ML23188A040
| ML23188A040 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/08/2023 |
| From: | Joel Wiebe NRC/NRR/DORL/LPL3, Plant Licensing Branch 1 |
| To: | Rhoades D Constellation Energy Generation |
| Goetz, S | |
| References | |
| EPID L-2022-LLA-0115 | |
| Download: ML23188A040 (24) | |
Text
August 8, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 346 AND 324 RE: ADOPTION OF TSTF-577, REVISED FREQUENCIES FOR STEAM GENERATOR TUBE INSPECTIONS, REVISION 1 (EPID L-2022-LLA-0115)
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 346 to Renewed Facility Operating License No. DPR-53 and Amendment No. 324 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2. These amendments consist of changes to the technical specifications in response to your application transmitted by letter dated August 10, 2022, as supplemented by letters dated December 7, 2022, and May 22, 2023. The amendments for other plants included in your letter dated August 10, 2022, will be issued under separate cover.
These amendments revise the Steam Generator (SG) Program and the Steam Generator (SG) Tube Inspection Report technical specifications based on Technical Specifications Task Force (TSTF) Traveler TSTF 577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (TSTF 577), and the associated NRC staff safety evaluation of TSTF 577.
D. Rhoades A copy of our related safety evaluation is enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 346 to DPR-53
- 2. Amendment No. 324 to DPR-69
- 3. Safety Evaluation
- 4. Notices and Environmental Findings cc: Listserv CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 346 Renewed License No. DPR-53 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (CEG, the licensee) dated August 10, 2022, as supplemented by letters dated December 7, 2022, and May 22, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 346, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 8, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.08 15:22:04 -04'00' CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 324 Renewed License No. DPR-69 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC (CEG, the licensee) dated August 10, 2022, as supplemented by letters dated December 7, 2022, and May 22, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 324, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 120 days.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 8, 2023 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2023.08.08 15:22:40 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 346 AND 324 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 RENEWED FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Insert License DPR-53 License DPR-53 Page 3 Page 3 License DPR-69 License DPR-69 Page 3 Page 3 TSs TSs Page 5.5-6 Page 5.5-6 Page 5.5-7 Page 5.5-7 Page 5.5-8 Page 5.5-8 Page 5.5-9 Page 5.5-9 Page 5.5-10 Page 5.5-10 Page 5.6-6 Page 5.6-6 Page 5.6-7 Page 5.6-7 Amendment No. 346 (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 346, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
(a)
For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.
(3)
Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 345 are hereby incorporated into this license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Additional Conditions.
Amendment No. 324 (4)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 324, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
(a)
For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.
(3)
Less Than Four Pump Operation The licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.
ProgramsandManuals 5.5 5.5ProgramsandManuals CALVERTCLIFFSUNIT1 5.56 CALVERTCLIFFSUNIT2 Amendment No. 346 AmendmentNo.324 5.5.6 ConcreteContainmentTendonSurveillanceProgram Thisprogramprovidescontrolsformonitoringanytendon degradationinprestressedconcretecontainments,including effectivenessofitscorrosionprotectionmedium,toensure containmentstructuralintegrity.Theprogramshallinclude baselinemeasurementspriortoinitialoperation.TheTendon SurveillanceProgram,inspectionfrequencies,andacceptance criteriashallbeinaccordancewithSectionXI,SubsectionIWLof theASMEBoilerandPressureVesselCodeandapplicableaddendaas requiredby10CFR50.55a,asamendedbyreliefgrantedin accordancewith10CFR50.55a(a)(3).
TheprovisionsofSR3.0.3areapplicabletotheTendon SurveillancePrograminspectionfrequencies.
5.5.7 ReactorCoolantPumpFlywheelInspectionProgram Thisprogramshallprovidefortheinspectionofeachreactor coolantpumpflywheelpertherecommendationsofregulatory positionC.4.bofRegulatoryGuide1.14,Revision1,August 1975.
InlieuofRegulatoryPositionC.4.b(1)andC.4.b(2),aqualified inplaceUTexaminationoverthevolumefromtheinnerboreofthe flywheeltothecircleonehalfoftheouterradiusorasurface examination(MTand/orPT)ofexposedsurfacesoftheremoved flywheelsmaybeconductedatanintervalnottoexceed20years.
5.5.8 DELETED 5.5.9 SteamGenerator(SG)Program AnSGProgramshallbeestablishedandimplementedtoensurethat SGtubeintegrityismaintained.Inaddition,theSGProgram shallincludethefollowing:
a.
Provisionsforconditionmonitoringassessments.Condition monitoringassessmentmeansanevaluationoftheasfound conditionofthetubingwithrespecttotheperformance
ProgramsandManuals 5.5 5.5ProgramsandManuals CALVERTCLIFFSUNIT1 5.57 CALVERTCLIFFSUNIT2 Amendment No. 346 Amendment No. 324 criteriaforstructuralintegrityandaccidentinduced leakage.Theasfoundconditionreferstotheconditionof thetubingduringanSGinspectionoutage,asdeterminedfrom theinserviceinspectionresultsorbyothermeans,priorto thepluggingoftubes.Conditionmonitoringassessments shallbeconductedduringeachoutageduringwhichtheSG tubesareinspectedorpluggedtoconfirmthatthe performancecriteriaarebeingmet.
b.
PerformancecriteriaforSGtubeintegrity.SGtubeintegrity shallbemaintainedbymeetingtheperformancecriteriafor tubestructuralintegrity,accidentinducedleakage,and operationalLEAKAGE.
1.
Structuralintegrityperformancecriterion:Allin serviceSGtubesshallretainstructuralintegrityover thefullrangeofnormaloperatingconditions(including startup,operationinthepowerrange,hotstandby,and cooldown),allanticipatedtransientsincludedinthe designspecification,anddesignbasisaccidents.This includesretainingasafetyfactorof3.0againstburst undernormalsteadystatefullpoweroperationprimary tosecondarypressuredifferentialandasafetyfactor of1.4againstburstappliedtothedesignbasis accidentprimarytosecondarypressuredifferentials.
Apartfromtheaboverequirements,additionalloading conditionsassociatedwiththedesignbasisaccidents, orcombinationofaccidentsinaccordancewiththe designandlicensingbasis,shallalsobeevaluatedto determineiftheassociatedloadscontribute significantlytoburstorcollapse.Intheassessment oftubeintegrity,thoseloadsthatdosignificantly affectburstorcollapseshallbedeterminedand assessedincombinationwiththeloadsduetopressure withasafetyfactorof1.2onthecombinedprimary loadsand1.0onaxialsecondaryloads.
ProgramsandManuals 5.5 5.5ProgramsandManuals CALVERTCLIFFSUNIT1 5.58 CALVERTCLIFFSUNIT2 AmendmentNo. 346 AmendmentNo. 324 2.
Accidentinducedleakageperformancecriterion:The primarytosecondaryaccidentinducedleakageratefor anydesignbasisaccident,otherthanaSGtuberupture, shallnotexceedtheleakagerateassumedinthe accidentanalysisintermsoftotalleakagerateforall SGsandleakagerateforanindividualSG.Leakageis nottoexceed100gpdperSG.
3.
TheoperationalLEAKAGEperformancecriterionis specifiedinLCO3.4.13,RCSOperationalLEAKAGE.
c.
ProvisionsforSGtubepluggingcriteria.Tubesfoundby inserviceinspectiontocontainflawswithadepthequalto orexceeding40%ofthenominaltubewallthicknessshallbe plugged.
d.
ProvisionsforSGtubeinspections.PeriodicSGtube inspectionsshallbeperformed.Thenumberandportionsof thetubesinspectedandmethodsofinspectionshallbe performedwiththeobjectiveofdetectingflawsofanytype (e.g.,volumetricflaws,axial,andcircumferentialcracks) thatmaybepresentalongthelengthofthetube,fromthe tubetotubesheetweldatthetubeinlettothetubeto tubesheetweldatthetubeoutlet,andthatmaysatisfythe applicabletubepluggingcriteria.Thetubetotubesheet weldisnotpartofthetube.Inadditiontomeetingthe requirementsofd.1,d.2,andd.3below,theinspection scope,inspectionmethods,andinspectionintervalsshallbe suchastoensurethatSGtubeintegrityismaintaineduntil thenextSGinspection.Adegradationassessmentshallbe performedtodeterminethetypeandlocationofflawsto whichthetubesmaybesusceptibleand,basedonthis assessment,todeterminewhichinspectionmethodsneedtobe employedandatwhatlocations.
1.
Inspect100%ofthetubesineachSGduringthefirst refuelingoutagefollowingSGinstallation.
ProgramsandManuals 5.5 5.5ProgramsandManuals CALVERTCLIFFSUNIT1 5.59 CALVERTCLIFFSUNIT2 AmendmentNo. 346 AmendmentNo.324 2.
AfterthefirstrefuelingoutagefollowingSG installation,inspect100%ofthetubesineachSGat leastevery96effectivefullpowermonths,which definestheinspectionperiod.
3.
IfcrackindicationsarefoundinanySGtube,thenthe nextinspectionforeachaffectedandpotentially affectedSGforthedegradationmechanismthatcaused thecrackindicationshallbeatthenextrefueling outage.Ifdefinitiveinformation,suchasfrom examinationofapulledtube,diagnosticnondestructive testing,orengineeringevaluationindicatesthata cracklikeindicationisnotassociatedwithacrack(s),
thentheindicationneednotbetreatedasacrack.
e.
Provisionsformonitoringoperationalprimarytosecondary LEAKAGE.
ProgramsandManuals 5.5 5.5ProgramsandManuals CALVERTCLIFFSUNIT1 5.510 CALVERTCLIFFSUNIT2 AmendmentNo. 346 AmendmentNo. 324 5.5.10 SecondaryWaterChemistryProgram Thisprogramprovidescontrolsformonitoringsecondarywater chemistrytoinhibitsteamgeneratortubedegradationandlow pressureturbinediscstresscorrosioncracking.Theprogram shallinclude:
a.
Identificationofasamplingscheduleforthecritical variablesandcontrolpointsforthesevariables; b.
Identificationoftheproceduresusedtomeasurethevalues ofthecriticalvariables; c.
Identificationofprocesssamplingpointswhichshallinclude monitoringthedischargeofthecondensatepumpsforevidence ofcondenserinleakage; d.
Proceduresfortherecordingandmanagementofdata; e.
Proceduresdefiningcorrectiveactionsforalloffcontrol pointchemistryconditions;and
ReportingRequirements 5.6 5.6ReportingRequirements CALVERTCLIFFSUNIT1 5.66 CALVERTCLIFFSUNIT2 AmendmentNo. 346 AmendmentNo.324 thermalmechanicallimits,corethermalhydrauliclimits, ECCSlimits,nuclearlimitssuchasSDM,transientanalysis limits,andaccidentanalysislimits)ofthesafetyanalysis aremet.
d.
TheCOLR,includinganymidcyclerevisionsorsupplements, shallbeprovideduponissuanceforeachreloadcycletothe NRC.
5.6.6 NotUsed 5.6.7 PostAccidentMonitoringReport WhenareportisrequiredbyConditionBorFofLCO3.3.10,"Post AccidentMonitoringInstrumentation,"areportshallbesubmitted withinthefollowing14days.Thereportshalloutlinethe preplannedalternatemethodofmonitoring,thecauseofthe inoperability,andtheplansandscheduleforrestoringthe instrumentationchannelsoftheFunctiontoOPERABLEstatus.
5.6.8 TendonSurveillanceReport Anyabnormaldegradationofthecontainmentstructuredetected duringthetestsrequiredbythePreStressedConcreteContainment TendonSurveillanceProgramshallbereportedtotheNRCwithin 30days.Thereportshallincludeadescriptionofthetendon condition,theconditionoftheconcrete(especiallyattendon anchorages),theinspectionprocedures,thetoleranceson cracking,andthecorrectiveactiontaken.
5.6.9 SteamGeneratorTubeInspectionReport Areportshallbesubmittedwithin180daysaftertheinitial entryintoMODE4followingcompletionofaninspectionperformed inaccordancewiththeSpecification5.5.9,"SteamGenerator(SG)
Program."Thereportshallinclude:
ReportingRequirements 5.6 5.6ReportingRequirements CALVERTCLIFFSUNIT1 5.67 CALVERTCLIFFSUNIT2 Amendment No. 346 AmendmentNo.324 a.
ThescopeofinspectionsperformedoneachSG; b.
Thenondestructiveexaminationtechniquesutilizedfor tubeswithincreaseddegradationsusceptibility; c.
Foreachdegradationmechanismfound:
1.
Thenondestructiveexaminationtechniquesutilized; 2.
Thelocation,orientation(iflinear),measured size(ifavailable),andvoltageresponseforeach indication.Fortubewearatsupportstructures lessthan20percentthroughwall,onlythetotal numberofindicationsneedstobereported; 3.
Adescriptionoftheconditionmonitoring assessmentandresults,includingthemargintothe tubeintegrityperformancecriteriaandcomparison withthemarginpredictedtoexistatthe inspectionbythepreviousforwardlookingtube integrityassessment;and 4.
Thenumberoftubespluggedduringtheinspection outage.
d.
Ananalysissummaryofthetubeintegrityconditions predictedtoexistatthenextscheduledinspection (theforwardlookingtubeintegrityassessment) relativetotheapplicableperformancecriteria, includingtheanalysismethodology,inputs,and results; e.
