.3 SR 3.4.15.3 STE-RCS Loops, Mode 2 3.4.17 3.4.16 Verify thermal power SR 3.4.17.1 SR 3.4.16.1 STE-RCS Loops, Modes 4 & 5 3.4.17 Verify charging pumps are de-energized SR 3.4.17.2 Verify charging flow path is isolated SR 3.4.17.3 Perform SR 3.1.1.1 SR 3.4.17.4 SITs 3.5.1 3.5.1 Verify isolation valves are open SR 3.5.1.1 SR 3.5.1.1 Verify borated water volume in SITs SR 3.5.1.2 SR 3.5.1.2 Verify nitrogen pressure in SITs SR 3.5.1.3 SR 3.5.1.3 Verify boron concentration in SITs SR 3.5.1.4 SR 3.5.1.4 Verify power is removed from SIT isolation valves SR 3.5.1.5 SR 3.5.1.5 EGCS-Operating 3.5.2 3.5.2 Verify specified valve position SR 3.5.2.1 SR 3.5.2.1 Verify valves are in the correct position SR 3.5.2.2 SR 3.5.2.2 Verify ECCS piping is full of water SR 3.5.2.3 Verify valves actuate to correct position SR 3.5.2.6 SR 3.5.2.5 Verify ECCS pumps start on signal SR 3.5.2.7 SR 3.5.2.6 Verify LPSI pump stops on signal SR 3.5.2.8 SR 3.5.2.7 Verify throttle valves stop in correct position SR 3.5.2.9 Verify containment sump is not blocked by debris SR 3.5.2.10 SR 3.5.2.8 Verify SOC interlock works SR 3.5.2.9 RWT 3.5.4 3.5.4 Verify water temperature SR 3.5.4.1 SR 3.5.4.1 Verify water temperature SR 3.5.4.1 SR 3.5.4.2 Verify water volume SR 3.5.4.2 SR 3.5.4.3 Verify boron concentration SR 3.5.4.3 SR 3.5.4.4 TSP/STB 3.5.5 3.5.5 Verify baskets contain TSP/STB SR 3.5.5.1 SR 3.5.5.1 Verify pH adjustment of water SR 3.5.5.2 SR 3.5.5.2 4
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification TitlelSurveillance Description TSTF-425 CCNPP Containment Air Locks 3.6.2 3.6.2 Verify only one door open at a time SR 3.6.2.2 SR 3.6.2.2 Containment Isolation Valves 3.6.3 3.6.3 Verify purge valves are closed SR 3.6.3.1 Verify vent valves are closed SR 3.6.3.2 SR 3.6.3.1 Verify isolation valves are closed SR 3.6.3.3 SR 3.6.3.2 Verify isolation time of valves SR 3.6.3.5 Perform leak rate test of purge valves SR 3.6.3.6 Verify valves actuate to correct position SR 3.6.3.7 SR 3.6.3.5 Verify purge valve is blocked SR 3.6.3.8 Containment Pressure 3.6.4 3.6.4 Verify pressure is within limits SR 3.6.4.1 SR 3.6.4.1 Containment Air Temperature 3.6.5 3.6.5 Verify temperature is within limits SR 3.6.5.1 SR 3.6.5.1 Containment Spray and Cooling System 3.6,6A 3.6.6 Verify containment spray valves are in the correct position SR 3.6.6A.1 SR 3.6.6,1 Operate cooling train fan SR 3.6.6A.2 SR 3.6.6.2 Verify cooling water flow rate SR 3.6.6A.3 SR 3.6.6.3 Verify 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 3.6.6.5 Verify containment spray pump starts SR 3.6.6A.7 SR 3.6.6.6 Verify cooling train starts SR 3.6.6A.8 SR 3.6.6.7 Verify spray nozzle is unobstructed SR 3.6.6A.9-Spray Additive System 3.6.7 Shield Building Exhaust Air Cleanup System 3.6.8 HMS 3.6.9 ..
