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MONTHYEARML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) JAFP-16-0110, Correction to 2014 Annual Radioactive Effluent Release Report2016-06-29029 June 2016 Correction to 2014 Annual Radioactive Effluent Release Report JAFP-16-0060, James a Fitzpatrick - Extension to Commitments Made in Response to March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3, Emergency Communication and Staffing Assessments2016-04-14014 April 2016 James a Fitzpatrick - Extension to Commitments Made in Response to March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3, Emergency Communication and Staffing Assessments ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15238B5372015-09-0404 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15229A0232015-08-13013 August 2015 Tables 1 and 2 JAFP-15-0017, J.A. Fitzpatrick - Response to Regulatory Issue Summary 2014-132015-02-0202 February 2015 J.A. Fitzpatrick - Response to Regulatory Issue Summary 2014-13 JAFP-14-0145, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-19019 December 2014 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-10-0088, Submittal of Corrections to the 2004, 2005, 2006, 2007, and 2008 Annual Radioactive Effluent Release Reports2010-07-15015 July 2010 Submittal of Corrections to the 2004, 2005, 2006, 2007, and 2008 Annual Radioactive Effluent Release Reports ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0732400092007-11-19019 November 2007 JAFNPP SEIS Web Reference - NOAA 2004b - Thunderstorms and Wind Events ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0733004352007-08-17017 August 2007 Comments from JAFNPP Regarding Safety Evaluation Report with Open Items ML0705804642007-05-25025 May 2007 Audit Summary for the JAFNPP LRA Safety Site Audits ML0701603912007-01-16016 January 2007 JAFNPP - SEIS Web Reference - Great Lakes: Lake Ontario ML0710004712006-03-0909 March 2006 Great Lakes Atlas Fact Sheet #1 ML0701602092005-12-31031 December 2005 JAFNPP - SEIS Web Reference - Schaner 2005, Pelagic Planktivores, NYSDEC Lake Ontario Annual Report 2005 ML0701603982005-12-31031 December 2005 JAFNPP - SEIS Web Reference - Mnr Fish Stocking Summary 2005 ML0535703362005-12-0505 December 2005 Geographical, Environmental and Siting Information Minority and Low Income Data, Pilgrim and FitzPatrick Sites from 2000 Census ML0529001372005-10-17017 October 2005 Transformer Data - for Information Only Press Release-I-05-039, NRC Begins Special Inspection at James A. Fitzpatrick Nuclear Plant2005-07-0707 July 2005 Press Release-I-05-039: NRC Begins Special Inspection at James A. Fitzpatrick Nuclear Plant ML0701602162004-12-31031 December 2004 JAFNPP - SEIS Web Reference - O'Gorman Et Al 2005 JAFP-04-0190, In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)2004-12-15015 December 2004 In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17) JAFP-05-0179, Enclosure 13, Calculation JAF-CALC-ELEC-02610 125VDC B Station Battery Sizing & Voltage Drop Revision 2, Appendix 4, Page 2 of 2, SBO2003-05-16016 May 2003 Enclosure 13, Calculation JAF-CALC-ELEC-02610 125VDC B Station Battery Sizing & Voltage Drop Revision 2, Appendix 4, Page 2 of 2, SBO ML0701602221999-10-31031 October 1999 JAFNPP - SEIS Web Reference - Boyd and Biberhofer 1999 2023-04-05
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 4, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST- FLOOD-CAUSING MECHANISM REEVALUATION (TAC NO. MF6106)
Dear Sir or Madam:
The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15082A250), flood hazard reevaluation report (FHRR) submitted by Entergy Nuclear Operations, Inc. (Entergy, the licensee) for James A. FitzPatrick Nuclear Power Plant (FitzPatrick), as well as supplemental information resulting from requests for additional information and audits.
