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Category:Graphics incl Charts and Tables
MONTHYEARML22278A2452022-09-19019 September 2022 Rev. 21 to Updated Final Safety Analysis Report, Chapter 8, Section 8.3-1(a), Sequence of Events in the Automatic Application of Emergency AC Loads on Loca and Loop ML21133A0472021-04-29029 April 2021 0 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6A, Figures ML21133A0892021-04-29029 April 2021 0 to Updated Final Safety Analysis Report, Chapter 8, Section 8.3, Tables ML21133A0762021-04-29029 April 2021 0 to Updated Final Safety Analysis Report, Chapter 3, Sections 3.3 Through 3.7, Figures ML21133A0652021-04-29029 April 2021 0 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3A, Figures 3A-320 Through 3A-462 ML20339A3742020-12-10010 December 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15357A5172015-12-24024 December 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation RS-14-319, Cancellation of Parent Company Guarantee2014-11-13013 November 2014 Cancellation of Parent Company Guarantee RS-14-069, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-.2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-. RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan ML0731703702007-11-0808 November 2007 Response to Request for Additional Information - Submittal of Relief Requests Associated with the Third Lnservice Inspection (ISI) Interval ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0430003142004-10-25025 October 2004 Supplement to the Request for License Amendment Related to Application of Alternative Source Term, Dated February 27, 2004 ML17037B8491975-08-23023 August 1975 08/21/1975 Summary of Meeting with Mark II Owners, Sargent & Lundy, Bechtel, Stone & Webster, Burns & Roe, and the NRC Staff to Discuss Load Factors and Load Combinations Proposed by the Mark II Owners and Their Architect ... 2022-09-19
[Table view] Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes 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 ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval ML23325A2062023-11-21021 November 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23313A0432023-11-13013 November 2023 Summary of Regulatory Audit in Support of Amendment Request for Control Room Air Conditioning Technical Specifications ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000352/20230032023-10-27027 October 2023 Integrated Inspection Report 05000352/2023003 and 05000353/2023003 and Independent Spent Fuel Storage Installation Inspection 07200065/2023001 ML23297A1722023-10-24024 October 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000352/2024010 and 05000353/2024010 IR 05000352/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000352/2023501 and 05000353/2023501 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 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23276A5162023-10-0303 October 2023 Federal Emergency Management Agency Level 1 Finding from 2023 Evaluated Emergency Preparedness Exercise ML23275A1082023-09-29029 September 2023 FEMA Level 1 Findings Limerick NPP- Boyertown/Colebrookdale ML23241A9452023-09-27027 September 2023 Generation Station, Units 1 and 2 Regulatory Audit Plan Supporting Review of the Equipment Qualification Portion of Limerick Digital Instrumentation and Controls License Amendment Request ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23255A0952023-09-12012 September 2023 Resubmittal of License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) to Address ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A1002023-09-0606 September 2023 Requalification Program Inspection IR 05000352/20230052023-08-31031 August 2023 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2023005 and 05000353/2023005) ML23248A2082023-08-31031 August 2023 UFSAR Cover Page ML23242A2172023-08-30030 August 2023 Response to Request for Additional Information for Application to Adopt TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems and Associated Technical Specification Changes NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23228A0942023-08-16016 August 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . IR 05000352/20230022023-08-14014 August 2023 Integrated Inspection Report 05000352/2023002 and 05000353/2023002 ML23220A0182023-08-0808 August 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000352/2023401 and 05000353/2023401 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 ML23212B2362023-07-31031 July 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System - WEC Documents ML23212B1052023-07-31031 July 2023 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation - Revise ML23202A2192023-07-21021 July 2023 Response to Request for Additional Information for Supplemental License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the . ML23193B0122023-07-20020 July 2023 Audit Plan in Support of Review of License Amendment Request and Exemption Request for Digital Instrumentation and Controls Installation Support (Epids L-2023-LLA-0025 and L-2023-LLE-0005) ML23187A0962023-07-19019 July 2023 Generation Station, Unit Nos. 1 and 2 - Revised Estimated Review Completion Date Concerning License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23208A1522023-07-0606 July 2023 PEMA Letter Dated 7-6-23 Re Limerick Exercise 9-26-23 ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . ML23145A1972023-06-23023 June 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 255, 256, 257, 258, 259, and 260 2024-02-02
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OFFICIAb YSe ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 24, 2015 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST- FLOOD-CAUSING MECHANISM REEVALUATION (CAC NOS. MF6107 AND MF6108)
Dear Mr. Hanson:
The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the reevaluated flood-causing mechanisms described in the March 12, 2015 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML15084A586), flood hazard reevaluation report (FHRR) submitted by Exelon Generation Company, LLC (the licensee) for Limerick Generating Station, Units 1 and 2 (Limerick), 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 reevaluate 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 COMSECY-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.
