ML15170A126
| ML15170A126 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/17/2015 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| W3FI-2015-0006 | |
| Download: ML15170A126 (28) | |
Text
Attachment 6 to W3FI-2015-0006Proposed No Significant Hazards Consideration(2 Pages Attached) to W3F1-2015-0006Page 1Attachment 6Proposed No Significant Hazards ConsiderationDescription of Amendment Request:This license amendment requests the adoption of an approved change to the standardtechnical specifications (STS) for Combustion Engineering Pressurized Water Reactors(NUREG-1432), to allow relocation of specific technical specification (TS) surveillancefrequencies to a licensee-controlled program. The proposed change is described in TechnicalSpecification Task Force (TSTF) Traveler, TSTF-425, Revision 3 (Rev. 3) (ADAMSAccession No. ML080280275), related to the Relocation of Surveillance Frequencies toLicensee Control -RITSTF Initiative 5b and is described in the Notice of Availabilitypublished in the Federal Register on July 6, 2009 (74 FR 31996).The proposed change is consistent with NRC-approved Industry/TSTF Traveler, TSTF-425,Rev. 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF Initiative 5b." Theproposed change relocates surveillance frequencies to a licensee-controlled program, theSurveillance Frequency Control Program, the SFCP. This change is applicable to licenseesusing probabilistic risk guidelines contained in NRC-approved NEI 04-10, "Risk-InformedTechnical Specifications Initiative 5b, Risk-Informed Method for Control of SurveillanceFrequencies," (ADAMS Accession No. 071360456).Basis for proposed no significant hazards consideration: As required by 10 CFR 50.91(a),Entergy's analysis of the issue of no significant hazards consideration is presented below:1. Does the proposed change involve a significant increase in the probability orconsequences of any accident previously evaluated?Response: No.The proposed change relocates the specified frequencies for periodic surveillancerequirements to licensee control under a new Surveillance Frequency ControlProgram. Surveillance frequencies are not an initiator to any accident previouslyevaluated. As a result, the probability of any accident previously evaluated is notsignificantly increased. The systems and components required by the technicalspecifications for which the surveillance frequencies are relocated are still required tobe operable, meet the acceptance criteria for the surveillance requirements, and becapable of performing any mitigation function assumed in the accident analysis. As aresult, the consequences of any accident previously evaluated are not significantlyincreased.Therefore, the proposed change does not involve a significant increase in theprobability or consequences of an accident previously evaluated.2. Does the proposed change create the possibility of a new or different kind of accidentfrom any previously evaluated?Response: No.No new or different accidents result from utilizing the proposed change. The changesdo not involve a physical alteration of the plant (i.e., no new or different type ofequipment will be installed) or a change in the methods governing normal to W3F1-2015-0006Page 2plant operation. In addition, the changes do not impose any new or differentrequirements. The changes do not alter assumptions made in the safety analysis. Theproposed changes are consistent with the safety analysis assumptions and currentplant operating practice.Therefore, the proposed change does not create the possibility of a new or differentkind of accident from any accident previously evaluated.3. Does the proposed change involve a significant reduction in the margin of safety?Response: No.The design, operation, testing methods, and acceptance criteria for systems,structures, and components (SSCs), specified in applicable codes and standards (oralternatives approved for use by the NRC) will continue to be met as described in theplant licensing basis (including the final safety analysis report and bases to TS), sincethese are not affected by changes to the surveillance frequencies. Similarly, there isno impact to safety analysis acceptance criteria as described in the plant licensingbasis. To evaluate a change in the relocated surveillance frequency, Entergy willperform a probabilistic risk evaluation using the guidance contained in NRC approvedNEI 04-10, Rev. 1, in accordance with the TS SFCP. NEI 04-10, Rev. 1,methodology provides reasonable acceptance guidelines and methods for evaluatingthe risk increase of proposed changes to surveillance frequencies consistent withRegulatory Guide 1.177.Therefore, the proposed changes do not involve a significant reduction in a margin ofsafety.Based upon the reasoning presented above, Entergy concludes that the requested changedoes not involve a significant hazards consideration as set forth in 10 CFR 50.92(c),Issuance of Amendment. to W3F1-2015-0006STS-WF3 CTS Cross Reference(24 Pages Attached) to W3F1-2015-0006Page 1Attachment 7STS-WF3 CTS Cross ReferenceTS Section TitlelSurveillance Description TSTF-425 WF3Verify SDM is within the limits specified in the COLR -MODES 3.1.1.1 4.1.1.23,4,&5.With any CEA fully or partially withdrawn, the SHUTDOWN 3.1.1.1 4.1.1.1.1 .eMARGIN shall be determined to be greater than or equal to thatspecified in the COLR:When in MODE 3, 4, or 5 with greater than or equal to 1.0, atleast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that CEA group withdrawalis within the Transient Insertion Limits of Specification 3.1.3.6.With any CEA fully or partially withdrawn, the SHUTDOWN 4.1.1.1.1.bMARGIN shall be determined to be greater than or equal to thatspecified in the COLR:When in MODE 1 or MODE 2 with Kff greater than or equal to1.0 by verifying that CEA group withdrawal is within the TransientInsertion Limits of Specification 3.1.3.6.Verify overall core reactivity balance is within + 1.0% Ak/k of 3.1.2.1 4.1.1.1.2predicted values -MODES 1 & 2At least one of the above required flow paths shall be 4.1.2.1demonstrated OPERABLE by verifying that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correct position.At least two of the above required flow paths shall be 4.1.2.2.ademonstrated OPERABLE:At least once per 31 days by verifying that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correct position.At least two of the above required flow paths shall be 4.1.2.2.bdemonstrated OPERABLE:By verifying that each automatic valve in the flow path actuatesto its correct position on an SIAS test signal.At least two of the above required flow paths shall be 4.1.2.2.cdemonstrated OPERABLE:By verifying that the flow path required by Specification3.1.2.2a.1 and 3.1.2.2a.2 delivers at least 40 gpm to the ReactorCoolant System.Each required charging pump shall be demonstrated OPERABLE 4.1.2.4by verifying that each charging pump starts in response to anSIAS test signal. to W3F1-2015-0006Page 2TS Section Title/Surveillance Description TSTF-425 WF3Each required boric acid makeup pump shall be demonstrated 4.1.2.6OPERABLE by verifying that each boric add makeup pumpstarts in response to an SIAS test signal.The above required borated water source shall be demonstrated 4.1.2.7.aOPERABLE:a. When the Reactor Auxiliary Building air temperature is lessthan 550F by verifying the boric acid makeup tank solution isgreater than or equal to 60OF (when it is the source of boratedwater).The above required