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| number = ML18051A401 | | number = ML18051A401 | ||
| issue date = 02/21/2018 | | issue date = 02/21/2018 | ||
| title = | | title = Staff Assessment of Response to 10 CFR (F) Information Request - Flood Causing Mechanism Reevaluation (Public) | ||
| author name = Vega F | | author name = Vega F | ||
| author affiliation = NRC/NRR/DLP/PBMB | | author affiliation = NRC/NRR/DLP/PBMB | ||
| addressee name = Reddemann M | | addressee name = Reddemann M | ||
| addressee affiliation = Energy Northwest | | addressee affiliation = Energy Northwest | ||
| docket = 05000397 | | docket = 05000397 | ||
| Line 14: | Line 14: | ||
| document type = Letter | | document type = Letter | ||
| page count = 3 | | page count = 3 | ||
| project = CAC:MF8455, EPID:L-2016-JLD-0010 | |||
| stage = Other | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:OFFICIAL USE ONLY-SECURITY RELATED INFORMATION Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest MD 1023 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 21, 2018 76 North Power Plant Loop P.O. Box 968 Richland, WA 99352 | |||
==SUBJECT:== | |||
COLUMBIA GENERATING STATION-STAFF ASSESSMENT OF RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST-FLOOD-CAUSING MECHANISM REEVALUATION (CAC NO. MF8455; EPID NO. | |||
000495/05000397/L-2016-JLD-OO 10) | |||
==Dear Mr. Reddemann:== | |||
By {{letter dated|date=March 12, 2012|text=letter dated March 12, 2012}}, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information under Title 10 of the Code of Federal Regulations, Section 50.54(f) | |||
(hereafter referred to as the 50.54(f) letter). 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 that licensees reevaluate flood-causing mechanisms using present-day methodologies and guidance. By {{letter dated|date=October 6, 2016|text=letter dated October 6, 2016}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A309), Energy Northwest (the licensee) responded to this request for Columbia Generating Station (Columbia). | |||
By {{letter dated|date=December 7, 2016|text=letter dated December 7, 2016}} (ADAMS Accession No. ML16337A111 ), the NRC staff sent the licensee a summary of the staff's review of Columbia's reevaluated flood-causing mechanisms. The enclosed staff assessment provides the documentation supporting the NRC staff's conclusions summarized in the letter. As stated in the letter, the reevaluated flood hazard results for the local intense precipitation (LIP) and streams and rivers flood-causing mechanisms were not bounded by the current design basis. In order to complete its response to Enclosure 2 to the 50.54(f) letter, the licensee is expected to submit a focused evaluation for LIP and streams and rivers to address these reevaluated flood hazards, as discussed in COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazard for Operating Nuclear Power Plants," and Japan Lessons-Learned Division (JLD) Interim Staff Guidance (ISG) JLD-ISG-2016-01, "Guidance for Activities Related to Near-Term Task Force Recommendation 2.1, Flooding Hazard Reevaluation; Focused Evaluation and Integrated Assessment." This letter closes out the NRC's efforts associated with CAC No. MF8455. | |||
The Enclosure transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled. | |||
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION | |||
M. Reddemann OFFICIAL USE ONLY-SECURITY RELATED INFORMATION If you have any questions, please contact me at (301) 415-1617 or by e-mail at Frankie.Vega@nrc.gov. | |||
Docket No. 50-397 | |||
==Enclosure:== | |||
Staff Assessment of Flood Hazard Reevaluation Report for Columbia (non-public, Security Related) cc w/o encl: Distribution via Listserv Sincerely, tJ' | |||
.// | |||
Frankie ega, Pr~ger Beyond-Design-Basis Management Branch Division of Licensing Projects Office of Nuclear Reactor Regulation OFFICIAL USE ONLY-SECURITY RELATED INFORMATION | |||