Thenumberandpercentageoftubespluggedtodate,and theeffectivepluggingpercentageineachSG;and f.
TheresultsofanySGsecondarysideinspections.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 346 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CONSTELLATION ENERGY GENERATION, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 Application Safety Evaluation Date
August 10, 2022, (ML22222A068)
December 7, 2022, (ML22342B230)
May 22, 2023, (ML23143A136)
August 8, 2023 Principal Contributors to Safety Evaluation
1.0 PROPOSED CHANGE
S By letter dated August 10, 2022, as supplemented by letters dated December 7, 2022, and May 22, 2023, Constellation Energy Generation, LLC (the licensee) requested changes to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant (Calvert Cliffs), Unit Nos. 1 and 2. In its August 10, 2022, letter, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line-Item Improvement Process (CLIIP). The proposed changes would revise the Steam Generator (SG) Program and the Steam Generator Tube Inspection Report TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (TSTF-577) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577 (ML21098A188). This request was removed from the CLIIP process because of the complexity caused by not completing the required 100 percent SG tube inspections before the date of the request.
The tubes within an SG function as an integral part of the reactor coolant pressure boundary and, in addition, isolate fission products in the primary coolant from the secondary coolant and the environment. SG tube integrity means that the tubes are capable of performing this safety function in accordance with the plant design and licensing basis.
Calvert Cliffs, Unit Nos. 1 and 2, SGs have Alloy 690 thermally treated (Alloy 690TT) tubes.
1.1 Proposed TS Changes to Adopt TSTF-577 In accordance with NRC staff-approved TSTF-577, the licensee proposed changes that would revise Calvert Cliffs TS 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator Tube Inspection Report. Specifically, the licensee proposed the following changes to adopt TSTF-577:
TS 5.5.9, Steam Generator (SG) Program:
TS 5.5.9 introductory paragraph and paragraph b.1 would be revised by replacing steam generator with SG in a few instances.
TS 5.5.9.d.2 would be revised by deleting the requirement to base inspection frequency on the more restrictive metric between either the effective full power months (EFPM) or refueling outage and to use just the EFPM metric.
TS 5.5.9.d.2 would be revised by deleting the requirement to inspect 100 percent of the tubes during each period in paragraphs d.2.a, d.2.b, d.2.c, and d.2.d (144, 120, 96, and 72 EFPM, respectively) and by adding the requirement to inspect 100 percent of the tubes every 96 EFPM.
TS 5.5.9.d.2 would be revised by deleting the allowance to extend the inspection period by 3 EFPM and by deleting the discussion of prorating inspections.
TS 5.5.9.d.3 would be revised by replacing shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections) with shall be at the next refueling outage.
TS 5.6.9, Steam Generator Tube Inspection Report:
Existing reporting requirement b. would be renumbered as c. and be revised by editorial and punctuation changes.
New reporting requirement b. would be added to require the nondestructive examination (NDE) techniques utilized for tubes with increased degradation susceptibility be reported.
Existing reporting requirement c. would be renumbered as c.1. and be revised by editorial and punctuation changes.
Existing reporting requirement d. would be renumbered as c.2. and be revised to note that the location, orientation (if linear), measured size (if available), and voltage response do not need to be reported for tube wear indications at support structures that are less than 20 percent through-wall. However, the total number of tube wear indications at support structures that are less than 20 percent through-wall would be reported.
New reporting requirement d. would be added to require an analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection relative to the applicable performance criteria, including the analysis methodology, inputs, and results.
Existing reporting requirement e. would be renumbered as c.4 and be revised by editorial and punctuation changes.
Existing reporting requirement f. would be renumbered as e. and be revised by editorial and punctuation changes.
New reporting requirement f. would be added to require the results of any SG secondary side inspections be reported.
Existing reporting requirement g. would be renumbered as c.3. and be revised to add the requirements to report a description of the condition monitoring assessment, the margin to the tube integrity performance criteria, and a comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment. In addition, the requirement to report the results of tube pulls and in-situ testing would be deleted.
1.2 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in Section 1.1, the licensee identified the following variations.
1.2.1 Variations The licensee identified three variations for Calvert Cliffs. First, the Calvert Cliffs TSs use different numbering than Standard Technical Specifications (STSs) on which TSTF-577 was based. Specifically, the Steam Generator Tube Inspection Report is numbered 5.6.9 in Calvert Cliffs TSs rather than TS 5.6.7 as stated in the TSTF. Second, the Calvert Cliffs TS 5.5.9.b currently references Steam generator instead of SG. The licensee proposed to use SG, in order to be consistent with the STS on which TSTF-577 is based. Finally, Calvert Cliffs TS 5.6.9 currently does not include quotation marks around the program title, Steam Generator (SG)
Program. The licensee proposed to include quotation marks in order to be consistent with the STS on which TSTF-577 is based.