borated water source shall be demonstrated 4.1.2.7.b. 1OPERABLE:Verifying the boron concentration of the water.The above required borated water source shall be demonstrated 4.1.2.7.b.2OPERABLE:Verifying the contained borated water volume of the tank.Each borated water source shall be demonstrated OPERABLE: 4.1.2.8.aBy verifying the boric acid makeup tank solution temperature isgreater than or equal to 60'F when the Reactor Auxiliary Buildingair temperature is less than 550FEach borated water source shall be demonstrated OPERABLE: 4.1.2.8.b.1Verifying the boron concentration in the water.Each borated water source shall be demonstrated OPERABLE: 4.1.2.8.b.2Verifying the contained borated water volume of the watersource.Each required boron dilution alarm shall be demonstrated 4.1.2.9.2OPERABLE by performing a channel check.Each required boron dilution alarm shall be demonstrated 4.1.2.9.2OPERABLE by performing a channel functional test.Each required boron dilution alarm shall be demonstrated 4.1.2.9.2OPERABLE by performing a channel calibration.The requirements of Specification 3.1.2.9.a.2 or 3.1.2.9.b.2 shall 4.1.2.9.4be verified.Verify the indicated position of each CEA to be within [7 inches] 3.1.4.1 4.1.3.1.1of all other CEAs in its group.Verify that, for each CEA, its OPERABLE CEA position indicator 3.1.4.2 4.1.3.2channels indicate within [5 inches] of each other.Verify CEA freedom of movement (trippability) by moving each 3.1.4.3 4.1.3.1.2individual CEA that is not fully inserted into the reactor core [5inches] in either direction.Perform a CHANNEL FUNCTIONAL TEST of the reed switch 3.1.4.4 4.1.3.3position transmitter channel. to W3F1-2015-0006Page 3TS Section Title/Surveillance Description TSTF-425 WF3Verify each shutdown CEA is withdrawn 2- [145] inches. 3.1.5.1 4.1 .3.5.bVerify each regulating CEA group position is within its insertion 3.1.6.1 4.1.3.6limits.Verify the accumulated times during which the regulating CEA 3.1.6.2 4.1.3.6groups are inserted beyond the steady state insertion limits butwithin the transient insertion limits.Verify PDIL Alarm Circuit is OPERABLE. 3.1.6.3 4.1.3.6Vperify -THstERMAL PonE ,isjE eqSual W G 1oo esta h etpwr 31.7. 34.10.2.Verify that the position of each CEA not fully inserted is within the 3.1.7.1 4.10.1.1acceptance criteria for available negative reactivity addition.Verify part length CEA group position. 3.1.7.1 -Verify THERMAL POWER is equal to or less than the test power 3.1.8.1 4.10.2.1plateau.Verify that the position of each CEA not fully inserted is within the 3.1.8.1 4.10.1.1acepaceciteria for aivailable niegative reactivity addition.Verify THERMAL POWER equal to or less than the test power 3.1.9.1 4.10.2.1plateau.Verify LHR, as indicated on each OPERABLE local power 3.2.1.1 4.2.1.2density channel, is within its limit.Verify the COLSS margin alarm actuates at a THERMAL 3.2.1.2 4.2.1.3POWER equal to or less than the core power operating limitbased on LHR.Verify measured Fm y obtained using the Incore Detector System 3.2.2.1 4.2.2.2.bis equal to or less than the value of Fcxy used in the COLSS andCPCs.Calculate Tq and verify it is within the limit 3.2.3.1 4.2.3.2.bVerify COLSS azimuthal tilt alarm is actuated at a Tq value less 3.2.3.2 4.2.3.2.cthan the Tq value used in the CPCs.Independently confirm the validity of the COLSS calculated Tq by 3.2.3.3 4.2.3.2.duse of the incore detectors.1 Waterford no longer has part length CEAs. to W3F1 -2015-0006Page 4TS Section Title/Surveillance Description TSTF-425 WF3Verify DNBR, as indicated on all OPERABLE DNBR channels, is 3.2.4.1 4.2.4.2within the limit of Figure 3.2.4-1 or 3.2.4-2 of the COLR, asapplicable.Verify COLSS margin alarm actuates at a THERMAL POWER 3.2.4.2 4.2.4.3level equal to or less than the core power operating limit basedon DNBR.Verify ASI is Within Limits. 3.2,51 4,27Each reactor protective instrumentation channel shall be --. 4.3.1.1 Table 4.3-1demonstrated OPERABLE by the performance of the CHANNEL Functional Unit (FU)CHECK, CHANNEL CALIBRATION and CHANNEL 1FUNCTIONAL TEST operations for the MODES and at thefrequencies shown in Table 4.3-1.Manual Reactor Trip Channel Functional TestPerform a CHANNEL CHECK of each RPS instrument channel 3.3.1.1 4.3.1.1 Table 4.3-1except Loss of Load. FUs 2 through 10,and 14 through 16Verify total Reactor Coolant System (RCS) flow rate as indicated 3.3.1.2 4.3.1.1 Table 4.3-1by each CPC is less than or equal to the RCS total flow rate. FU 10If necessary, adjust the CPC addressable constant flowcoefficients such that each CPC indicated flow is less than orequal to the RCS flow rate.Check the CPC auto restart count. 3.3.1.3 4.3.1.5Perform calibration (heat balance only) and adjust the linear 3.3.1.4 4.3.1.1 Table 4.3-1power level signals and the CPC addressable constant FU 2, 9, 10, and 14multipliers to make the CPC AT power and CPC nuclear powercalculations agree with the calorimetric, if the absolute differenceis > [2]%.Verify total RCS flow rate indicated by each CPC is less than or 3.3.1.5 4.3.1.1 Table 4.3-1equal to the RCS flow determined by calorimetric calculations. FU 10Verify linear power subchannel gains of the excore detectors are 3.3.1.6 4.3.1.1 Table 4.3-1consistent with the values used to establish the shape annealing FU 2matrix elements in the CPCs.Perform CHANNEL FUNCTIONAL TEST on each channel 3.3.1.7 4.3.1.1, Table 4.3-1except Loss of Load and power range neutron flux. FUs 2 through 10, 12,13, 14, 15, 16Perform CHANNEL CALIBRATION of the power range neutron 3.3.1.8 4.3.1.1 Table 4.3-1flux channels. FU 2Perform CHANNEL FUNCTIONAL TEST for Loss of Load 3.3.1.9Function.Perform CHANNEL CALIBRATION on each channel, including 3.3.1.10 4.3.1.2 and 4.3.1.1,bypass removal functions. Table 4.3-1 FUs 3through 10, 14, 15,16Perform a CHANNEL FUNCTIONAL TEST on each CPC 3.3.1.11 4.3.1.2 and 4.3.1.1,channel. Table 4.3-1 FU 14 to W3F1-2015-0006Page 5TS Section TitlelSurveillance Description TSTF-425 WF3Verify RPS RESPONSE TIME is within limits. 3.3.1.14 4.3.1.3Perform a CHANNEL CHECK of each logarithmic power 3.3.2.1 4.3.1.1, Table 4.3-1channel. FU 3Perform a CHANNEL FUNCTIONAL TEST on each logarithmic 3.3.2.2 4.3.1.1, Table 4.3-1power channel. FU 3Perform a CHANNEL CALIBRATION on each logarithmic power 3.3.2.4 4.3.1.1, Table 4.3-1channel, including bypass removal function with Allowable Value FU 3;for trip channels < [.93]%. 4.3.1.2Verify RPS RESPONSE TIME is within limits. 3.3.2.5 4.3.1.3Perform a CHANNEL CHECK. 3.3.3.1 4.3.1.1 Table 4.3-1FU 15Check the CEAC auto restart count. 3.3.3.2 4.3.1.5Perform a CHANNEL FUNCTIONAL TEST. 3.3.3.3 4.3.1.1 Table 4.3-1FU 15Perform a CHANNEL CALIBRATION. 3.3.3.4 4.3.1.1 Table 4.3-1FU 15Perform a CHANNEL FUNCTIONAL TEST. 3.3.3.5 4.3.1.1 Table 4.3-1FU 15Verify the isolation characteristics of each CEAC isolation 3.3.3.6 4.3.1.4.a & bamplifier and each optical isolator for CEAC to CPC datatransfer.Perform Channel Functional Test of Each RTCB Channel. 3.3.3.1 Table 4.3-1FU 13Perform Channel Functional Test of Each RPS Logic 3.3.3.2 Table 4.3-1Channel. FUs 12Perform Channel Functional Test, Including Verification of UV 3.3.3.4 Table 4.3-1and Shunt Trips of Each RTCB Channel. FU 13Perform a Channel Check of each ESFAS instrument channel. 