Iodine Cleanup System/Iodine Removal System 3.6.10 3.6.8 Operate each train SR 3.6.10.1 SR 3.6.8.1 Verify each train actuates SR 3.6.10.3 SR 3.6.8.3 Verify bypass damper can be opened SR 3.6.10.4 ..
Shield Building 3.6.11 ..
MSlVs 3.7.2 3.7.2 MFIVs 3.7.3 3.7.15 ADVs 3.7.4 3.7.18 Verify complete cycle of ADVs 3.7.4.1 3.7.18.1 AFW System 3.7.5 3.7.3 Verify valves are in the correct position SR 3.7.5.1 SR 3.7.3.1 Verify valves actuate to the correct position SR 3.7.5.3 SR 3.7.3.4 Verify the AFW pumps start automatically SR 3.7.5.4 SR 3.7.3.5 Verify the AFW system can provide minimum flow SR 3.7.3.6 Condensate Storage Tank 3.7.6 3,7.4 Verify CST level/volume SR 3.7.6.1 SR 3.7.4.1 CCW/CC System 3.7.7 3.7.5 Verify valves are in the correct position SR 3.7.7.1 SR 3.7.5.1 Verify valves actuate to the correct position SR 3.7.7.2 SR 3.7.5.2 Verify pumps start automatically SR 3.7.7.3 SR 3.7.5.3 5
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP SWS/SRW 3.7.8 3.7.6 Verify valves are in the correct position SR 3.7.8.1 SR 3.7.6.1 Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.6.2 Verify pumps start automatically SR 3.7.8.3 SR 3.7.6.3 SWS/SW 3.7.8 3.7.7 Verify valves are in the correct position SR 3.7.8.1 SR 3.7.7.1 Verify valves actuate to the correct position SR 3.7.8.2 SR 3.7.7.2 Verify pumps start automatically SR 3.7.8.3 SR 3.7.7.3 UHS 3.7.9 ECW 3.7.10 ..
CREACS/CREVS 3.7.11 3.7.8 Operate filter train SR 3.7.11.1 SR 3.7.8.1 Verify each train actuates on a signal SR 3.7.11.3 SR 3.7.8.3 Verify positive pressure can be maintained SR 3.7.11.4 CREATS/CRETS 3.7.12 3.7.9 Verify heat load can be removed/temperature can be maintained SR 3.7.12.1 SR 3.7.9.1 ECCS PREACS 3.7.13 .... ___
FBACS/SFPEVS 3.7.14 3.7.11 Operate each train SR 3.7.14.1 Verify a train is in operation SR 3.7.11.1 Verify each train actuates on a signal SR 3.7.14.3 Verify a train can maintain a negative pressure SR 3.7.14.4 SR 3.7.11.3 Verify the bypass damper can be opened SR 3.7.14.5 PREACSIPREVS 3.7.15 3.7.12 Operate each train SR 3.7.15.1 SR 3.7.12.1 Verify each train actuates on a signal SR 3.7.15.3 SR 3.7.12.3 Verify a train can maintain a negative pressure SR 3.7.15.4 Verify the bypass damper can be opened SR 3.7.15.5 Fuel Storage Pool Water Level/ SFP Water Level 3.7.16 3.7.13 Verify water level in pool SR 3.7.16.1 SR 3.7.13.1 FSP Boron Concentration/SFP Boron Concentration 3.7.17 3.7.16 Verify boron concentration in pool SR 3.7.17.1 SR 3.7.16.1 Secondary Specific Activity 3.7.19 3.7.14 Verify secondary specific activity is within limits SR 3.7.19.1 SR 3.7.14.1 AC Sources-Operating 3.8.1 3.8.1 Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.1 Verify correct breaker alignment SR 3.8.1.1 SR 3.8.1.2 Verify DG standby start SR 3.8.1.2 SR 3.8.1.3 Verify 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 3.8.1.4 Verify day tank volume SR 3.8.1.4 SR 3.8.1.5 Check for water in the day tank SR 3.8.1.5 SR 3.8.1.6 Verify fuel oil transfer system operates SR 3.8.1.6 SR 3.8.1.7 Verify DG standby start (fast start) SR 3.8.1.7 SR 3.8.1.9 Verify manual transfer of AC sources SR 3.8.1.8 SR 3.8.1.10 Verify single load reject SR 3.8.1.9 SR 3.8.1.12 Verify full load reject SR 3.8.1.10 6
