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{{Adams
#REDIRECT [[L-2014-266, Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229]]
| number = ML14252A228
| issue date = 08/29/2014
| title = Turkey Point, Units 3 and 4 - Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229
| author name = Kiley M
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000250, 05000251
| license number = DPR-031, DPR-051
| contact person =
| case reference number = L-2014-266
| document type = Letter
| page count = 18
}}
 
=Text=
{{#Wiki_filter:0FPL.L-2014-26610 CFR 50.90August 29, 2014U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555-0001Re: Turkey Point Nuclear Plant, Units 3 and 4Docket Nos. 50-250 and 50-251Renewed Facility Operating Licenses DPR-31 and DPR-41Response to NRC Technical Specifications Branch Request for Additional Informationregarding License Amendment Request No. LAR-229, "Application for TechnicalSpecification Change Regarding Risk-Informed Justifications for the Relocation of SpecificSurveillance Frequency Requirements to a Licensee Controlled Program"
 
==References:==
1)M. Kiley (FPL) letter (L-2014-033) to NRC Document Control Desk, "LicenseAmendment Request No. LAR-229 Application for Technical Specification ChangeRegarding Risk-Informed Justifications for the Relocation of Specific SurveillanceFrequency Requirements to a Licensee Controlled Program," dated April 9, 2014(ADAMS Accession No. ML14105A042).2) A. Klett (NRC) letter to M. Nazar (FPL), "Turkey Point Nuclear Generating UnitNos. 3 and 4 -Request for Additional Information on license amendment request torevise technical specifications to implement TSTF-425, Revision 3, 'RelocateSurveillance Frequencies to Licensee Control -Risk Informed TechnicalSpecifications Task Force (RITSTF) Initiative 5B' (TAC Nos. MF3931 and MF3932),"dated August 7, 2014 (ADAMS Accession No. ML14212A713).By letter dated April 9, 2014 (Reference 1), Florida Power & Light Company (FPL) submitted alicense amendment request (LAR) to Renewed Facility Operating License Nos. DPR-31 andDPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4. The proposed amendments wouldrevise the Technical Specifications (TS) to implement Technical Specifications Task Force (TSTF)Traveler 425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control-Risk InformedTechnical Specifications Task Force (RITSTF) Initiative 5B."By letter dated August 7, 2014 (Reference 2), the NRC Technical Specifications Branch submitteda request for additional information (RAI) related to the proposed LAR. The responses to the fourquestions in the RAI are provided in Attachment 1. Attachment 2 contains revised TS marked uppages that support the responses to the RAI (LAR Attachment 3). Attachment 3 contains revisedpages to LAR Attachment 6, "Cross-Reference Between TSTF-425 and Turkey Point TechnicalSpecifications."Florida Power &Light Company o 199760 SW 344t' Street, Florida City, Florida 33035 Fl..
