L-17-221, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident

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Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
ML17213A015
Person / Time
Site: Beaver Valley
Issue date: 07/27/2017
From: Bologna R
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17213A014 List:
References
CAC MF3726, CAC MF3727, L-17-221
Download: ML17213A015 (2)


Text

FENOC futpry Beaver Valley Power Station P.O. Box 4 Fn# Eruagr f\trcfser Qprra/iry

-Qhinninannfi PA 16n77 Richard D. Bologna 724-682-5234 Srfe Vhe President Fax: 724-643-8069 July 27,2017 L-17-221 10 cFR 50.54(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 1 1555 Rockville Pike Rockville, MD 20852

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Seismic Probabilistic Risk Assessment. Resnonse to NRC uest for Information Pursuant to 10 CFR .54(fl Reoardino Recommendation 2. 1 the Near-Term Task NTT Review F hima Dai-ichi MF3726, MF3727)

On March 12,2012, the Nuclear Regulatory Commission (NRC) issued a Request for lnformation per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees.

Enclosure 1 of Reference 1 requested each addressee to reevaluate the site seismic hazard using updated seismic information and present-day regulatory guidance and methodologies and, if necessory, to perform a risk evaluation. By letter dated October 27,2015 (Reference 2), the NRC transmitted final seismic information request tables, which identified that FirstEnergy Nuclear Operating Company (FENOC) is to conduct a seismic probabilistic risk assessment (SPRA) for Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2.

The enclosures to this letter provide the SPRA for BVPS Unit No. 1 and BVPS Unit No. 2 (Enclosures A and B, respectively), including the requested information in response to Item (8.8) of Reference 1 associated with NTTF Recommendation 2.1 Seismic evaluation criteria.

Beaver Valley Power Station, Unit Nos. 1 and 2 L-17-221 Page 2 There are no regulatory commitments contained in this letter. lf there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager Fleet Licensing, at 330-315-6810.

I declare under penalty of perjury that the foregoing is true and correct. Executed on July &7 , zo1r.

Respectfully, Richard D. Bolog na Enclosures A. Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2,1, Beaver Valley Power Station Unit No. 1 B. Seismic Prohabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1, Beaver Valley Power Station Unit No. 2

References:

1. NRC Letter, Request for lnformation Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recornmendations 2.1,2.3. and 9.3, of the Near-Term Task Force Review of lnsights from the Fukushima Dai-ichi Accident, dated March 12,2012, Agencywide Documents Access and Management System (ADAMS) Accession Number ML12053A340.
2. NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for lnformation Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of lnsights from the Fukushima Dai-ichi Accident, dated October ?7 ,2015, ADAfvlS Accession Number ML15194A015.

cc; Director, Office of Nuclear Reactor Regulation (NRR)

NRC Region I Administrator NRC Resident lnspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative