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TAC:MF2798, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARGNRO-2013/00012, Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request2013-09-25025 September 2013 Maximum Extended Load Line Limit Analysis Plus (Mellla+), License Amendment Request Project stage: Request ML13345A1822013-12-19019 December 2013 Supplemental Information Needed for Acceptance of Licensing Action, Request to Revise Technical Specification to Allow Operation in Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Domain Project stage: Acceptance Review ML13364A2862013-12-30030 December 2013 Maximum Extended Load Mine Limit Analysis Plus (Mella+) License Amendment Request-Responses to Requests for Supplemental Information Project stage: Supplement ML14023A5802014-01-23023 January 2014 NRR E-mail Capture - Acceptance Review of Grand Guld Nuclear Station License Amendment Request Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Acceptance Review ML14037A1492014-02-0606 February 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00024, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/20142014-03-10010 March 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 2/6/2014 Project stage: Response to RAI ML14080A2722014-03-18018 March 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI ML14119A0092014-04-28028 April 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Audit Plan Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: Other ML14101A0432014-05-0808 May 2014 Request for Withholding from Public Disclosure - 12/19/2013 Affidavit Executed by L. Dolan, GE-Hitachi Nuclear Energy Americas LLC Related to Responses to Request for Supplemental Information Project stage: Other ML14101A0872014-05-0808 May 2014 Request for Withholding from Public Disclosure - 9/10/2013 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Nedc - 33612P, Revision 0 Project stage: Other ML14140A3012014-05-19019 May 2014 NRR E-mail Capture - Grand Gulf Nuclear Station, Unit 1, Request for Additional Information Regarding Maximum Load Line Limit Analysis Plus Project stage: RAI ML14211A1362014-07-30030 July 2014 NRR E-mail Capture - Grand Gulf Nuclear Station Request for Additional Information Regarding Maximun Extended Load Line Limit Plus Amendment Request Project stage: RAI GNRO-2014/00051, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/20142014-08-14014 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 7/2/2014 Project stage: Response to RAI GNRO-2014/00045, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142014-08-26026 August 2014 Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Response to RAI GNRO-2014/00064, Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/20142014-09-0404 September 2014 Superseding Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014 Project stage: Response to RAI GNRO-2014/00052, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/20142014-09-10010 September 2014 Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 7/29/2014 Project stage: Request ML14265A4222014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/25/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 3 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3842014-10-23023 October 2014 Request for Withholding from Public Disclosure - 6/19/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00045 Dated 8/26/14 Project stage: Other ML14265A3702014-10-23023 October 2014 Request for Withholding from Public Disclosure - 7/1/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00064 Dated 9/4/14 Project stage: Other ML14111A0582014-10-23023 October 2014 Request for Withholding from Public Disclosure - 3/4/14 Affidavit Executed by P. Yandow, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure to GNRO-2014/00024 Responses to Request for Additional Information Project stage: RAI ML14262A3972014-11-12012 November 2014 Request for Withholding from Public Disclosure - 7/22/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Enclosure 1 to GNRO-2014/00051 Dated 8/14/14 Project stage: Other ML14262A3722014-11-12012 November 2014 Request for Withholding from Public Disclosure - 8/20/14 Affidavit Executed by J. Harrison, GE-Hitachi Nuclear Energy Americas LLC Related to Attachment 1 to GNRO-2014/00052 Dated 9/10/14 Project stage: Other ML14260A1302014-11-25025 November 2014 April 