3.3.5.1 4.3.2.1, Table 4.3-2FUs lb & c, 2.b, 3.b &c, 4.b & c, 5.b, 7.b, c& e.Perform Channel Functional Test of each ESFAS instrument 3.3.5.2 4.3.2.1, Table 4.3-2channel. FUs 1.b,c, 2.b, 3.b, c &d, 4.b & c, 5.b &c,7b, & cPerform a CHANNEL CALIBRATION of each ESFAS instrument 3.3.5.3 4.3.2.1, Table 4.3-2channel, including bypass removal functions. FUs 1.b & c, 2.b, 3.b &c, 4.b & c, 5.b, 6.a, b& c, 7.b, c& e;4.3.2.2 to W3FI-2015-0006Page 6TS Section TitlelSurveillance Description TSTF-425 WF3Verify ESF RESPONSE TIME is within limits. 3.3.5.4 4.3.2.3Perform a CHANNEL FUNCTIONAL TEST on each ESFAS logic 3.3.6.1 4.3.2.1, Table 4.3-2channel. FUs 1.d, 2.c, 3.d, 4.d,5.c, 7.dPerform a subgroup relay test of each Actuation Logic channel, 3.3.6.2 4.3.2.1 Table 4.3-2which includes the de-energization of each subgroup relay and FUs 1.d, 2.c, 3.d, 4.d,verification of the OPERABILITY of each subgroup relay. 5.c, 7.dPerform a CHANNEL FUNCTIONAL TEST on each ESFAS 3.3.6.3 4.3.2.1, Table 4.3-2Manual Trip channel. FUs 1.a, 2.a, 3.a, 4.a,5.a, 7aEach radiation monitoring instrumentation channel shall be 4.3.3.1, Table 4.3-3demonstrated OPERABLE by the performance of the CHANNEL Instrument 2.c, d, &CHECK, CHANNEL CALIBRATION and CHANNEL e; 3.a, b, c, d, & eFUNCTIONAL TEST operations for the MODES and at thefrequencies shown in Table 4.3-3.Perform Channel Check. 3.3.6.1Perform Channel Functional Test. 3.3.6.2 4.3.2.1, Table 4.3-2FUs 6.a, b & cPerform CHANNEL CALIBRATION with setpoint Allowable 3.3.6.3 4.3.2.1, Table 4.3-2Values as follows: Channel Calibrationa. Degraded Voltage Function 43180] V and <[3220] V Time Column -FUs 6.a,bdelay: 4 ] seconds and -5[ ] seconds at [ ] V and & cb. Loss of Voltage Function ?[3180] V and <[3220] V Time delay:4] seconds and 5[ ] seconds at [ V.Each chlorine detection system shall be demonstrated 4.3.3.7.1OPERABLE by performance of a CHANNEL CHECK and aCHANNEL 'CALIBRATION.Each broad range gas detection system shall be demonstrated 4.3.3.7.3OPERABLE by performance of a CHANNEL CHECK, and aCHANNEL FUNCTIONAL TEST. The CHANNEL FUNCTIONALTEST will include the introduction of a standard gas.Perform Channel Check on each containment radiation 3.3.7.1 4.3.3. 1, Table 4.3-3,monitor channel. Instrument 1.bPerform Channel Functional Test on each containment 3.3.7.2 4.3.3. 1, Table 4.3-3,radiation monitor channel. Instrument 1.bVerify CPIS high radiation setpoint is less than or equal to theAllowable Value of [220 mR/hr].Perform Channel Functional Test on each CPIS Actuation 3.3.7.3logic Channel.2 Waterford LOV CFT is done at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than quarterly as NUREG 1432 requires. to W3FI-2015-0006Page 7TS Section Title/Surveillance Description TSTF-425 WF3Perform Channel Calibration on each containment radiation 3.3.7.4 4.3.3.1, Table 4.3-3,monitor channel. Instrument 1.bPerform Channel Functional Test on each CPIS Manual Tnp 3.3.7.5channel.Verify CPIS response time of each containment radiation channel 3.3.7.6is within limits.Perform a CHANNEL CHECK on the required control room 3.3.8.1 4.3.3.1, Table 4.3-3radiation monitor channel. FU 2.bPerform a CHANNEL FUNCTIONAL TEST on the required CRIS 3.3.8.2 Table 4.3-3radiation monitor channel. FU 2.bVerify CRIS high radiation setpoint is less than or equal to theAllowable Value of [6E4] cpm above normal background.Perform a CHANNEL FUNCTIONAL TEST on the required CRIS 3.3.8.3Actuation Logic channel.Perform a CHANNEL CALIBRATION on the required CRIS 3.3.8.4 Table 4.3-3radiation monitor channel. FU 2.bPerform a CHANNEL FUNCTIONAL TEST on the required CRIS 3.3.85Manual Trip channel.Verify response time of required CRIS channel is within limits. 3.3.8.6Perform Channel Check 3.3.9.1Perform a CHANNEL FUNCTIONAL TEST on each CVCS 3.3.9.2isolation channel with setpoints in accordance with the followingAllowable Values:West Penetration RoomPressure -High < .5 psigLetdown Heat ExchangerRoom Pressure -High < .5 psigPerform a CHANNEL CALIBRATION on each CVCS isolation 3.3.9.3 --pressure indicating channel.Perform a CHANNEL FUNCTIONAL TEST on each SBFAS 3.3.10.1 -automatic actuation channel.Perform Channel Functional Test -SBFAS Manual Trip 3.3.10.2Channel.Perform a CHANNEL CHECK on required FHIS radiation 3.3.10.1 4.3.3.1, Table 4.3-3,monitor channel. Instrument 1.bPerform a CHANNEL FUNCTIONAL TEST on required FHIS 3.3.10.2 4.3.3.1, Table 4.3-3,radiation monitor channel. Verify radiation monitor setpoint Instrument 1 .b[Allowable Values]:[ Airborne Particulate/ Iodine: :[6E4] cpm above background].Airbome Gaseous: [6E4] cpm above background.Perform a CHANNEL FUNCTIONAL TEST on required FHIS 3.3.10.3Actuation Logic channel. to W3F1-2015-0006Page 8TS Section Title/Surveillance Description TSTF-425 WF3Perform a CHANNEL FUNCTIONAL TEST on required FHIS 3.3.10.4Manual Trip logic.Perform a CHANNEL CALIBRATION on required FHIS radiation 3.3.10.5 4.3.3.1, Table 4.3-3,monitor channel. Instrument 1.bVerify response time of required FHIS channel is within limits. 3.3.10.6Perform Channel Check for each required instrumentation 3.3.11.1 4.3.3.6, Table 4.3-7channel that is normally energized.Perform Channel Calibration. 3.3.11.2 4.3.3.6, Table 4.3-7Each explosive gas monitoring instrumentation channel shall be... 4.3.3.11, Table 4.3-9demonstrated OPERABLE by performance of the CHANNEL Instrument la&bCHECK, CHANNEL CALIBRATION, and CHANNELFUNCTIONAL TEST operations at the frequencies shown inTable 4.3-9.Perform Channel Check. 3.3.12.1 4.3.3.5, Table 4.3-6Verify Each Control Circuit and Transfer Switch Can Perform 3.3.12.2 ..its Intended function.Perform Channel Calibration Each Instrument Channel. 3.3.12.3 4.3.3.5, Table 4.3-6Perform Channel Functional Test Rx Trip Circuit Breaker 3.3.12.4 --Open/Close Indication.Perform Channel Check. 3.3.13.1 4.3.1.1, Table 4.3-1FU 3Perform Channel Functional Test. 3.3.13.2 4.3.1.1, Table 4.3-1FU 3Perform Channel Calibration. 3.3.13.3 4.3. 1. 1, Table 4.3-1FU 3Verify Pressurizer Pressure is within the limits specified in the 3.4.1.1 4.2.8COLR.Verify RCS Cold Leg Temperature is within the limits specified 3.4.1.2 4.2.6in the COLR.Verify RCS total flow rate is greater than or equal to the limits 3.4.1.3 4.2.5specified in the COLR.Verify by precision heat balance that RCS total flow rate is within 3.4.1.4 ---the limits specified in the COLR.Verify RCS Tavg in Each Loop -[520]°F. 3.4.2.1The Reactor Coolant System temperature (Tcold) shall be .... 4.1.1.4determined to be greater than or equal to 533°F.Verify RCS Pressure, Temperature, and H/U and CID Rates within 3.4.3.1 4.4.8.1.1 to W3F1-2015-0006Page 9TS Section Title/Surveillance Description TSTF-425 WF3limits specified in the PTLR.Verify Each RCS Loop in Operation. 3.4A1 4A.11Verify One RCS Loop in Operation. 3.4.5.1 4.4.1.2.2Verify Secondary Side Water Level in Each SIG >[25]%. 3.4.5.2 4.4.1.2.3Verify Correct Breaker Alignment and Indicated Power 3.4.5.3 4.4.1.2.1Available to Each Required Pump.Verify required RCS loop or SDC train is in operation. 3.4.6.1 4.4.1.3.3Verify secondary side water level in required SG(s) is ?[25]%. 3.4.6.2 4.4.1.3.2Verify correct breaker alignment and indicated power available to 3.4.6.3 4.4.1.3.1each required pump.Verify Required SDC Train in Operation. 3.4.7.1 4.4.1.4.3Verify Secondary Side Water Level in Each SG >[251%. 3.4.7.2 4.4.1.4.2Verify Correct Breaker alignment and Indicated Power 3.4.7.3 4.4.1.4.1Available to Each Required SDC Pump.Verify Required SDC Train in Operation. 3.4.8.1 4.4.1.5Verify Correct Breaker Alignment and Indicated Power 3.4.8.2Available to Each Required SDC Pump.Verify Water Level is < [60%]. 