Pkg ML18051A332; ML18051A359 (Non-Public;Encl} | |||
ML18051A401 (Public Letter) | |||
*by input dated OFFICE N RR/DLP/PBMB/PM NRR/DLP/PBMB/LA NRO/DSEA/RHM2/BC NAME FVega SLent CCook* | |||
DATE 02/20/2018 02/20/2018 02/01/2018 OFFICE NRR/DLP/PBMB/BC (A) NRR/DLP/PBMB/PM NAME EBowman FVega DATE 02/21/2018 02/21/2018}} | |||
Latest revision as of 09:58, 6 January 2025
| ML18051A401 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 02/21/2018 |
| From: | Frankie Vega Beyond-Design-Basis Management Branch |
| To: | Reddemann M Energy Northwest |
| Shared Package | |
| ML18051A332 | List: |
| References | |
| CAC MF8455, EPID L-2016-JLD-0010 | |
| Download: ML18051A401 (3) | |
Text
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest MD 1023 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 21, 2018 76 North Power Plant Loop P.O. Box 968 Richland, WA 99352
SUBJECT:
COLUMBIA GENERATING STATION-STAFF ASSESSMENT OF RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST-FLOOD-CAUSING MECHANISM REEVALUATION (CAC NO. MF8455; EPID NO.
000495/05000397/L-2016-JLD-OO 10)
Dear Mr. Reddemann:
By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information under Title 10 of the Code of Federal Regulations, Section 50.54(f)
(hereafter referred to as the 50.54(f) letter). 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 that licensees reevaluate flood-causing mechanisms using present-day methodologies and guidance. By letter dated October 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A309), Energy Northwest (the licensee) responded to this request for Columbia Generating Station (Columbia).
By letter dated December 7, 2016 (ADAMS Accession No. ML16337A111 ), the NRC staff sent the licensee a summary of the staff's review of Columbia's reevaluated flood-causing mechanisms. The enclosed staff assessment provides the documentation supporting the NRC staff's conclusions summarized in the letter. As stated in the letter, the reevaluated flood hazard results for the local intense precipitation (LIP) and streams and rivers flood-causing mechanisms were not bounded by the current design basis. In order to complete its response to Enclosure 2 to the 50.54(f) letter, the licensee is expected to submit a focused evaluation for LIP and streams and rivers to address these reevaluated flood hazards, as discussed in COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazard for Operating Nuclear Power Plants," and Japan Lessons-Learned Division (JLD) Interim Staff Guidance (ISG) JLD-ISG-2016-01, "Guidance for Activities Related to Near-Term Task Force Recommendation 2.1, Flooding Hazard Reevaluation; Focused Evaluation and Integrated Assessment." This letter closes out the NRC's efforts associated with CAC No. MF8455.
The Enclosure transmitted herewith contains Security-Related Information. When separated from the Enclosure, this document is decontrolled.
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION
M. Reddemann OFFICIAL USE ONLY-SECURITY RELATED INFORMATION If you have any questions, please contact me at (301) 415-1617 or by e-mail at Frankie.Vega@nrc.gov.
Docket No. 50-397
Enclosure:
Staff Assessment of Flood Hazard Reevaluation Report for Columbia (non-public, Security Related) cc w/o encl: Distribution via Listserv Sincerely, tJ'
.//
Frankie ega, Pr~ger Beyond-Design-Basis Management Branch Division of Licensing Projects Office of Nuclear Reactor Regulation OFFICIAL USE ONLY-SECURITY RELATED INFORMATION
Pkg ML18051A332; ML18051A359 (Non-Public;Encl}
ML18051A401 (Public Letter)
- by input dated OFFICE N RR/DLP/PBMB/PM NRR/DLP/PBMB/LA NRO/DSEA/RHM2/BC NAME FVega SLent CCook*
DATE 02/20/2018 02/20/2018 02/01/2018 OFFICE NRR/DLP/PBMB/BC (A) NRR/DLP/PBMB/PM NAME EBowman FVega DATE 02/21/2018 02/21/2018