Turkey Point Units 3 and 4 L-2014-266Docket Nos. 50-250 and 50-251 Page 2 of 2This submittal does not alter the no significant hazards consideration or environmental assessmentpreviously submitted by FPL in Reference 1.This submittal contains no new commitments or revisions to existing commitments.The Turkey Point Nuclear Safety Committee has reviewed and approved this response to thelicense amendment application. In accordance with 10 CFR 50.91 (b)(1), a copy of this letter isbeing forwarded to the designated State of Florida official.Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto,Licensing Manager, at (305) 246-7327.I declare under penalty of perjury that the foregoing is true and accurate.Executed on the 29 day of 45'4 2014.Very truly yours,Michael KileySite Vice PresidentTurkey Point Nuclear PlantAttachments (3)cc: USNRC Regional Administrator, Region IIUSNRC Project Manager, Turkey Point Nuclear PlantUSNRC Senior Resident Inspector, Turkey Point Nuclear PlantMs Cindy Becker, Florida Department of Health Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-266Attachment 1Page 1 of 6Attachment ITurkey Point Nuclear PlantUnit Nos. 3 and 4License Amendment Request No. LAR-229Response to Request for Additional Information Turkey Point Units 3 and 4 L-2014-266Docket Nos. 50-250 and 50-251 Attachment 1Page 2 of 6Response to Request for Additional InformationThe following information is provided by Florida Power & Light Company (FPL) in response to theU.S. Nuclear Regulatory Commission's (NRC) Request for Additional Information. The informationwas requested to support the review of License Amendment Request (LAR)-229, "Application forTechnical Specification Change Regarding Risk-Informed Justifications for the Relocation ofSpecific Surveillance Frequency Requirements to a Licensee Controlled Program." LAR-229 wassubmitted to the NRC by FPL letter L-2014-033 dated April 9, 2014 (ADAMS Accession No.ML14105A042).By letter from NRC (A. Klett) to FPL (M. Nazar), dated August 7,2014 (ADAMS Accession No.ML14212A713), the NRC Technical Specifications Branch provided a request for additionalinformation (RAI). The RAI consisted of four questions. The responses to the questions areprovided below. Revised marked-up Technical Specifications pages are provided in Attachment 2.Revised pages for LAR Attachment 6, "Cross-Reference Between TSTF-425 and Turkey PointTechnical Specifications" are provided in Attachment 3.STSB RAI-1The licensee proposed to replace specific surveillance frequencies in Technical Specifications(TSs) Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6, and 4.4-3 with "SFCP." However, Florida Power &Light did not incorporate what the acronym "SFCP" stands for in the proposed TSs.Please provide a proposed change to TSs Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6, and 4.4-3 that isconsistent with Technical Specification Task Force (TSTF)-425 and clearly states that SFCPstands for the surveillance frequency control program in the Turkey Point TSs.For examples, review NRC-approved license amendment requests for Surry Power Station Units 1and 2, Hope Creek Generating Station Unit 1, and Salem Nuclear Generating Station Units 1 and 2(Agencywide Documents Access and Management System Accession Nos. ML1 10740033,ML103410243, and ML110410691, respectively).FPL ResponseFPL reviewed the license amendment requests identified above, and also reviewed the recentlyapproved Seabrook license amendment, dated July 24, 2014 (ADAMS Accession No.ML13212A069). This proposed change is consistent the Seabrook license amendment.FPL revised TS Table 1.1, "Frequency Notation" to include the definition for SFCP. SFCP isdefined as "In accordance with the Surveillance Frequency Control Program." With SFCP definedin Table 1.1, Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6 and 4.4-3 are unchanged. A marked-up TSpage for Table 1.1 is provided in Attachment 2.STSB RAI-2Surveillance Requirement (SR) 4.2.1.1.b requires monitoring and logging the indicated Axial FluxDifference (AFD) for each operable excore channel at least once per hour for the first 24 hours and Turkey Point Units 3 and 4 L-2014-266Docket Nos. 50-250 and 50-251 Attachment 1Page 3 of 6at least once per 30 minutes thereafter, when the alarm used to monitor the AFD is inoperable.The licensee proposes to delete, "at least once per" from SR 4.2.1.1.b. After the deletion, SR4.2.1.1.b requires monitoring and logging the indicated AFD for each operable excore channel hourfor the first 24 hours and at least once per 30 minutes thereafter, when the alarm used to monitorthe AFD is inoperable. The phrasing of the proposed SR is incoherent.Please provide a proposed change to Turkey Point SR 4.2.1.1 .b that is coherent and consistentwith TSTF-425.FPL ResponseFPL did not intend to change TS surveillance requirement 4.2.1.1.b. The deletion was an editorialerror and unintended. SR 4.2.1.1.b is unchanged by this license amendment request.A revised marked-up TS page without the deletion and an unchanged SR 4.2.1 .1 .b is provided inAttachment 2.STSB RAI-3Surveillance requirement 4.2.4.1 currently states:The quadrant power tilt ratio shall be determined to be within the limit above 50%of rated thermal power by:a. Calculating the ratio at least once per 7 days when the power range upper detector highflux deviation and power range lower detector high flux deviation alarms are operable, andb. Calculating the ratio at least once per 12 hours during steady-state operation when eitheralarm is inoperable.The licensee proposes to change SR 4.2.4.1 to (added wording is in italic font):The quadrant power tilt ratio shall be determined to be within the limit above 50%of rated thermal power:a. In accordance with the Surveillance Frequency Control Program by calculating the ratiowhen the power range upper detector high flux deviation and power range lower detectorhigh flux deviation alarms are operable in accordance with the Surveillance FrequencyControl Program, andb. By calculating the ratio at least once per 12 hours during steady-state operation wheneither alarm is inoperable.The proposed surveillance requirement 4.2.4.1 has added duplicate wording.Explain the need for the duplicate wording, or provide a change to SR 4.2.4.1 that does not haveduplicate wording.
