Letter Sequence Other |
---|
|
|
MONTHYEARML15072A0092015-03-11011 March 2015 R.E. Ginna Nuclear Power Plant Submittal of Flood Hazard Report Per 10CFR50.54(f) Re Fukushima Near-Term Force Recommendation 2.1: Flooding Project stage: Other ML15148A1632015-06-10010 June 2015 Nuclear Regulatory Commission Plan for the Audit of Exelon Generation Company, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for R. E. Ginna Nuclear Power Plant Project stage: Other ML15334A4532015-12-0404 December 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request-Flood Causing Mechanism Reevaluation Project stage: Other RS-17-026, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal Project stage: Request 2015-03-11
[Table View] |
Similar Documents at Ginna |
---|
Category:Graphics incl Charts and Tables
MONTHYEARNMP1L3339, R. E. Ginna Station - Constellation Energy Group, LLC: Notification of Change in Indirect Ownership2020-04-24024 April 2020 R. E. Ginna Station - Constellation Energy Group, LLC: Notification of Change in Indirect Ownership ML18143B0222018-05-23023 May 2018 R. E. Ginna - Plate G-I, Seismic Refraction Profile I ML18143B0262018-05-23023 May 2018 R. E. Ginna - Plate G-3, Seismic Refraction Surveys, Seismic Refraction Line III and Iv. ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15334A4532015-12-0404 December 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request-Flood Causing Mechanism Reevaluation ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0315504242003-06-0303 June 2003 in Surge Example, Ginna Maximum System At'S During Heatups, & Ginna Maximum System At'S During Cooldowns ML18143A4451978-08-0303 August 1978 Spent Fuel Pool Cooling ML18143A4421978-08-0202 August 1978 R. E. Ginna - Response to Request, Attached Are Additional Detail on Flux Map Taken During Startup of Cycle 8 ML18142B0721978-07-28028 July 1978 Forwards Semiannual Effluent Release Report for the Period of Jan. - Jun. 1978 ML18143A4501978-07-27027 July 1978 R. E. Ginna - 1978 Steam Generator Inspection Final Report and NRC Questionnaire Update ML18142A7031978-04-18018 April 1978 Response to NRC Request Consisting of Information Concerning Data Taken During the Startup of Cycle 7 at Subject Facility with Attachment Table Presenting Predicted Rod Worth and the Measured Rod Worths with and Without Control Rod ML18142B0711978-03-14014 March 1978 Forwards Semiannual Effluent Release Report for the Period of Jul. - Dec. 1977 ML18192A0781977-05-11011 May 1977 R. E. Ginna - Steam Generator Inspection Final Report, May 11, 1977 ML18142B0701977-02-0303 February 1977 Forwards Semiannual Effluent Release Report for the Period of Jul. - Dec. 1976 ML18142B0691976-07-26026 July 1976 Forwards Semiannual Effluent Release Report for the Period of Jan. - Jun. 1976 ML18142C0691975-10-30030 October 1975 R. E. Ginna - 10/30/1975 Letter Transmittal of Request for Exemption from Certain Provisions of Appendix J to 10 C.F.R. Part 50 2020-04-24
[Table view] Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection 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 RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23258A1382023-09-18018 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010 IR 05000244/20230052023-08-31031 August 2023 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report IR 05000244/20234012023-08-15015 August 2023 LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only) IR 05000244/20230022023-08-0303 August 2023 LLC - Integrated Inspection Report 05000244/2023002 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 IR 05000244/20234022023-07-19019 July 2023 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only) RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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 RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report ML23121A0482023-05-0101 May 2023 R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000244/20230012023-04-26026 April 2023 LLC - Integrated Inspection Report 05000244/2023001 ML23100A0302023-04-10010 April 2023 2023 10 CFR 50.46 Annual Report ML23114A1152023-03-29029 March 2023 Electronic Reporting of Exposure Data for 2022 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 ML23075A0872023-03-15015 March 2023 R. E. Ginna Nuclear Power Plant - Project Manager Assignment 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 IR 05000244/20220062023-03-0101 March 2023 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006) ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23060A1622023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators ML22287A0692023-02-0808 February 2023 R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request ML23010A0112023-02-0101 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000244/20223012023-01-20020 January 2023 Initial Operator Licensing Examination Report 05000244/2022301 IR 05000244/20220122023-01-12012 January 2023 LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012 ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22348A2062022-12-14014 December 2022 Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 2024-02-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation
- Company, LLC 4300 Winfield Road Warrenville, IL 60555 December 4, 2015
SUBJECT:
R.E. GINNA 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 MF6098)
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 re-evaluated flood-causing mechanisms described in the March 11, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15072A009, flood hazard reevaluation report (FHRR) submitted by R. E. Ginna Nuclear Power Plant, LLC (the licensee) for R. E. Ginna Nuclear Power Plant (Ginna),
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. ML 12053A340).