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP Verify DG start and operation on a loss of offsite power SR 3.8.1.11 Verify DG start and operation on an ESF signal SR 3.8.1.12 Verify non-critical trips are bypassed SR 3.8.1.13 SR 3.8.1.13 Verify 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 3.8.1.11 SR 3.8.1.17 Verify hot restart of the DG SR 3.8.1.15 Verify DG synchronizes to offsite power SR 3.8.1.16 SR 3.8.1.14 Verify ESF signal overrides DG test mode SR 3.8.1 .17-Verify load sequencer operation SR 3.8.1.18 SR 3.8.1.8 Verify DG start and operation on an ESE/LOOP signal SR 3.8.1.19 SR 3.8.1.15 Verify DG operation during simultaneous start SR 3.8.1.20 Diesel Fuel Oil, Lube Oil and Starting Air/Diesel Fuel Oil 3.8.3 3.8.3 Verify volume of diesel fuel oil SR 3.8.3.1 SR 3.8.3.1 Verify lube oil inventory SR 3.8.3.2 Verify air start receiver pressure SR 3.8.3.4 Remove accumulated water from storage tank SR 3.8.3.5 SR 3.8.3.3 DC Sources - Operating 3.8.4 3.8.4 Verify battery terminal voltage SR 3.8.4.1 SR 3.8.4.1 Verify battery charger provides adequate voltage SR 3.8.4.2 SR 3.8.4.6 Verify battery capacity SR 3.8.4.3 SR 3.8.4.7 Verify no visible corrosion .... SR 3.8.4.2 Verify no physical damage -- SR 3.8.4.3 Remove visible corrosion SR 3.8.4.4 Verify battery connection resistance .... SR 3.8.4.5 Battery ParameterslBattery Cell Parameters 3.8.6 3.8.6 Verify float current/voltage SR 3.8.6.1 SR 3.8.6.1 Verify battery cell voltage SR 3.8.6.2 SR 3.8.6.2 Verify electrolyte level SR 3.8.6.3 SR 3.8.6.1 Verify battery temperature SR 3.8.6.4 SR 3.8.6.3 Verify cell voltage SR 3.8.6.5 SR 3.8.6.2 Verify battery capacity - discharge test SR 3.8.6.6 SR 3.8.4.8 Inverters-Operating 3.8.7 3.8.7 Verify correct voltage SR 3.8.7.1 SR 3.8.7.1 Inverters-Shutdown 3.8.8 3.8.8 Verify correct voltage SR 3.8.8.1 SR 3.8.8.1 Distribution Systems-Operating 3.8.9 3.8,9 Verify correct breaker alignments SR 3.8.9.1 SR 3.8.9.1 Distribution Systems-Shutdown 3.8.10 3.8.10 Verify correct breaker alignments SR 3.8.10.1 SR 3.8.10.1 Boron Concentration 3.9.1 3.9.1 Verify boron concentration SR 3.9.1.1 SR 3.9.1.1 Nuclear Instrumentation 3.9.2 3.9.2 Perform Channel Check SR 3.9.2.1 SR 3.9.2.1 Perform Channel Calibration SR 3.9.2.2 SR 3.9.2.2 Containment Penetrations 3.9.3 3.9.3 Verify containment penetrations are in correct status SR 3.9.3.1 SR 3.9.3.1 Verify containment purge actuates on a signal SR 3.9.3.2 SR 3.9.3.2 7
ATTACHMENT (1)
COMPARISON MATRIX Technical Specification Title/Surveillance Description TSTF-425 CCNPP SDC 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 3.9.4.1 SDC and Coolant Circulation-Low Water Level 3.9.5 3.9.5 Verfy ae oeraleSR DC oos 3.9.5.1 SR 3.9.5.1 Verify correct breaker alignment SR 3.9.5.2 SR 3.9.5.3 Verify flow rate of SDC loop SR 3.9.5.2 Refueling Water Level/Refueling Pool Water Level 3.9.6 3.9.6 Verify water level SR 3.9.6.1 SR 3.9.6.1 8
ATTACHM ENT (2)
MARKED UP TECHNICAL SPECIFICATION AND TECHNICAL SPECIFICATION BASES PAGES Calvert Cliffs Nuclear Power Plant July 30, 2015 30, 2015Power Plant JulyNuclear Calvert Cliffs
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) _________
SURVEILLANCE FREQUENCY SR 3.8.1.16 For the LCO 3.8.1.c AC electrical sources, In accordance SR 3.8.1.1, SR 3.8.1.2, SR 3.8.1.3, with applicable SR 3.8.1.5, SR 3.8.1.6, and SR 3.8.1.7 are Surveillance required to be performed. Requirements SR 3.8.1.17-----------NOTE--- ------
Momentary transients outside the load and power factor limits do not invalidate this test.