3.4.9.1 4.4.3.1.1Verify Capacity of Required Pressurizer Heaters >[150] kW. 3.4.9.2 4.4.3.1.2Verify Required Pressurizer Heaters Capable of Being 3.4.9.3 4.4.3.1.3Powered from Emergency Bus.The auxiliary spray shall be verified to have power available to 4.4.3.2.1each valve.The auxiliary spray valves shall be cycled. 4.4.3.2.2Perform a Complete Cycle of Each Block valve. 3.4.11.1Perform a Complete Cycle of Each PORV. 3.4.11.2Perform a Complete Cycle of Each Solenoid Air Control Valve 3.4.11.3and Check Valve on the Accumulators.Verify PORVs and Block Valves are Capable of Being 3.4.11.4Powered from Emergency Power.Verify in the control room at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that each 4.4.8.3.1.avalve in the suction path between the RCS and the SDC reliefI to W3FI-2015-0006Page 10TS Section Title/Surveillance Description TSTF-425 WF3valve is open.Verify a Maximum of One HPSI Pump is Capable of 3.4.12.1Injecting intothe RCSVerify a Maximum of One Charging Pump is Capable of 3.4.12.2injecting intothe RCSVerify Each SIT is Isolated 3.4.12.3Verify Required RCS Vent > [1.3] Square Inches Open 3.4.12.4 4.4.8.3.2Verify PORV Block Valve is Open for Each Required PORV 3.4.12.5Perform Channel Functional Test on PORV 3.4.12.6Perform Channel Calibration on Each Required PORV 3.4.12.7Actuation ChannelVerify RCS operational LEAKAGE is within limits by performance 3.4.13.1 4.4.5.2.1of RCS water inventory balance.Verify primary to secondary LEAKAGE is <150 gallons per day 3.4.13.2 4.4.5.2.2through any one SG.Verify leakage from each RCS PIV is equivalent to <0.5 gpm per 3.4.14.1 4.4.5.2.3.a, 4.4.5.2.4.anominal inch of valve size up to a maximum of 5 gpm at an RCSpressure Z[2215] psia and <[2255] psia.Verify SDC System autoclosure interlock prevents the valves 3.4.14.2 4.5.2.d.1from being opened with a simulated or actual RCS pressuresignal ?[425] psig.Verify SDC System autoclosure interlock causes the valves to 3.4.14.3close automatically with a simulated or actual RCS pressuresignal 4-.600] psig.Perform Channel Check Containment Atmosphere Radiation 3.4.15.1 4.4.5.1.aMonitor.Perform Channel Functional Test Containment Atmosphere 3.4.15.2 4.4.5.1.aRad Monitor.Perform Channel Calibration Containment Sump Monitor. 3.4.15.3 4.4.5.1.bPerform Channel Calibration Containment Atmosphere 3.4.15.4 4.4.5.1.aRadioactivity Monitor.Perform Channel Calibration Containment Air Cooler 3.4.15.5condensate flow rate monitor.Containment sump level and flow monitors -performance of a 4.4.5.1.bCHANNEL CHECK (containment sump level monitor only).Verify RCS Gross Specific Activity s pCi/gm. 3.4.16.1 4.4.7, Table 4.4-4, #1Verify RCS Dose Equivalent 1-131 specific activity < 1.0 3.4.16.2 4.4.7, Table 4.4-4, #2pCi/gm.Determine E Bar from a sample taken in MODE 1 after a 3.4.16.3 4.4.7, Table 4.4-4, #3minimum of 2 EFPD and 20 days of MODE 1 operation haveelapsed since the reactor was last subcritical for > 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. to W3F1-2015-0006Page 11TS Section Title/Surveillance Description TSTF-425 WF3Each Reactor Coolant System vent path shall be demonstrated 4.4.10OPERABLE by:a. Verifying all manual isolation valves in each vent path arelocked in the open position.b. Cycling each vent valve through at least one complete cycle offull travel from the control room during COLD SHUTDOWN orREFUELING.c. Verifying flow through the Reactor Coolant System vent pathsduring venting during COLD SHUTDOWN or REFUELING.Verify Thermal Power < 5%. 14.17.1 4.103.1Verify SIT Isolation Valve fully Open. 3.5.1.1 4.5.1.a.2Verify borated water volume in each SIT is > [28% narrow range 3.5.1.2 4.5.1.a.1(1802 cubic feet) and < 72% narrow range (1914 cubic feet)].Verify nitrogen cover pressure in each SIT is ?[615] psig and 3.5.1.3 4.5.1.a.1<[655] psig.Verify boron concentration in each SIT is ?[1500] ppm and 3.5.1.4 4.5.1.b5[2800] ppm.Verify power is removed from each SIT isolation valve operator 3.5.1.5 4.5.1.dwhen pressurizer pressure is ?[2000] psia.Verifying that each safety injection tank isolation valve opens ...1 4.5.1.eautomatically under each of the following conditions:1. When an actual or simulated RCS pressure signal exceeds535 psia, and2. Upon receipt of a safety injection test signal.Verify Valve are in Position and Power Removed [and key 3.5.2.1 4.5.2.alocked in position].Verify each ECCS manual, power operated, and automatic valve 3.5.2.2 4.5.2.b.1in the flow path, that is not locked, sealed, or otherwise securedin position, is in the correct position.Verify ECCS Piping Full of Water. 3.5.2.3 4.5.2.b.2Verify each ECCS automatic valve in the flow path, that is not 3.5.2.6 4.5.2.e.1locked, sealed, or otherwise secured in position, actuates to thecorrect position on an actual or simulated actuation signal.Verify each ECCS pump starts automatically on an actual or 3.5.2.7 4.5.2.e.2simulated actuation signal.Verify each LPSI pump stops on an actual or simulated actuation 3.5.2.8 4.5.2.e.3signal.Verify, for each ECCS throttle valve listed below, each position 3.5.2.9 4.5.2.g3stop is in the correct position.3 Waterford TS SR 4.5.2.g is an event driven SR that meets the TSTF-425 criteria for exclusion, so it isnot included in the TS change. to W3F1-2015-0006Page 12TS Section Title/Surveillance Description TSTF-425 WF3Verify, by visual inspection, each ECCS train containment sump 3.5.2.10 4.5.2.d.2suction inlet is not restricted by debris and the suction inlet trashracks and screens show no evidence of structural distress orabnormal corrosion.Verify RWT borated water temperature is >[401F and <[1001F. 3.5.4.1 4.5.4.bVerify RWT borated water volume is ?[362,800 gallons, (88)%] 3.5.4.2 4.5.4.a. 1[above the ECCS suction connection].Verify RWT boron concentration is 2t[1720] ppm and <[2500] 3.5.4.3 4.5.4.a.2ppm.Verify TSP Baskets Contain > 291 ft.3.3.5.5.1 4.5.2.d.3Verify that a sample from the TSP baskets provides adequate pH 3.5.5.2 4.5.2.d.4adjustment of RWT water.Verify Only One Door Can be Opened at a Time 3.6.2.2 4.6.1.3.cVerify each [42] inch purge valve is sealed closed except for one 3.6.3.1purge valve in a penetration flow path while in Condition E of thisLCO.Verify each [8] inch purge valve is closed except when the [8] 3.6.3.2inch purge valves are open for pressure control, ALARA or airquality considerations for personnel entry, or for Surveillancesthat require the valves to be open.Verify each containment isolation manual valve and blind flange 3.6.3.3 4.6.1.1.athat is located outside containment and not locked, sealed, orotherwise secured and is required to be closed during accidentconditions is closed, except for containment isolation valves thatare open under administrative controls.The cumulative time that the purge supply or exhaust isolation 4.6.1.7.1valves are open during the past 365 days shall be determined.Perform Leak Rate Test of Purge Valves. 3.6.3.6Verify Automatic Valves Actuate to Correct Position. 3.6.3.7 4.6.3.2Verify each [ ] inch containment purge valve is blocked to restrict 3.6.3.8 4.6.1.7.3the valve from opening > [50]%.Verify containment pressure is within limits. 3.6.4.1 4.6.1.4Verify Average Air Temperature is within limits. 3.6.5.1 4.6.1.5Verify each containment spray manual, power operated, and 3.6.6A.1 4.6.2.1.bautomatic valve in the flow path that is not locked, sealed, orotherwise secured in position is in the correct position.Operate each containment cooling train fan unit for ?15 minutes. 