GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor

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Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor
ML22290A251
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/17/2022
From: Hauger J
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-22-110
Download: ML22290A251 (3)


Text

Jeremy S. Hauger Vice President, Engineering P.O. Box 968, PE30 Richland, WA 99352-0968 Ph. 509.377.8727 jshauger@energy-northwest.com 10 CFR 50.90 GO2-22-110 10 CFR 50.69 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO ADOPT 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS

Reference:

1. Letter from J. K. Dittmer (Energy Northwest) to U.S. Nuclear Regulatory Commission, License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, dated November 9, 2021 (ADAMS Accession No. ML21314A224)
2. Letter from J. K. Dittmer (Energy Northwest) to U.S. Nuclear Regulatory Commission, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, dated May 10, 2022 (ADAMS Accession No. ML22130A591)

Dear Sir or Madam:

In Reference 1, Energy Northwest requested an amendment to the Columbia Generating Station (Columbia) Operating License. The proposed amendment would modify the Columbia licensing basis, by the addition of a License Condition, to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Part 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. Reference 2 was submitted to provide additional information to supplement Reference 1.

    

    

 

    

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October 17, 2022 ENERGY

, ___ NORTHWEST

GO2-22-110 Page 2 of 2 The information contained in the attachment to this letter supplements References 1 and

2. The information provided in this supplement does not affect the Technical Analysis or No Significant Hazards Consideration conclusions contained in the license amendment request, and does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

In accordance with 10 CFR 50.91, Energy Northwest is notifying the State of Washington of this amendment supplement by transmitting a copy of this letter and attachment to the designated State Official.

This letter and its attachment contain no new commitments.

If there are any questions or if additional information is needed, please contact Mr. R.M. Garcia, Licensing Supervisor, at 509-377-8463.

I declare under penalty of perjury that the foregoing is true and correct.

Executed this ______ day of ___________ 2022.

Respectfully, Jeremy S. Hauger Vice President, Engineering

Attachment:

Supplemental Information cc:

NRC RIV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C CD Sonoda - BPA/1399 EFSECutc.wa.gov - EFSEC E Fordham - WDOH R Brice - WDOH L Albin - WDOH

    

    

 

    

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DocuSigned by:

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GO2-22-110 Attachment Page 1 of 1 Attachment Supplemental Information The following supplemental information includes an update to References 1 and 2.

Energy Northwest discovered an error in the mean values while evaluating the seismic uncertainty analysis. It was identified that an incorrect setting was used in the Electric Power Research Institute software to calculate the mean seismic core damage frequency (SCDF) and mean seismic large early release frequency (SLERF) values in Reference 1. Discovery of the error required re-analysis of the seismic mean using industry guidance and best practices. Energy Northwest determined that updates to the Mean SCDF, SLERF, and total values were warranted. The SCDF and SLERF mean values represent estimated bounding values, while the total core damage frequency (CDF) and large early release frequency (LERF) mean values (internal events/flooding, fire, and seismic) continue to meet the Regulatory Guide 1.174 threshold requirements of 1E-04 per year for CDF and 1E-05 per year for LERF. See Table 1 below for a summary of the updated SCDF, SLERF, and total values. The italicized information replaces information previously presented in References 1 and 2.

Table 1. Summary of Mean CDF and LERF HAZARD Calculated Mean (per year)

CDF LERF Internal Events/Internal Flood 2.61E-06 1.62E-07 Internal Fire 4.28E-05 3.48E-06 Seismic 2.34E-05 6.19E-06 TOTAL 6.88E-05 9.83E-06

    

    

 

    

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