Turkey Point Units 3 and 4 L-2014-266Docket Nos. 50-250 and 50-251 Attachment 1Page 4 of 6FPL ResponseFPL amended this SR 4.2.4.1 in its final version for clarity. The surveillance frequency wasrelocated to the beginning of the sentence. An editorial error resulted in the second requiredchange "Insert 1" being left in the markup. The second change "Insert 1" is deleted.A revised marked-up TS page without the second insertion for surveillance requirement 4.2.4.1 isprovided in Attachment 2. Note that the revised marked-up page incorporates TS Amendment260/255 which revised the page number from 3/4 2-15 to 3/4 2-13.SR 4.2.4.1.a now statesa. In accordance with the Surveillance Frequency Control Program by calculating theratio when the Power Range Upper Detector High Flux Deviation and Power RangeLower Detector High Flux Deviation Alarms are OPERABLE, andSTSB RAI-4Surveillance requirement 4.5.2.b currently states:Each ECCS component and flow path shall be demonstrated operable:b. At least once per 31 days by:.3) Verifying that each RHR Pump develops the indicated differentialpressure applicable to the operating conditions in accordance withFigure 3.5-1 when tested pursuant to Specification 4.0.5.Surveillance requirement 4.8.1.1.2.1.2 currently states:At least once per 10 years by:.2) For Unit 4 only, performing a pressure test of those portions of the dieselfuel oil system designed to Section III, subsection ND of the ASME Codein accordance with Section Xl of the ASME Boiler and Pressure VesselCode and applicable Addenda.The licensee proposes to change SR 4.5.2.b to (new wording is in italic font):Each ECCS component and flow path shall be demonstrated operable:b. In accordance with the Surveillance Frequency Control Program by:.3) Verifying that each RHR Pump develops the indicateddifferential pressure applicable to the operating conditions inaccordance with Figure 3.5-1 when tested pursuant toSpecification 4.0.5.