3.6.6A.2 4.6.2.2.a.1 to W3F1 -2015-0006Page 13TS Section Title/Surveillance Description TSTF-425 WF3Verify Each Cooling Train Cooling Water Flow Rate > SR 3.6.6A.3 4.6.2.2.a.2[2000] GPM to Each Fan.Verify the containment spray piping is full of water to the [100] ft. SR 3.6.6A,4 4.6.2.1.alevel in the containment spray header.Verify each automatic containment spray valve in the flow path 3.6.6A.6 4.6.2.1.d. 1that is not locked, sealed, or otherwise secured in position,actuates to the correct position on an actual or simulatedactuation signal.Verifying that upon a recirculation actuation test signal, the safety .... 4.6.2.1.d.2injection system sump isolation valves open and that arecirculation mode flow path via an OPERABLE shutdowncooling heat exchanger is established.Verify each containment spray pump starts automatically on an 3.6.6A.7 4.6.2.1.d.3actual or simulated actuation signal.Verify each containment cooling train starts automatically on an 3.6.6A.8 4.6.2.2.bactual or simulated actuation signal.Verify Spray Nozzle is unobstructed. 3.6.6.A.9 4.6.2.1.eVerify each spray additive manual, power operated, and 3.6.7.1automatic valve in the flow path that is not locked, sealed, orotherwise secured in position is in the correct position.Verify spray additive tank solution volume is >[816] gal [90%] and 3.6.7.2<[896] gal [100%].Verify spray additive tank [N2H4] solution concentration is 3.6.7.3-[33]% and <[35]% by weight.Verify each spray additive automatic valve in the flow path that is 3.6.7.5not locked, sealed, or otherwise secured in position, actuates tothe correct position on an actual or simulated actuation signal.Verify spray additive flow [rate] from each solution's flow path. 3.6.7.6Operate each SBEACS train for [-10 continuous hours with the 3.6.8.1 4.6.6.1.aheaters operating or (for systems without heaters) ->15 minutes.Verify each SBEACS train actuates on an actual or simulated 3.6.8.3 4.6.6.1.d.2actuation signal.Verify each SBEACS filter bypass damper can be opened. 3.6.8.4Verifying that the filter cooling bypass valves can be manually -__ 4.6.6.1.d.3cycled.Verify each SBEACS train flow rate is -[] cfm. 3.6.8.5 4.6.6.1.b.31. Verifying that the ventilation system satisfies the in-place --- 4.6.6.1.b.1 & b.2testing acceptance criteria and uses the test procedures ofRegulatory Positions C.5.a, C.5.c, and C.5.d of RegulatoryGuide 1.52, Revision 2, March 1978, and the system flow rateis 10,000 cfm +/-10%.2. Verifying within 31 days after removal that a laboratoryanalysis of a representative carbon sample obtained inaccordance with Regulatory Position C.6.b of RegulatoryGuide 1.52, Revision 2, March 1978, shows the methyl iodidepenetration less than 0.5% when tested in accordance withASTM D3803-1989 at a temperature of 30CC and a relative to W3F1 -2015-0006Page 14TS Section Title/Surveillance Description TSTF-425 WF3humidity of 70%.1. Verifying that the pressure drop across the combined HEPA 4.6.6.1.d.1, d.4, & d.5filters and charcoal adsorber banks is less than 7.8 incheswater gauge while operating the system at a flow rate of10,000 cfm +/- 10%.4. Verifying that each system produces a negative pressure ofgreater than or equal to 0.25 inch water gauge in the annuluswithin 1 minute after a start signal.5. Verifying that the heaters dissipate 60 + 6.0, -6.0 kW whentested in accordance with ANSI N510-1975.Operate each HMS train for >15 minutes. 3.6.9.1Verify each HMS train flow rate on slow speed is 4[37,000] cfm. 3.6.9.2Verify each HMS train starts on an actual or simulated actuation 3.6.9.3signal.Operate each ICS train for [>10 continuous hours with heaters 3.6.10.1operating or (for systems without heaters) >15 minutes].Verify each ICS train actuates on an actual or simulated 3.6.10.3actuation signal.Verify each ICS filter bypass damper can be opened. 3.6.10.4Verify annulus negative pressure is > [5] inches water gauge. 3.6.11.1 4.6.6.2.aVerify one shield building access door in each access opening is 3.6.11.2 4.6.6.2.bclosed.Verify the shield building can be maintained at a pressure equal 3.6.11.4to or more negative than [-0.25] inch water gauge in the annulusby one Shield Building Exhaust Air Cleanup System train with afinal flow rate <[ ] cfm within [1] minute after a start signal.Verify each MSIV actuates to the isolation position on an actual 3.7.2.2 4.7.1.5.bor simulated actuation signal.Verify each MFIV [and [MFIV] bypass valve] actuates to the 3.7.3.2 4.7.1.6.bisolation position on an actual or simulated actuation signal.By performing a CHANNEL CHECK when the automatic --- 4.7.1.7.aactuation channels are required to be OPERABLE.By verifying each ADV automatic actuation channel is in .... 4.7.1.7.bautomatic with a setpoint of less than or equal to 1040 psia whenthe automatic actuation channels are required to be OPERABLE.By performing a CHANNEL CALIBRATION of each ADV --- 4.7.1.7.dautomatic actuation channel.By verifying actuation of each ADV to the open position on an 4.7.1.7.eactual or simulated automatic actuation signal. to W3F1-2015-0006Page 15TS Section TitlelSurveillance Description TSTF-425 WF3Verify one complete cycle of each ADV. 3.7.4.1 4.7.1.7.c4Verify one complete cycle of each ADV block valve. 3.7.4.2Verify each AFW manual, power operated, and automatic valve 3.7.5.1 4.7.1.2.ain each water flow path and in both steam supply flow paths tothe steam turbine driven pump, that is not locked, sealed, orotherwise secured in position, is in the correct position.Verify each AFW automatic valve that is not locked, sealed, or 3.7.5.3 4.7.1.2.c.1otherwise secured in position, actuates to the correct position onan actual or simulated actuation signal.Verify each AFW pump starts automatically on an actual or 3.7.5.4 4.7.1.2.c.2simulated actuation signal when in MODE 1, 2, or 3.Verify CST level is >ý[350,000] gal. 3.7.6.1 4.7.1.3.1.aBy verifying CSP temperature when the RAB air temperature is ...4.7.1.3.1 .bless than 55°F or greater than 1000F.Verify each CCW manual, power operated, and automatic valve 3.7.7.1 4.7.3.ain the flow path servicing safety related equipment, that is notlocked, sealed, or otherwise secured in position, is in the correctposition.Verify each CCW automatic valve in the flow path that is not 3.7.7.2 4.7.3.blocked, sealed, or otherwise secured in position, actuates to thecorrect position on an actual or simulated actuation signal.Verify each CCW pump starts automatically on an actual or 3.7.7.3 4.7.3.csimulated actuation signal.Verify each SWS manual, power operated, and automatic valve 3.7.8.1 4.7.3.ain the flow path servicing safety related equipment, that is notlocked, sealed, or otherwise secured in position, is in the correctposition.Verify each SWS automatic valve in the flow path that is not 3.7.8.2 4.7.3.blocked, sealed, or otherwise secured in position, actuates to thecorrect position on an actual or simulated actuation signal.Verify each SWS pump starts automatically on an actual or 3.7.8.3 4.7.3.csimulated actuation signal.Verify water level of UHS is >[562] ft. [mean sea level]. 3.7.9.1 4.7.4.aVerify average water temperature of UHS is 5[9O]'F. 3.7.9.2 4.7.4.aOperate each cooling tower fan for a[15] minutes. 