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. ML 12054A735).
On March 30, 2015, the Commission provided Staff Requirements Memoranda (SRM) (ADAMS Accession No. ML 15089A236) 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. ML 14309A256),
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 information submitted by the licensee 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 flood hazard mechanisms bounded by the current design-basis (Table 1) are not included.
The NRC 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 B. Hanson described in guidance documents currently being finalized by the industry and NRC staff) for Ginna. 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, 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 Ginna 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. ML 15174A257).
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. ML 15209A682).
B. Hanson If you have any questions, please contact me at (301) 415-6197 or e-mail at Tekia.Govan@nrc.gov.
Docket No. 50-244
Enclosure:
Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv Sincerely, Tekia Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation ENCLOSURE:
SUMMARY TABLES OF REEVALUATED FLOOD HAZARD LEVELS
- R.E. Ginna Nuclear Power Plant Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Local Intense Precipitation Screen House Streams and Rivers PMF -Reactor Building PMF -Auxiliary Building PMF -Turbine Building PMF -Control Building PMF -All-Volatile-Treatment Building PMF -Standby Auxiliary Feedwater Pump Building PMF -Screen House PMF -Diesel Generator Building Failure of Dams and Onsite Water Control/Storage Structures Stillwater Elevation 254.5 ft NGVD29 272.0 ft NGVD29 273.8 ft NGVD29 256.6 ft NGVD29 272.0 ft NGVD29 272.0 ft NGVD29 273.0 ft NGVD29 256.6 ft NGVD29 i i I Waves/ Run up Minimal i Not I , applicable Not applicable Not applicable Not applicable Not applicable
!I Not applicable Not applicable 256.6 ft Not NGVD29 applicable i I Not included
, Not included in DB 1 in DB Design Basis Hazard Elevation 254.5 ft NGVD29 272.0 ft NGVD29 273.8 ft NGVD29 256.6 ft NGVD29 272.0 ft NGVD29 272.0 ft NGVD29 273.0 ft NGVD29 256.6 ft NGVD29 256.6 ft NGVD29 Not included in DB Reference FHRR Section 1.3 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Table 2.2-6 FHRR Section 3.1.3 R.E. Ginna Nuclear Power Plant Table 1. Current Design Basis Flood Hazards for Use in the MSA --------**--
Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard Elevation Storm Surge I Tropical Storm and Associated 253.3 ft 7.7 ft 260.9 ft FHRR Section 1.3 phenomena NGVD29 NGVD29 I Seiche Not included Not included Not included FHRR Section 3.1.5 in DB in DB in DB I I Tsunami I Not included Not included Not included FHRR Section 3.1.6 I in DB I in DB in DB I I I I Ice-Induced Flooding
! No Impact No Impact No Impact FHRR Section 3.1.7 I on the Site i on the Site on the Site Identified I Identified Identified Channel Migrations/Diversions Not included Not included Not included FHRR Section 3.1.8 in DB in DB in DB Note 1: Reported values are rounded to the nearest one-tenth of a foot.