Turkey Point Units 3 and 4 L-2014-266Docket Nos. 50-250 and 50-251 Attachment 1Page 5 of 6The licensee proposes to change SR 4.8.1.1.2.1.2 to (new wording is in italic font):In accordance with the Surveillance Frequency Control Program by:.2) For Unit 4 only, performing a pressure test of those portions of the dieselfuel oil system designed to Section III, subsection ND of the ASME Codein accordance with Section Xl of the ASME Boiler and Pressure VesselCode and applicable Addenda.Turkey Point TS 4.0.5 addresses SRs for inservice inspection and testing of ASME Code Class 1,2, and 3 components.The NRC staff model safety evaluation for TSTF-425 states that all surveillance frequencies canbe relocated except for frequencies that reference other approved programs for the specific interval(such as the Inservice Testing Program or the Primary Containment Leakage Rate TestingProgram).The licensee's proposed change to SRs 4.5.2.b and 4.8.1.1.2.1.2 applies the surveillance frequencycontrol program to inservice inspection and testing of American Society of Mechanical Engineers(ASME) Code Class 1, 2, and 3 components; this is not allowed.Please explain the proposed change, remove the proposed change to SRs 4.5.2.b and4.8.1.1.2.1.2, or provide a change to SRs 4.5.2.b and 4.8.1.1.2.1.2 that does not apply thesurveillance frequency control program to inservice inspection and testing of ASME Code Class 1,2, and 3 components.FPL ResponseSurveillance requirements 4.5.2.b and 4.8.1.1.2.1 contained multiple surveillance requirements.When revising surveillance requirements 4.5.2.b and 4.8.1.1.2.1, FPL inadvertently includedsurveillance requirements 4.5.2.b.3) and 4.8.1.1.2.1.2 into the surveillance frequency controlprogram. FPL has revised the changes such that 4.5.2.b.3) and 4.8.1.1.2.1.2 are tested at thecurrently required frequency in accordance with Specification 4.0.5 and are not included in theSurveillance Frequency Control Program.SR 4.5.2.b.3) now states:.3) At least once per 31 days by verifying that each RHR Pump develops theindicated differential pressure applicable to the operating conditions inaccordance with Figure 3.5-1 when tested pursuant to Specification4.0.5.SR 4.8.1.1.2.1.2 now states:.2) At least once per 10 years, for Unit 4 only, performing a pressure test ofthose portions of the diesel fuel oil system designed to Section Il1,subsection ND of the ASME Code in accordance with Section Xl of theASME Boiler and Pressure Vessel Code and applicable Addenda.
Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-266Attachment 1Page 6 of 6Revised marked-up TS pages for these surveillance requirements are provided in Attachment 2.Note that the revised marked-up page for SR 4.8.1.1.2.1.2 incorporates TS Amendment 260/255which revised the page number from 3/4 8-9 to 3/4 8-10.
Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-266Attachment 2Attachment 2Turkey Point Nuclear PlantUnit Nos. 3 and 4License Amendment Request No. LAR-229Marked-Up Technical Specifications Pages(This coversheet plus 6 pages)
Insert 1Note that Insert I capitalization and punctuation is varied basedon the use in each specific surveillance requirement.In accordance with the Surveillance Frequency Control Program TABLE 1.1FREQUENCY NOTATIONNOTATIONSDWMQSARS/UN.A.PFREQUENCYAt least once per 12 hours.At least once per 24 hours.At least once per 7 days.At least once per 31 days.At least once per 92 days.At least once per 184 days.At least once per 18 months.Prior to each reactor startup.Not applicable.Completed prior to each release.In accordance with the SurveillanceFrequency Control Program ITURKEY POINT -UNITS 3 & 41-7AMENDMENT NOS. "ST"AND 132-POWER DISTRIBUTION LIMITSSURVEILL ANCEF REQUIREMENTS4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% oRATED THERMAL POWER by: "1"a. Monitoring the indicated AFD for each OPERABLE excore channel:1) ' k =8t G..