3.7.9.3 4.7.4.bVerify each ECW manual, power operated, and automatic valve 3.7.10.1 4.7.12.1.ain the flow path, that is not locked, sealed, or otherwise secured4 Waterford TS 4.7.1.7.c is included in the IST program so it meets the criteria for TSTF-425 exclusionand is not included in the TS Change. to W3F1-2015-0006Page 16TS Section TitlelSurveillance Description TSTF-425 WF3in position, is in the correct position.At least once per 31 days by verifying that the water outlet 4.7.12.1.btemperature is < 420F at a flow rate of > 500 gpm.Verify the proper actuation of each ECW System component on 3.7.10.2 4.7.12.1.dan actual or simulated actuation signal.Operate each CREACS train for [a10 continuous hours with 3.7.11.1 4.7.6.1.aheaters operating or (for systems without heaters) a15 minutes].Verify each CREACS train actuates on an actual or simulated 3.7.11.3 4.7.6.1.d.2actuation signal.Each control room air filtration train (S-8) shall be demonstrated 4.7.6.1.bOPERABLE by:1. Verifying that the filtration train satisfies the in-place testingacceptance criteria and uses the test procedures ofRegulatory Positions C.5.a, C.5.c, and C.5.d of RegulatoryGuide 1.52, Revision 2, March 1978, and the system flowrate is 4225 cfm +/-10%.2. Verifying within 31 days after removal that a laboratoryanalysis of a representative carbon sample obtained inaccordance with Regulatory Position C.6.b of RegulatoryGuide 1.52, Revision 2, March 1978, shows the methyliodide penetration less than 0.5% when tested inaccordance with ASTM 03803-1989 at a temperature of30°C and a relative humidity of 70%.3. Verifying a system flow rate of 4225 cfm +/-10% during trainoperation when tested in accordance with ANSI N510-1975.Each control room air filtration train (S-8) shall be demonstrated 4.7.6.1.d.1, 3, & 4OPERABLE by:1. Verifying that the pressure drop across the combined HEPAfilters and charcoal adsorber banks is less than 7.8 incheswater gauge while operating the train at a flow rate of 4225cfm +/-10%.2. See above.3. Verifying that heaters dissipate 10 +11.0, -1.0 kW when testedin accordance with ANSI N510-1975.4. Verifying that on a toxic gas detection signal, the systemautomatically switches to the isolation mode of operation.Verify each CREATCS train has the capability to remove the 3.7.12.1assumed heat load.Each control room air conditioning unit shall be demonstrated 4.7.6.3.aOPERABLE:a. By verifying that the operating control room air conditioningunit is maintaining average control room air temperature lessthan or equal to 800F.Each control room air conditioning unit shall be demonstrated 4.7.6.3.bOPERABLE:If not performed within the last quarter, by verifying that eachcontrol room air conditioning unit starts and operates for at least15 minutes. to W3F1 -2015-0006Page 17TS Section Title/Surveillance Description TSTF-425 WF3Operate each ECCS PREACS train for [->10 continuous hours 3.7.13.1 4.7.7.awith the heater operating or (for systems without heaters) ->15minutes].Verify each ECCS PREACS train actuates on an actual or 3.7.13.3 4.7.7.d.2simulated actuation signal.Verify one ECCS PREACS train can maintain a negative 3.7.13.4 4.7.7.d.1 and 2pressure >[ ] inches water gauge relative to atmosphericpressure during the [post-accident] mode of operation at a flowrate of <[20,000] cfm.Verify each ECCS PREACS filter bypass damper can be opened. 3.7.13.5 4.7.7.d.3Each controlled ventilation area system shall be demonstrated -__ 4.7.7.bOPERABLE by:1. Verifying that the filtration train satisfies the in-place testingacceptance criteria and uses the test procedures ofRegulatory Positions C.5.a, C.5.c, and C.5.d of RegulatoryGuide 1.52, Revision 2, March 1978, and the system flowrate is 4225 cfm +/-1 0%.2. Verifying within 31 days after removal that a laboratoryanalysis of a representative carbon sample obtained inaccordance with Regulatory Position C.6.b of RegulatoryGuide 1.52, Revision 2, March 1978, shows the methyliodide penetration less than 0.5% when tested inaccordance with ASTM 03803-1989 at a temperature of30'C and a relative humidity of 70%.3. Verifying a system flow rate of 4225 cfm +/-10% during trainoperation when tested in accordance with ANSI N510-1975.Verifying that the heaters dissipate 20 + 2.0, -2.0 kW when 4.7.7.d.4tested in accordance with ANSI N510-1975.Operate each FBACS train for [?10 continuous hours with the 3.7.14.1heaters operating or (for systems without heaters) ?15 minutes].Verify each FBACS train actuates on an actual or simulated 3.7.14.3actuation signal.Verify one FBACS train can maintain a negative pressure >[] 3.7.14.4inches water gauge with respect to atmospheric pressure, duringthe [post-accident] mode of operation at a flow rate <[3000] cfm.Verify each FBACS filter bypass damper can be opened. 3.7.14.5Operate each PREACS train for [>10 continuous hours with the 3.7.15.1 4.7.7.aheater operating or (for systems without heaters) >15 minutes].Verify each PREACS train actuates on an actual or simulated 3.7.15.3 4.7.7.d.2actuation signal.Verify one PREACS train can maintain a negative pressure >[] 3.7.15.4 4.7.7.d.1 and 2inches water gauge with respect to atmospheric pressure duringthe [post-accident] mode of operation at a flow rate of 5[3000]cfm.Verify each PREACS filter bypass damper can be opened. 3.7.15.5 4.7.7.d.3 to W3F1-2015-0006Page 18TS Section Title/Surveillance Description TSTF-425 WF3At least once per 18 months or (1) after any structural -4.7.7.bmaintenance on the HEPA filter or charcoal adsorber housings,or (2) following painting, fire or chemical release in anyventilation zone communicating with the system by:1. Verifying that the filtration train satisfies the in-place testingacceptance criteria and uses the test procedures ofRegulatory Positions C.5.a, C.5.c, and C.5.d of RegulatoryGuide 1.52, Revision 2, March 1978, and the system flowrate is 4225 cfm +/-1 0%.2. Verifying within 31 days after removal that a laboratoryanalysis of a representative carbon sample obtained inaccordance with Regulatory Position C.6.b of RegulatoryGuide 1.52, Revision 2, March 1978, shows the methyliodide penetration less than 0.5% when tested inaccordance with ASTM 03803-1989 at a temperature of30'C and a relative humidity of 70%.3. Verifying a system flow rate of 4225 cfm +/-10% during trainoperation when tested in accordance with ANSI N510-1975.Verifying that the heaters dissipate 20 + 2.0, -2.0 kW when .... 4.7.7.d.4tested in accordance with ANSI N510-1975.Verify the fuel storage pool water level is ?23 ft. above the top of 3.7.16.1 4.9.11irradiated fuel assemblies seated in the storage racks.Verify the fuel storage pool boron concentration is within limit. 3.7.17.1 4.9.12Verify the specific activity of the secondary coolant is within limit. 3.7.19.1 4.7.1.4, Table 4.7-1Verify correct breaker alignment and indicated power availability 3.8.1.1 4.8.1.1.1.afor each [required] offsite circuit.Verify each DG starts from standby conditions and achieves 3.8.1.2 4.8.1.1.2.a.4steady state voltage >[3740] V and <[4580] V, and frequencya[58.8] Hz and <[61.2] Hz.Verify each DG is synchronized and loaded, and operates for 3.8.1.3 4.8.1.1.2.a.5a60 minutes at a load [4500] kW and <[5000] kW.Verifying the diesel generator is aligned to provide standby -_ 4.8.1.1.2.a.6power to the associated emergency busses.Verify each day tank [and engine mounted tank] contains a[220] 3.8.1.4 4.8.1.1.2.a.1gal of fuel oil.Check for and remove accumulated water from each day tank 3.8.1.5 4.8.1.1.2.b[and engine mounted tank].Verify the fuel oil transfer system operates to [automatically] 3.8.1.6 4.8.1.1.2.a.3transfer fuel oil from storage tank[s] to the day tank [and enginemounted tank].Verify each DG starts from standby condition and achieves: 3.8.1.7 4.8.1.1.2.da. In :[10] seconds, voltage [3740] V and frequency a[58.8] Hzandb. Steady state voltage 43740] V and <[4580] V, and frequency?