2.0 REGULATORY EVALUATION
The regulations in Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(5),
Administrative controls, state that [a]dministrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in
[10 CFR] 50.4. Technical Specification, Section 5.0, Administrative Controls, requires that an SG program be established and implemented to ensure that SG tube integrity is maintained.
Programs established by the licensee, including the SG program, are listed in the administrative controls section of the TS to operate the facility in a safe manner.
The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]
Edition (SRP), Chapter 16.0, Technical Specifications, Revision 3, dated March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-14321, as modified by NRC-approved travelers.
TSTF-577 revised the STSs related to SG tube inspections and SG tube inspection reporting requirements. The NRC approved traveler TSTF-577 under the CLIIP on April 14, 2021 (ML21099A086).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-577 The NRC staff compared the licensees proposed TS changes in Section 1.1 of this SE against the changes approved in TSTF-577. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-577 are applicable because Calvert Cliffs, Unit Nos. 1 and 2, are pressurized-water reactors (PWRs) and the NRC staff approved the TSTF-577 changes for PWRs. The NRC staff finds that the licensees proposed changes to the Calvert Cliffs, Unit Nos. 1 and 2, TSs in Section 1.1 of this SE are consistent with those found acceptable in TSTF-577.
In the SE of TSTF-577, the NRC staff concluded that the TSTF-577 changes to STS 5.5.9, Steam Generator (SG) Program, and STS 5.6.7, Steam Generator Tube Inspection Report, were acceptable because, as discussed in Section 3.0 of that SE, they continued to ensure SG tube integrity and, therefore, protected the public health and safety. In particular, the structural integrity performance criterion and accident-induced leakage performance criterion (explained in STS 5.5.9.b, items 1 and 2, respectively) will continue to be met with the proposed revised SG inspection intervals (maximum allowable time between SG inspections) and inspection periods (maximum allowable time between 100 percent of SG tubes inspections). Additionally, the proposed changes to the reporting requirements will provide more detailed and consistent information to the NRC. Therefore, the NRC staff found that the proposed changes to the SG program and inspection reporting requirements were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(5) by providing administrative controls necessary to assure operation of the facility in a safe manner. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Calvert Cliffs, Unit Nos. 1 and 2, TSs in Section 1.1 of this SE continue to meet the requirements of 10 CFR 50.36(c)(5).
3.2 Additional Proposed TS Changes 3.2.1 Variations The variations are described in Section 1.2.1 of this SE. The NRC staff finds the variations acceptable because the variations do not substantively alter TS requirements.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are therefore acceptable.
1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Combustion Engineering Plants, NUREG-1432, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21258A421 and ML21258A424, respectively).
4.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 346 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CONSTELLATION ENERGY GENERATION, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 Application Safety Evaluation Date
August 10, 2022, (ML22222A068)
December 7, 2022, (ML22342B230)
May 22, 2023, (ML23143A136)
August 8, 2023 Principal Contributors to Safety Evaluation Clinton Ashley
1.0 INTRODUCTION
By letter dated August 10, 2022, as supplemented by letters dated December 7, 2022, and May 22, 2023, Constellation Energy Generation, LLC (the licensee) requested changes to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant (Calvert Cliffs), Unit Nos. 1 and 2. In its August 10, 2022, letter, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line-Item Improvement Process (CLIIP). The proposed changes would revise the Steam Generator (SG) Program and the Steam Generator Tube Inspection Report TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (TSTF-577) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577 (ML21098A188). This request was removed from the CLIIP process because of the complexity caused by not completing the required 100 percent SG tube inspections before the date of the request.
The supplements dated December 7, 2022, and May 22, 2023, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on October 4, 2022 (87 FR 60216).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Maryland State official was notified of the proposed issuance of the amendment on June 6, 2023. The State official had no comments.
3.0 ENVIRONMENTAL CONSIDERATION
The amendment relates, in part, to changes in recordkeeping, reporting, or administrative procedures or requirements. The amendment also relates, in part, to changing requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on October 4, 2022 (87 FR 60216).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
Date of issuance: August 8, 2023
ML23188A040 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NAME JWiebe SRohrer VCusumano DATE 7/6/2023 7/11/2023 6/6/2023 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME JWhited JWiebe DATE 8/8/2023 8/8/2023