= POF 7 days when the alarm used to monitor the AFD is OPERABLE, and2) At least once per hour for the first 6 hours after restoring the alarm used to monitor the,,t a I AFD to OPERABLE status.*b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once perhour for the first 24 hours and at least once per 30 minutes thereafter, when the alarm used tomonitor the AFD is inoperable. The logged values of the indicated AFD shall be assumed to existduring the interval preceding each logging.4.2.1. The target flux difference of each OPERABLE excore channel shall be determined by measurement at-e ,ast 92 Effect Full. , ,w. B;,y. The provisions of Specification 4.0.4 are not applicable.4.2.1.3 target flux difference shall be updated at le;at ..m,. pr. 31, Eff.,' Full ,..w.r Boy; by eitherdetermi g the target flux difference pursuant to Specification 4.2.1.2 above or by linear interpolation between ><the mo recently measured value and the predicted value at the end of the cycle life. The provisions ofSpeci ation 4.0.4 are not applicable.In accordance with theSurveillance FrequencyControl Program, the* Performance of a functional test to demonstrate OPERABILITY of the alarm used to monitor the AFD may besubstituted for this requirement.TURKEY POINT -UNITS 3 & 43/4 2-2AMENDMENT NOS. 1-6 and +50 POWER DISTRIBUTION LIMITSLIMITING CONDITION FOR OPERATION (Continued)ACTION (Continued)2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2hours and reduce the Power Range Neutron Flux-High Trip Setpoints to less than orequal to 55% of RATED THERMAL POWER within the next 4 hours; and3. Identify and correct the cause of the out-of -limit condition prior to increasing THERMALPOWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWERmay proceed provided that the QUADRANT POWER TILT RATIO is verified within itslimit at least once per hour for 12 hours or until verified at 95% or greater RATEDTHERMAL POWER.d. The provisions of Specifications 3.0.4 are not applicable.SURVEILLANCE REQUIREMENTS4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATEDTHERMAL POWER "y:a. Galekle"e the ratio at least e,,e per 7 days when the Power Range Upper Detector High Fluxa. ratio at ',eas=t onepr1 ordrn taysat prto hnihraamiZDeviation and Power Range Lower Detector High Flux Deviation Alarms are OPERABLE, andCs',cthe ratio at least once per 12 hours during steady-state operation when either alarm is~~~~~i~noperae.Bcacltn4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% ofRATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors toconfirm that the normalized symmetric power distribution, obtained either from two sets of four symmetric thimblelocations or full-core flux map, or by incore thermocouple map is consistent with the indicated QUADRANTPOWER TILT RATIO at least once per 12 hours.4.2.4.3 If the QUADRANT POWER TILT RATIO is not within its limit within 24 hours and the POWERDISTRIBUTION LIMITS of 3.2.2 and 3.2.3 are within their limits, a Special Report in accordance with 6.9.2 shallbe submitted within 30 days including an evaluation of the cause of the discrepancy.In accordance with theSurveillanceFrequency ControlProgram by calculatingTURKEY POINT -UNITS 3 & 43/4 2-13AMENDMENT NOS. 260-AND 266 EMERGENCY CORE COOLING SYSTEMSSURVEILLANCE REQUIREMENTS4.5.2 Each ECCS component and flow path shall be demonstrated OPERABLE:a. .A4t l6c-.t n-o-e pcr 12 by verifying by control room indication that the following valves are in theindiced positions with power to the valve operators