By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as the 50.54(f) letter)
(ADAMS Accession No. ML12053A340). The request was issued as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A735). On March 30, 2015, the Commission provided Staff Requirements Memoranda (SRM) (ADAMS Accession No. ML15089A236) to COM-SECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events.
The NRC staff has reviewed the flood hazard information submitted by the 1.icensee and has summarized the results of the review in the tables provided as an Enclosure to this letter.
Table 1 provides the current design-basis flood hazard mechanisms. Table 2 provides the reevaluated flood hazard mechanisms; however, the reevaluated hazard mechanisms bounded by the current design-basis (Table 1) are not included.
The staff has concluded that the licensee's reevaluated flood hazards information, as summarized 1n Enclosure 1, is suitable for the assessment of mitigating strategies, developed in
response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the. industry and NRC staff) for FitzPatrick. Further, the NRC staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding". The NRC staff plans to issue a staff assessment documenting the basis for these conclusions at a later time.
In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the FitzPatrick MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA.
As stated above, Table 2 of the enclosure to this letter describes the reevaluated flood hazards that exceed the current design-basis. In order to complete its response to the information requested by Enclosure 2 to the 50.54(f) letter, the licensee is expected to submit an integrated assessment or a focused evaluation, as appropriate, to address these reevaluated flood hazards, as described in NRC letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond Design Bases External Events" (ADAMS Accession No. ML15174A257). This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML15209A682).
If you have any questions, please contact me at (301) 415-2915 or e-mail at Victor.Hall@nrc.gov.
Sincerely, Victor E. Hall, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv
ENCLOSURE:
SUMMARY
TABLES OF REEVALUATED FLOOD HAZARD LEVELS
FitzPatrick Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard Elevation Local Intense Precipitation Not included Not included Not included FHHR Table 4-1 in DB in DB in DB I i i I
I Streams and Rivers I Not included Not included Not included ! FHRR Table 4-1 in DB in DB in DB I I
i Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included FHRR Table 4-1 in DB in DB in DB Storm Surge I i
I
' Storm Surge 254.1 ft 7.9 ft 262 ft FHRR Table 4-1 I
USLS35 USLS35 Storm Surge at Screenwell 254.0 ft 1.0 ft 255 ft FHRR Table 4-1 USLS35 I USLS35 Seiche 1
Not included Not included Not included FHRR Table 4-1 in DB in DB in DB Tsunami Not included Not included I Not included I FHRR Table 4-1 in DB in DB in DB Ice-Induced Flooding Not included Not included Not included FHRR Table 4-1 in DB in DB in DB
- -- __ _I
FitzPatrick Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard Elevation Channel Migrations/Diversions Not included Not included Not included FHRR Table 4-1 in DB in DB in DB Note: Reported values are rounded to the nearest one-tenth of a foot.
FitzPatrick
,- Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Elevation I
Waves/
Run up Reevaluated Hazard Elevation Reference --
Local Intense Precipitation 272.8 ft Minimal 272.8 ft FHRR Table 4-1 and FHRR USLS35 USLS35 Appendix A Streams and Rivers Unnamed Stream 272.8 ft Not 272.8 ft FHRR Table 4-4 USLS35 applicable USLS35 Storm Surge PMSS + PMP +Waves 252.8 ft 15.2 ft 268.0 ft FHRR Sect 3.4.3 & Table 4-1 USLS35 USLS35 FHRR Table 4-1 Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.
PKG ML152388540; LTR: ML152388537; ENCL: ML15229A023 *via email OFFICE NRR/JLD/JHMB/PM* NRR/JLD/LA* NRO/DSEA/RHM2/TR* NRO/DSEA/RHM2/BC*
NAME AMinarik Slent LHibler ARivera-Varona DATE 08/28/15 08/27/15 08/17/15 08/17/15 OFFICE NRR/JLD/JHMB/BC OGC* NRR/JLD/JHMB/PM NAME MShams SClark VHall DATE 08/28/15 08/14/15 09/04/15