[58.8] Hz and :461.2] Hz. to W3F1-2015-0006Page 19TS Section Title/Surveillance Description TSTF-425 WF3Verify [automatic [and] manual] transfer of AC power sources 3.8.1.8 4.8.1.1.1.bfrom the normal offsite circuit to each alternate [required] offsitecircuit.Verify each DG rejects a load greater than or equal to its 3.8.1.9 4.8.1.1.2.e.1associated single largest post-accident load and:a. Following load rejection, the frequency is <[63] Hz,b. Within [3] seconds following load rejection, the voltage is>[3740] V and <[4580] V, andc. Within [3] seconds following load rejection, the frequency isa[58.8] Hz and <[61.2] Hz.Verify each DG does not trip, and voltage is maintained 45000] 3.8.1.10 4.8.1.1.2.e.2V during and following a load rejection of -[4500] kW and<[5000] kW.Verify on an actual or simulated loss of offsite power signal: 3.8.1.11 4.8.1.1.2.e.3.a&b,a. De-energization of emergency buses,b. Load shedding from emergency buses,c. DG auto-starts from standby condition and:1. Energizes permanently connected loads in <[10] seconds,2. Energizes auto-connected shutdown loads through [automaticload sequencer],3. Maintains steady state voltage a[3740] V and <[4580] V,4. Maintains steady state frequency 4[58.8] Hz and <[61.2] Hz,and5. Supplies permanently connected [and auto-connected]shutdown loads for >5 minutes.Verify on an actual or simulated Engineered Safety Feature 3.8.1.12 4.8.1.1.2.e.4'(ESF) actuation signal each DG auto-starts from standbycondition and:a. In <[10] seconds after auto-start and during tests, achievesvoltage -[3740] V and frequency :458.8] Hz,b. Achieves steady state voltage ?[3740] V and <[4580] V andfrequency ?[58.8] Hz and <[61.2] Hz,c. Operates for a5 minutes,d. Permanently connected loads remain energized from theoffsite power system, ande. Emergency loads are energized [or autoconnected through theautomatic load sequencer] from the offsite power system.During shutdown, simulating a loss-of-offsite power in 4.8.1.1.2.e.5.aconjunction with an SIAS actuation test signal, anda) Verifying deenergization of the emergency busses and loadshedding from the emergency busses.During shutdown, simulating a loss-of-offsite power in 4.8.1 .1.2.e.5.bconjunction with an SIAS actuation test signal, andb) Verifying the diesel starts on the auto-start signal, energizesthe emergency busses and the permanently connected loadswithin 10 seconds after the auto-start signal, energizes theautoconnected emergency loads through the load sequencerand operates for greater than or equal to 5 minutes. Afterenergization, the steady-state voltage and frequency of theemergency busses shall be maintained at 4160 +420, -240 1 15Waterford 3's SR does not include STS 3.8.1.12 parts d and e. to W3F1-2015-0006Page 20TS Section TitlelSurveillance Description TSTF-425 WF3volts and 60 +1.2, -0.3 Hz during this test.Verify each DG's noncritical automatic trips are bypassed on 3.8.1.13 4.8.1.1.2.e.5.c[actual or simulated loss of voltage signal on the emergency busconcurrent with an actual or simulated ESF actuation signal].Verify each DG operates for 224 hour0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br />s: 3.8.1.14 4.8.1.1.2.e.6a. For e[2] hours loaded 45250] kW and <[5500] kW andb. For the remaining hours of the test loaded 44500] kW and<[5000] kW.Verify each DG starts and achieves: 3.8.1.15 4.8.1.1.2.e.4a. In <[10] seconds, voltage 4[3740] V and frequency a[58.8] Hzandb. Steady state voltage 4[3740] V and <[4580] V, and frequency4[58.8] Hz and 5[61.2] Hz.During shutdown, verifying that the auto-connected loads and 4.8.1.1.2.e.7permanently connected loads to each diesel generator do notexceed the 2000-hour rating of 4400 kW.Verify each DG: 3.8.1.16 4.8.1.1.2.e.8a. Synchronizes with offsite power source while loaded withemergency loads upon a simulated restoration of offsitepower,b. Transfers loads to offsite power source, andc. Returns to ready-to-load operation.Verify, with a DG operating in test mode and connected to its 3.8.1.17 4.8.1.1.2.e.9bus, an actual or simulated ESF actuation signal overrides thetest mode by:a. Returning DG to ready-to-load operation and[b. Automatically energizing the emergency load from offsitepower. ]Verifying that each fuel transfer pump transfers fuel to its 4.8.1.1.2.e.10associated diesel oil feed tank by taking suction from theopposite train fuel oil storage tank via the installed crossconnect.Verify interval between each sequenced load block is within + 3.8.1.18 4.8.1.1.2.e. 11[10% of design interval] for each emergency [and shutdown] loadsequencer.[ [18] months mode 5,6Verifying that the following diesel generator lockout features 4.8.1.1.2.e. 12prevent diesel generator starting only when required:a) turning gear engagedb) emergency stopc) loss of D.C. control powerd) governor fuel oil linkage trippedVerify on an actual or simulated loss of offsite power signal in 3.8.1.19 4.8.1.1.2.e.5a&bconjunction with an actual or simulated ESF actuation signal:a. De-energization of emergency buses,b. Load shedding from emergency buses,c. DG auto-starts from standby condition and:1. energizes permanently connected loads in <[10] seconds,2. energizes auto-connected emergency loads through [loadsequencer], to W3F1-2015-0006Page 21TS Section TitlelSurveillance Description TSTF-425 WF33. achieves steady state voltage >[3740] V and <[4580] V,4. achieves steady state frequency a[58.8] Hz and <[61.2] Hz,and5. supplies permanently connected [and auto-connected]emergency loads for >[5] minutes.Verify, when started simultaneously from standby condition, each 3.8.1.20 4.8.1.1.2.gDG achieves:a. In 5[10] seconds, voltage a[3740] V and frequency [58.8] Hzandb. Steady state voltage 2[3740] V and <[4580] V, and frequency;[58.8] Hz and <[61.2] Hz.Verify each fuel oil storage tank contains ? a (7] day supply of 3.8.3.1 4.8.1.3.1fuel.Verify lubricating oil inventory is a [7] day supply. 3.8.3.2Verify each DG air start receiver pressure is ? [225] psig. 3.8.3.4Check for and remove accumulated water from each fuel oil 3.8.3.5storage tank.Verify battery terminal voltage is greater than or equal to the 3.8.4.1 4.8.2.1.a.2minimum established float voltage.Verify each battery charger supplies ? [400] amps at greater than 3.8.4.2 4.8.2.1.c.4or equal to the minimum established float voltage for -> [8] hours.ORVerify each battery charger can recharge the battery to the fullycharged state within [24] hours while supplying the largestcombined demands of the various continuous steady state loads,after a battery discharge to the bounding design basis eventdischarge state.Verify battery capacity is adequate to supply, and maintain in 3.8.4.3 4.8.2.1.dOPERABLE status, the required emergency loads for the designduty cycle when subjected to a battery service test.Verify each battery float current is < [2] amps. 3.8.6.1 4.8.2.1.a.1, Note bVerify each battery pilot cell float voltage is ? 2.13 volts. ---- 4.8.2.1.a. 1Electrolyte level > Minimum level indication mark and _5 1/4" ---- 4.8.2.1.a.1above and not maximum level indication mark.Specific Gravity > 1.200. 