R.E. Ginna Nuclear Power Plant Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA I Mechanism Stillwater Waves/ Reevaluated Reference I Elevation Run up Hazard I I Elevation I I Local Intense Precipitation
! ! LIP 6-h event: Reactor 270.9 ft Minimal 270.9 ft FHRR Table 2.1-1 Containment I NGVD29 NGVD29 I I LIP 6-h event: Auxiliary Building 270.7 ft Minimal 270.7 ft FHRR Table 2.1-1 NGVD29 NGVD29 I ' I I LIP 6-h event: Turbine Building 255.8 ft Minimal 255.8 ft FHRR Table 2.1-1 I NGVD29 NGVD29 I I ' LIP 6-h event: Control Building i 270.9 ft Minimal 270.9 ft FHRR Table 2.1-1 i NGVD29 NGVD29 ! I LIP 6-h event: All-Volatile-i 270.8 ft Minimal 270.8 ft FHRR Table 2.1-1 Treatment Building NGVD29 NGVD29 I I LIP 6-h event: Standby Auxiliary 270.2 ft Minimal 270.2 ft I FHRR Table 2.2-1 Feedwater Pump Building NGVD29 NGVD29 LIP 6-h event: Proposed Standby 270.5 ft Minimal 270.5 ft FHRR Table 2.1-1 Auxiliary Feedwater Pump NGVD29 NGVD29 Building Annex LIP 6-h event: Screen House 255.8 ft Minimal 255.8 ft FHRR Table 2.1-1 NGVD29 NGVD29 LIP 6-h event: Diesel Generator 255.8 ft Minimal 255.8 ft FHRR Table 2.1-1 Building NGVD29 NGVD29 Streams and Rivers ' Reactor Building (stillwater:
PMF; 272.4 ft Not 272.4 ft FHRR Table 2.2-6 total water level: PMF, H.1, H.4.2) NGVD29 applicable NGVD29 FHRR Sections 2.9.3 and 3.1.9 Turbine Building (stillwater:
PMF; 258.2 ft Not 258.2 ft FHRR Sections 2.9.3, 3.1.9 and total water level: H.4.2) NGVD29 applicable NGVD29 FHRR Enclosure 1 Table 4 ' I I R.E. Ginna Nuclear Power Plant Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Control Building (stillwater:
PMF; total water level: PMF, H.1, H.4.2) Standby Auxiliary Feedwater Pump Building (stillwater:
PMF; total water level: H.1) Proposed Standby Auxiliary Feedwater Pump Building Annex (stillwater:
PMF; total water level: H.1) j Screen House (stillwater:
PMF; total water level: H.4.2) Diesel Generator Building (stillwater:
PMF; total water level: H.4.2) Stillwater Elevation 272.4 ft NGVD29 272.8 ft NGVD29 273.5 ft NGVD29 258.2 ft NGVD29 258.4 ft NGVD29 Waves/ Run up Reevaluated Hazard Elevation Not I 272.4 ft applicable 1 NGVD29 0.9 ft 0.9 ft I 273.7 ft NGVD29 274.4ft NGVD29 Not 258.2 ft applicable NGVD29 Not applicable 258.4 ft NGVD29 Reference FHRR Table 2.2-6 FHRR Section 2.9.3 and 3.1.9 FHRR Table 2.2-6 FHRR Enclosure 1 Tables 2 and 3 FHRR Enclosure 1 Tables 2 and 3 FHRR Sections 2.9.3, 3.1.9 and FHRR Enclosure 1 Table 4 FHRR Sections 2.9.3, 3.1.9 and FHRR Enclosure 1 Table 4 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.
B. Hanson If you have any questions, please contact me at (301) 415-6197 or e-mail at Tekia.Govan@nrc.gov.
Docket No. 50-244
Enclosure:
Sincerely, IRA! Tekia Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC TGovan, NRR RidsNrrDorllpl1-1 Resource RidsRgn1 MailCenter Resource RidsOpaMail Resource ARivera-Varona, NRO MWillingham, NRO MShams, NRR JLD R/F LQuinn-Willingham, NRO RidsNrrDorl Resource RidsNrrLASLent
RidsAcrsAcnw_MailCtr Resource KErwin, NRO RRivera-Lugo, NRO LHibler, NRR RidsNRRJLD Resource RidsNroDsea Resource RidsNrrPMGinna Resource RidsOgcMailCenter Resource CCook, NRO ACampbell, NRO BHarvey, NRO ADAMS Accession Nos.: PKG ML15334A451; LTR: ML15334A453; ENCL: ML15327A204
- via email OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRO/DSEA/RHM2/TR*
NAME TGovan Slent LHibler DATE 12/2/2015 12/2/2015 11/24/2015 OFFICE NRO/DSEA/RHM2/TL
- NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME ARivera-Varona MShams TGovan DATE 11/24/2015 12/4/2015 12/4/2015 OFFICIAL RECORD COPY