23-25, 2014, Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Amendment Including Minimum Stable Film Boiling Temperature and Quench Model Project stage: Other GNRO-2014/00083, Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request2014-12-15015 December 2014 Traversing Incore Probe (TIP) Comparisons TIP Comparisons for Current Operating Conditions in Support of the Grand Gulf Nuclear Station (GGNS) Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request Project stage: Request GNRO-2014/00088, Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/20142015-01-20020 January 2015 Response to Item 20 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/20142015-02-0909 February 2015 Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus, Amendment Request, Dated 5/19/2014 Project stage: Request GNRO-2015/00011, Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method2015-02-18018 February 2015 Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method Project stage: Supplement ML15050A0772015-02-19019 February 2015 Request to Convert Regulatory Commitments for Time Critical Operator Actions Listed in Letter GNRO-2015/00003, Response to Item 25 Request for Additional Information Regarding Maximum Extended Load Line Limit. Project stage: Request ML15040A1262015-03-19019 March 2015 Request for Withholding Information from Public Disclosure - 10/30/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Americas LLC, Related to Attachment 1 to GNRO-2014/00088 Dated 1/20/15 (TAC MF27 Project stage: Withholding Request Acceptance ML15085A2272015-04-14014 April 2015 October 15, 2014, Onsite Audit Report Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Other ML15040A0932015-06-24024 June 2015 Request for Withholding Information from Public Disclosure-10/12/14 Affidavit Executed by James F. Harrison, GE-Hitachi Nuclear Energy Amenricas LLC Related to Attachment 1 to GNRO-2014/00083 Dated 12/15/2014 (MF2798) Project stage: Withholding Request Acceptance GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/20132015-08-14014 August 2015 Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013 Project stage: Request ML15229A2192015-08-31031 August 2015 Redacted, Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus License Amendment Request Project stage: Approval 2014-05-08
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
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GNRO-2015/00013 February19,2015 U.S.Nuclear Regulatory Commission Attn: DocumentControlDesk Washington,DC20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150 Kevin MulliganSiteVice PresidentTel.(601)437-7500
SUBJECT:
Request to convert Regulatory CommitmentsforTimeCritical Operator Actionslistedin.letter GNRO-2015/00003,"ResponsetoItem25 Request for Additional Information Regarding Maximum ExtendedLoadLineLimit Plus Amendment Request dated 5/19/2014" a License Condition Grand Gulf Nuclear'Station,Unit1 Docket No.50-416 License No.NPF-29
REFERENCES:
1.EntergyLetter,"MaximumExtendedLoadLineLimitAnalysisPlus(MELLLA+)LicenseAmendmentRequest,"GNRO-2013/00012,dated September 25,2013(ADAMSAccessionNo.ML13269A140).2.EntergyLetter,"ResponsetoItem25RequestforAdditionalInformationRegarding"MaximumExtendedLoadLineLimitPlusAmendmentRequest",GNRO-2015/00003,dated2/9/15.
DearSirorMadam:
In Reference 2 Entergy Operations Inc.(Entergy)submitted a responsetoanRAI generatedfromthe Staff's reviewofthe MELLLA+LARin Reference1fortheGrand Gulf Nuclear Station(GGNS),Unit1.Duringthe Staff'sreviewoftheRAI Response in Reference2,which included Commitments to train operatingcrewsonthe MELLLA+TimeCritical Operator Actionsandtoreportresultsof the trainingtothe Nuclear Regulatory Commission(NRC),the Staff identifiedtheneedto convert the commitmentstoa License Condition.
As discussed,Entergyproposedtoinclude the commitmentswiththe currentlistingof License Conditions.
CurrentlytheGGNS Operating Licensehas39 conditionsonpages4 through16ofthe document.Entergy proposestoaddanew conditionlistingthetimecritical operator actionstrainingandreporting requiredforthe MELLLA+LAR.The proposed changestothe Operating License are attachedtothisletter.
GNRO-2015/00013Page2of2Ifyouhaveany questionsorrequire additional information, please contactJamesNadeauat601-437-2103.
I declare underpenaltyofperjurythatthe foregoingistrueandcorrect.
Executedonthe19thdayofFebruary,2015.