4.8.2.1.a.1Verify each battery pilot cell float voltage is >[2.07] V. 3.8.6.2Verify each battery connected cell electrolyte level is greater than 3.8.6.3or equal to minimum established design limits.Verify each battery pilot cell temperature is greater than or equal 3.8.6.4to minimum established design limits.Verify each battery connected cell float voltage is ? [2.07] V. 3.8.6.5Verify each battery pilot cell float voltage is > 2.13 volts. ---- 4.8.2.1.b.1Electrolyte level > Minimum level indication mark and 5 1/4" ---- 4.8.2.1.b.1above and not maximum level indication mark.A to W3F1-2015-0006Page 22TS Section Title/Surveillance Description TSTF-425 WF3Specific Gravity > 1.195. Average of all connected cells > 1.205. 4.8.2.1.b.1There is no visible corrosion at either terminals or connectors, or 4.8.2.1.b.2the connection resistance of these items is less than 150 x 10"6ohms.3. The average electrolyte temperature of a random sample of at 4.8.2.1.b.3least ten of the connected cells is above 700F.The cells, cell plates, and battery racks show no visual indication 4.8.2.1.c.1of physical damage or abnormal deterioration.2. The cell-to-cell and terminal connections are clean, tight, and 4.8.2.1.c.2coated with anticorrosion material.3. The resistance of each cell-to-cell and terminal connection is 4.8.2.1.c.3less than or equal to 150 x 10-6 ohms.Verify battery capacity is a [80%] of the manufacturer's rating 3.8.6.6 4.8.2.1.ewhen subjected to a performance discharge test or a modifiedperformance discharge test.Verify correct inverter voltage, [frequency,] and alignment to 3.8.7.1 4.8.3.1required AC vital buses.Verify correct inverter voltage, [frequency,] and alignments to 3.8.8.1 4.8.3.2required AC vital buses.Verify correct breaker alignments and voltage to [required] AC, 3.8.9.1 4.8.3.1DC, and AC vital bus electrical power distribution subsystems.a~titutomai acstuaiom o he ytem and veifin haecVelfy correct breaker alignments and voltage to required AC, 3.8.1us1 4.8.3.2uC, and AC vital bus electrical power distrivution subsystems.least 1%o lltecrcirakrfte inoperable typefunictinlys etdThe above noted primary and backup containment penetration 4.8.4.1.a.1conductor overcurrent protective devices shall be demonstratedOPERABLE:1. By verifying that the medium voltage (4-15 kV) circuit breakersare OPERABLE by selecting, on a rotating basis, at least 10%of the circuit breakers of each voltage level, and performing thefollowing:(a) A CHANNEL CALIBRATION of the associated protectiverelays, and(b) An integrated system functional test which includes simulatedautomatic actuation of the system and verifying that eachrelay and associated circuit breakers and control circuitsfunction as designed.(c) For each circuit breaker found inoperable during thesefunctional tests, an additional representative sample of atleast 10% of all the circuit breakers of the inoperable typeshall also be functionally tested until no more failures arefound or all circuit breakers of that type have beenfunctionally tested.The above noted primary and backup containment penetration ---4.8.4. 1.a. 2conductor overcurrent protective devices shall be demonstrated to W3F1 -2015-0006Page 23TS Section TitlelSurveillance Description TSTF-425 WF3OPERABLE:a. By selecting and functionally testing a representativesample of at least 10% of each type of lower voltage circuitbreakers. Circuit breakers selected for functional testingshall be selected on a rotating basis. Testing of these circuitbreakers, except for those breakers with external tripdevices,* shall consist of injecting a current in excess of thebreakers' nominal setpoint and measuring the responsetime. The measured response time will be compared to themanufacturer's data to ensure that it is less than or equal toa value specified by the manufacturer. Circuit breakersfound inoperable during functional testing shall be restoredto OPERABLE status prior to resuming operation. For eachcircuit breaker found inoperable during these functionaltests, an additional representative sample of at least 10% ofall the circuit breakers of the inoperable type shall also befunctionally tested until no more failures are found or allcircuit breakers of that type have been functionally tested.The above noted primary and backup containment penetration 4.8.4.1.bconductor overcurrent protective devices shall be demonstratedOPERABLE:By subjecting each circuit breaker to an inspection andpreventive maintenance in accordance with procedures preparedin conjunction with its manufacturer's recommendations.The above required thermal overload protection and bypass 4.8.4.2.adevices shall be demonstrated OPERABLE.a. At least once per 18 months, by the performance of aCHANNEL FUNCTIONAL TEST of the bypass circuitry forthose thermal overload devices which are either1. Continuously bypassed and temporarily placed in force onlywhen the valve motors are undergoing periodic ormaintenance testing, or2. Normally in force during plant operation and bypassed underaccident conditions.The above required thermal overload protection and bypass 4.8.4.2.bdevices shall be demonstrated OPERABLE:At least once per 18 months by the performance of a CHANNELCALIBRATION of a representative sample of at least 25% of:1. All thermal overload devices which are not bypassed, suchthat each non-bypassed device is calibrated at least once per6 years.2. All thermal overload devices which are continuously bypassedand temporarily placed in force only when the valve motors areundergoing periodic or maintenance testing, and thermaloverload devices normally in force and bypassed underaccident conditions such that each thermal overload iscalibrated and each valve is cycled through at least onecomplete cycle of full travel with the motor-operator when thethermal overload is OPERABLE and not bypassed, at leastonce per 6 years.Verify boron concentration is within the limit specified in the 3.9.1.1 4.9.1.2COLR. to W3F1-2015-0006Page 24TS Section Title/Surveillance Description TSTF-425 WF3Perform CHANNEL CHECK. 3.9.2.1 4.9.2.aCHANNEL FUNCTIONAL TEST. 4.9.2.cPerform CHANNEL CALIBRATION. 3.9.2.2Verify each required containment penetration is in the required 3.9.3.1 4.9.4.1status.Verify each required containment purge and exhaust valve 3.9.3.2 4.9.4.2actuates to the isolation position on an actual or simulatedactuation signal.Vtferify9 r pequired SDC loops are 6b OPER BLE and oeSCloopi".951in operation.Verify correct breaker alignment and indicated power available to 3.9.5.2the required SDC pump that is not in operation.At least one shutdown cooling train shall be verified to be in -4.9.8.2operation and circulating reactor coolant at a flow rate of greaterthan or equal to 4000 gpm.Verify corefu belnwater alinevens2 t. abov idcthed tpofe rvilbeator 3.9.6.12..1.The water level shall be determined to be at least its minimum ---4.9.10.2required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at leastonce per thereafter during movement of CEAs.The saturation margin shall be determined to be within the above 4.10.5.1limits by continuous monitoring with the saturation marginmonitors required by Table 3.3-10 or, by calculating thesaturation margin.The quantity of radioactive material contained in each gas 4.11.2.6storage tank on-service shall be determined to be within theabove limit until the quantity exceeds 4.25 x 104 curies noblegases (50% of allowed limit) and then at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />swhen radioactive materials are being added to the tank. Tanksisolated for decay will be sampled to verify above limit is metwithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following removal from service.