removed:Valve Nu ber Valve Function Valve Position864A a B Supply from RWST to ECCS Open862A nd B RWST Supply to RHR pumps Open863 and B RHR Recirculation Closed8A and B H.H.S.I. to Hot Legs ClosedCV-758* RHR HX Outlet OpenTo permit temporary operation of these valves for surveillance or maintenance purposes, power may berestored to these valves for a period not to exceed 24 hours.b. At least ene per 31, days by:r 1) ',Verifying that the ECCS piping is full of water by venting the ECCS pump casings and-accessible discharge piping,Insert 12) erifying that each valve (manual, power-operated, or automatic) in the flow path that is notIt least once locked, sealed, or otherwise secured in position, is in its correct position, ander 31 days, 3)I that each RHR Pump develops the indicated differential pressure applicable to they verifying operating conditions in accordance with Figure 3.5-1 when tested pursuant toSpecification 4.0.5.c. Atd leat p days by:EInsert 1 I 1) Verifying that each SI pump develops the indicated differential pressure applicable to theI I operating conditions when tested pursuant to Specification 4.0.5.SI pump _ 1083 psid at a metered flowrate > 300 gpm (normal alignment or Unit 4 SI pumpsaligned to Unit 3 RWST), or_ 1113 psid at a metered flowrate 2! 280 gpm (Unit 3 SI pumps aligned to Unit 4RWST).*Air Supply to HCV-758 shall be verified shut off and sealed closed once per 31 days.TURKEY POINT -UNITS 3 & 43/4 5-5AMENDMENT NOS. AND 1"85-ELECTRICAL POWER SYSTEMSSURVEILLANCE REQUIREMENTS (Cohtnuedl-h.r after any modifications which could affect diesel generator&deg; interdependence by starting all required diesel generators simultaneously and verifying/ that all required diesel generators provide 60 + 0.6 Hz frequency and 3950-4350 volts inless than or equal to 15 seconds: andAt leat eme pe 10 yars by-.each fuel oil storage tank, removing the accumulated sediment andI1nsert 1 cleaning the tank.*2) _-y-Unit 4 only, performing a pressure test of those portions of the diesel fuel oilAt ls system designed to Section III, subsection ND of the ASME Code in accordanceAt least once per with Section Xl of the ASME Boiler and Pressure Vessel Code and applicableI10 years, for lAddenda.4.8.1.1.3ReDorts -(Not Used)* A temporary Class III fuel storage system containing a minimum volume of 38,000 gallons of fuel oil may beused for up to 10 days during the performance of Surveillance Requirement 4.8.1.1.2i.1 for the Unit 3 storage tankwhile Unit 3 is in Modes 5, 6, or defueled. If the diesel fuel oil storage tank is not returned to service within10 days, Technical Specification 3.8.1.1 Action b and 3.8.1.2 Action apply to Unit 4 and Unit 3 respectively.TURKEY POINT -UNITS 3 & 4 3/48-10 AMENDMENT NOS. 26e AND Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-266Attachment 3Attachment 3Turkey Point Nuclear PlantUnit Nos. 3 and 4License Amendment Request No. LAR-229Cross-Reference Between TSTF-425 andTurkey Point Technical Specifications(This coversheet plus 2 pages)
Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-033Attachment 6I TSTF-425 Turkey PointSurveillance Requirements Surveillance SurveillanceRequirement Requirement3.4.15, RCS Leakage Detection InstrumentationPerform Channel Check -containment atmosphere SR 3.4.15.1radioactivity monitor 4.4.6.1,Perform Channel Operational Test -containment atmosphere SR 3.4.15.2 Table 4.3-3radioactivity monitorPerform Channel Calibration -containment sump monitor SR 3.4.15.3 4.4.6.1.bPerform Channel Calibration -containment atmosphere SR 3.4.15.4 4.4.6.1,radioactivity monitor Table 4.3-3Perform Channel Operational Test -containment air cooler SR 3.4.15.5condensate flow rate monitor3.4.16, RCS Specific ActivityDetermine gross specific activity SR 3.4.16.1 4.4.8, Table 4.4-4Determine Dose Equivalent 1-131 SR 3.4.16.2 4.4.8, Table 4.4-4Determine E-Bar SR 3.4.16.3 ..Tritium determination ----- 4.4.8, Table 4.4-4Determine Dose Equivalent XE-133 ----- 4.4.8, Table 4.4-43.4.17, RCS Loop Isolation ValvesVerify valves open, SR 3.4.17.1C43.4.19, RCS Loops -Test ExceptionsSR341 .V erify Therm al Pow er >: P-7 .