Enclosure two transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
I OFFICIAL USE ONLY SECURITY RELATED INFORMl\TION B. Hanson The NRG staff has reviewed the information submitted by the licensee and has summarized the results of the review in the tables provided as Enclosure 1 to this letter. Table 1 provides the current design-basis flood hazard mechanisms. Table 2 provides reevaluated flood hazard mechanisms; however, reevaluated hazard mechanisms bounded by the current design-basis (Table 1) are not included. Because Table 2 includes security-related information, Enclosure 1 contains the redacted version of Table 2. Enclosure 2 is withheld from public disclosure and restores the security-related information to Table 2.
The NRG staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, 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 NRG staff) for Limerick. 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 NRG staff plans to issue a staff assessment documenting the basis for these conclusions at a later time.
In addition, Nuclear Energy Institute (NEI) guidance document 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 Limerick 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 the NRC letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond-Design-Basis 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).
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
- OFFJCIAL. USi ONbY SECURITY RELATED INFORMATION B. Hanson If you have any questions, please contact me at (301) 415-6197 or e-mail at Tekia.Govan@nrc.gov.
- lb-6~9 Tekia Govan, Project Manager ~
Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosures:
- 1. Summary of Results of Flooding Hazard Re-Evaluation Report (Redacted Version)
- 2. Summary of Results of Flooding Hazard Re-Evaluation Report (Non-Public Version) cc w/encl: Distribution via Listserv OfflCIAL USE ONLY SECURITY RELATED INFORMATION
ENCLOSURE 1:
SUMMARY
TABLES OF REEVALUATED FLOOD HAZARD LEVELS
Limerick Generating Station, Units 1 & 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA
---**---Mechan-i~--------,-- Stillwater-. ----WavesT- Design- Basis Ref~rence Elevation Run up Hazard Elevation Local Intense Precipitation Turbine Building 218.6 ft NGVD29 II ~inimal M
218.6ft NGVD29 FHRR Section 2.2.1 & Table 4.0.2 Diesel Generator Building
- Not included Not included Not included FHRR Section 2.2.1 & Transmittal in DB in DB in DB Letter j
Streams and Rivers i Schuylkill River 174.0 ft No Impact 174.0 ft FHRR Section 2.2.2 NGVD29 on the Site NGVD29 Identified Sanatoga Creek No Impact No Impact No Impact FHRR Section 2.2.1 I on the Site on the Site on the Site Identified Identified Identified No Impact Possum Hollow Run 159.0 ft on the Site 159.0 ft FHRR Section 2.2.1 & Table 4.0.3 I NGVD29 Identified NGVD29 I
I I
[Redact~]T .
I
-t--* -*- ------ -**-***
Failure of Dams and Onsite Water Control/Storage Structures
[Redacted) [Redacted) [Redacted] [Redacted)
I Storm Surge No Impact No Impact No Impact FHRR Section 2.2.4 on the Site on the Site on the Site I
Identified Identified Identified I I Seiche No Impact No Impact No Impact FHRR Section 2.2.4 on the Site on the Site on the Site Identified Identified Identified I
Tsunami No Impact No Impact No Impact FHRR Section 2.2.5 on the Site on the Site on the Site Identified Identified Identified
Limerick Generating Station, Units r & 2 Table 1. Current Design Basis Flood Hazards for Use in the MSA
Mechanism * * * - ~~~::~~* - ~~~~~--r*~~~~~:*i* Reference Elevation i
-----~ *~-----~
l Ice-Induced Flooding i No Impact No Impact No Impact FHRR Section 2.2.6 i on the Site on the Site on the Site Identified Identified Identified Channel Migrations/Diversions
- 1 No Impact No Impact No Impact FHRR Section 2.2.7 1
on the Site on the Site on the Site Identified Identified Identified Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Limerick Generating Station, Units 1 & 2 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism
,---*--**----~----**
Stillwater Waves/ Ree~aluated _______Reference--------------,
1 I Elevation ' Runup Hazard I Elevation Local Intense Precipitation Diesel Generator Building 217.1 ft Minimal 217.1 ft FHRR Section 3.1.3 & Transmittal NGVD29 NGVD29 Letter 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: ML15357A519; LTR: ML15357A517; ENCL 1: ML15355A534 (PUBLIC); ENCL 2:
ML15355A531 (NON-PUBLIC) *via email OFFICE NRR/JLD/JHMB/PM* NRR/JLD/LA NRO/DSEA/RHM1/TR* NRO/DSEA/RHM1/BC*
NAME TGovan SLent WSharp CCook DATE 12 / 24 /2015 12 / 23 /2015 12/21/2015 12/21/2015 OFFICE NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM TGovan (MShams NAME MShams for)
DATE 12 / 24 /2015 12 / 24 /2015