Verify each DG operates for Ž 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: ~ fl~~
- a. For Ž 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 to
Ž4200 kW for DG IA, and Ž 3150 kW and
- 3300 kW for DGs lB, 2A, and 2B, and
Ž2700 kW and
- 3000 kW for DGs lB, 2A, and 2B.
CALVERT CLIFFS - UNIT 1 3 .8. 1-17 Amendment No. 307 CALVERT CLIFFS - UNIT 2 Amendment No. 285
ADV s 3.7.18 SURVEILLANCE REQUIREMENTS _________
SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify one complete cycle of each ADV.
CALVERT CLIFFS - UNIT 1 3.7.,18-2 Amendment No. 311 CALVERT CLIFFS - UNIT 2 Amendment No. 289
ADVs B 3.7.18 BASES C.I and C.2 If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 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 upon the 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 />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.18.1 REQUIREMENTS To perform a cooldown of the RCS, the ADVs must be able to be opened through their full range. This SR ensures the ADVs are tested through a full cycle at least once per fuel cycle. This test is performed using the manual handwheel assembly. Any use of an ADV using the manual handwheel REFERECS1 USAScin0.
Revision XX I CALVERT CLIFFS - UNITS
- & 22 UNITS 11 & B 3.7.18-3 B 3.7.18-3 Revision XX I
AC Sources-Operating B 3.8.1 BASES SR 3.8.1.17 Reference 13 requires demonstration that the DGs can start and run continuously at full load capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Ž 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 load equivalent to 105-110% of the continuous service rating and the remainder of the time at a load equivalent to 90-100% of the continuous service rating. For the Nos. lB, 2A, and 2B DGs the SR reflects these loading ranges. For the No. IA DG, since the post accident loading is significantly less than the continuous service rating, the post accident loading (<4000 kW) is used instead of the continuous service rating. Actual testing is performed at a load higher than the post accident loading.
The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelubricating and warmup, discussed in SR 3.8.1.3 and for gradual loading, discussed in SR 3.8.1.4 are applicable to this SR.
~The load band is provided to avoid routine overloading of 1hE* *UrqeA mo('+/-. the 0G. Routine overloading may result in more frequent F:::M
- J-1*L. llS~r teardown inspections in accordance with vendor
@"*~c)*'*L*,::**A**Irecommendations in order to maintain DG OPERABILITY.
+k* S*cv L (c. In addition, the post-accident load for No. IA DG is
__ eV*L S A(.* significantly lower than the continuous rating of No. 1A DG.
- ,_* e.L.* ITo ensure No. 1A DG performance is not degraded, routine bj
- _ *monitoring of engine parameters should be performed during This SR is modified by a Note. Note 1 states that momentary transients due to changing bus loads do not invalidate this test. Similarly, momentary power factor transients above the limit will not invalidate the test.
REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants" CALVERT CLIFFS - UNITS 1 & 2 B 3,8.1-32 Revision 52