-SR 3 ..9 .--...TURKEY POINT TECHNICAL SPECIFICATIONS314.4.7, ChemistryDissolved oxygen, Chloride, Fluoride L ... 4.4.7, Table 4.4-33/4.4.9.2, RCS VentsVerify vent path 4.4.113.5 Emergency Core Cooling Systems (ECCS)3.5.1, AccumulatorsVerify isolation valve open SR 3.5.1.1 4.5.1.1.a.3Verify water volume SR 3.5.1.2 4.5.1.1.a.1Verify nitrogen cover pressure SR 3.5.1.3 4.5.1.1.a.2Verify boron concentration SR 3.5.1.4 4.5.1.1.bVerify power removed from isolation valve operator SR 3.5.1.5 4.5.1.1.cCheck valve operability .... 4.5.1.1.d3.5.2, ECCS -OperatingVerify valve positions with power removed SR 3.5.2.1 4.5.2.aVerify flow path valve positions SR 3.5.2.2 4.5.2.b.2Verify piping full of water SR 3.5.2.3 4.5.2.b.1Verify valve automatic actuations SR 3.5.2.5 4.5.2.f.1Verify automatic pump starts SR 3.5.2.6 4.5.2.f.2.a4.5.2.f.2.bVerify throttle valve positions SR 3.5.2.7 4.5.21g.2Inspect containment sump suction inlets SR 3.5.2.8 4.5.2.e.3Page 8 of 13 Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251L-2014-033Attachment 6TSTF-425 Turkey PointSurveillance Requirements Surveillance SurveillanceRequirement RequirementOperate pumps ----- 4.7.1.6.2Feed steam generators with pumps .... 4.7.1.6.3Operate diesel driven pump --- 4.7.1.6.4.aDiesel inspection .... 4.7.1.6.4.b3/4.7.7, Sealed Source ContaminationTest sources in use .... 4.7.7.2.a3.8 Electrical Power Systems3.8.1, AC SourcesVerify correct breaker alignment and indicated power SR 3.8.1.1 4.8.1.1.1.a4.8.1.1.2.a.6Verify starts from standby conditions SR 3.8.1.2 4.8.1.1.2.a.4Verify DG is synchronized and loaded SR 3.8.1.3 4.8.1.1.2.a.5Verify day tank volume SR 3.8.1.4 4.8.1.1.2.a.1Check for and remove accumulated water SR 3.8.1.5 4.8.1.1.2.cVerify fuel oil transfer system operates SR 3.8.1.6 4.8.1.1.2.bVerify diesel starts from standby condition SR 3.8.1.7 4.8.1.1.2.a.4Verify transfer of AC power sources SR 3.8.1.8 4.8.1.1.1 .bVerify DG rejects a load SR 3.8.1.9 4.8.1.1.2.g.2Verify DG does not trip on load rejection SR 3.8.1.10 4.8.1.1.2.g.3Verify on a loss of power signal SR 3.8.1.11 4.8.1.1.2.g.4Verify on an ESF actuation signal SR 3.8.1.12 4.8.1.1.2.g.5Verify DG's noncritical automatic trips are bypassed SR 3.8.1.13Verify DG operates for > 24 hours SR 3.8.1.14 4.8.1.1.2.g.7Verify DG state voltage and frequency SR 3.8.1.15 4.8.1.1.2.g.7Verify DG synchronizes SR 3.8.1.16 4.8.1.1.2.g.9Verify ESF overrides test mode SR 3.8.1.17 4.8.1.1.2.g.10Verify interval between each sequenced load block. SR 3.8.1.18 4.8.1.1.2.g.12Verify on LOOP with an ESF SR 3.8.1.19 4.8.1.1.2.g.6Verify simultaneously start SR 3.8.1.20 4.8.1.1.2.hVerify auto-connected loads .... 4.8.1.1.2.g.8Verify fuel oil transfer pump transfers oil 4.8.1.1.2.g. 11Verify DG lockout relay A 4.8.1.1.2.g.13Clean fuel oil storage tank 4.8.1.1.2.1.13.8.3, Diesel Fuel Oil, Lube Oil, and Starting AirVerify fuel oil storage tank volume SR 3.8.3.1 4.8.1.1.2.a.2Verify lubricating oil inventory SR 3.8.3.2 4.8.1.1.2.a.3Verify DG air start receiver pressure SR 3.8.3.4 ....Check for and remove accumulated water SR 3.8.3.5 4.8.1.1.2.d3.8.4, DC Sources -OperatingVerify battery terminal voltage SR 3.8.4.1 4.8.2.1.a.2Verify each battery charge supplies SR 3.8.4.2 4.8.2.1.c.3Page 12 of 13}}

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