Sincerely, KJM/ras
Attachment:
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Proposed License Condition u.S.Nuclear Regulatory CommissionATTN:Mr.A.Wang, NRRlDORLMailStop OWFN/8 G1411555RockvillePikeRockville,MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear StationPortGibson,MS39150u.S.Nuclear Regulatory CommissionATTN:Marc L.Dapas(w/2)
Regional Administrator,RegionIV1600EastLamar BoulevardArlington,TX76011-4511 AttachmenttoGNRO-2015/00013 Proposed License Condition GNRO-2015/00013 AttachmentProposedLicense ConditionTimeCritical Operator Action Commitmentsmadeasrequiredforthe MELLLA+LARwillbe convertedtoa License Conditionasfollows:PriortoOperationinthe MELLLA+Domain, Entergy will:Trainallactiveoperatingcrewstoperformthefollowingthree MELLLA+time-critical operator actions:1.InitiateReactorWaterLevel Reduction(90secondsfollowingfailuretoscram concurrentwithnoreactor recirculationpumpsinserviceandCTP
>50/0).2.InitiateStandbyLiquidControl Injection(300seconds if CTP>5%orbefore Suppression Pool Temperaturereaches110degreesF).3.InitiateResidualHeatRemoval SuppressionPoolCooling(660seconds).GGNSwill validatethatallactive operatingcrewshavemet thetime requirements forthethree MELLLA+time-critical operatoractionsduring evaluated scenarios.GGNSwillreportany MELLLA+time-critical actionsthatare converted to"immediateactions"totheNRCProjectManager.Thefollowingare one-time actionswhichexpire afterthefirstreport:Theresultsofthethree MELLLA+time-critical operatoractionstrainingwillbereportedtotheNRC Project Managerwithin60daysof completionofthetraining.Thereportedresultswillincludethefullrangeof responsetimesforeach time-criticalactionandthe average timesforeachcrew.
Any MELLLA+time-critical operator training failures during evaluated scenarioswillbereportedtotheNRCwithin60daysofany failureswithaplanforresolution.
(h)This license condition shall expire upon satisfaction of the requirements in paragraph (f)provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is caused by fatigue.(48)Time Critical Operator Action Commitments made as required for the MELLA+LAR will be converted to a License Condition as follows: Prior to Operation in the MELLA+Domain, Entergy will: Train all active operating crews to perform the following three MELLA+time-critical operator actions: 1.Initiate Reactor Water Level Reduction (90 seconds following failure to scram concurrent with no reactor recirculation pumps in service and CTP>5%).2.Initiate Standby Liquid Control Injection (300 seconds if CTP>5%or before Suppression Pool Temperature reaches 110 degrees F).3.Initiate Residual Heat Removal Suppression Pool Cooling (660 seconds).GGNS will validate that all active operating crews have met the time requirements for the three MELLA+time-critical operator actions during evaluated scenarios.
GGNS will report any MELLA+time-critical actions that are converted to"immediate actions" to the NRC Project Manager.The following are one-time actions which expire after the first report: The results of the three MELLA+time-critical operator actions training will be reported to the NRC Project Manager within 60 days of completion of the training.The reported results will include the full range of response times for each time-critical action and the average times for each crew.Any MELLA+time-critical operator training failures during evaluated scenarios will be reported to the NRC within 60 days of any failures with a plan for resolution.
D.The facility required exemptions from certain requirements of Appendices A and J to 10 CFR Part 50 and from certain requirements of10CFR Part 100.These include: (a)exemption from General Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1)the emergency override oftest mode for the Division 3 diesel engine, (2)the second level undervoltage protection for the Division 3 diesel engine, and (3)the generator ground over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSER#7)and (b)exemption from the requirements of Paragraph III.D.2(b)(ii)of Appendix J for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER#7).These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.In addition, by exemption dated December 20, 1986, the Commission exempted licensees from 10 CFR 100.11(a)(1), insofar as it incorporates the definition of exclusion area in10CFR 100.3(a), until April 30, 1987 regarding demonstration of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No.27 to License (NPF-29).This exemption is 16f Amendment No.++G,+78,+8&-1-9-1-,
authorized by law, and will not present an undue risk to the public health and safety, and is consistent with the common defense and security.In addition, special circumstances have been found justifying the exemption.
Therefore, these exemptions are hereby granted pursuant to10CFR 50.12.with the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act and the rules and regulations of the Commission.
E.The licensee shall fully implement and maintain in effect all provision of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)and to the authority of10CFR 50.90 and 10 CFR 50.54(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security, Safeguards Contingency and Training and Qualification Plan," and were submitted to the NRC on May 18, 2006.The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and10CFR 50.54(p).The licensee's CSP was approved by License Amendment No.186 as supplemented by a change approved by License Amendment No.192 and 200.16g Amendment No.