View source for LIC-16-0107, Final Response to the Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident and Corresponding Commitments

{{Adams
| number = ML16323A206
| issue date = 11/18/2016
| title = Final Response to the Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident and Corresponding Commitments
| author name = Marik S
| author affiliation = Omaha Public Power District
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = DPR-040
| contact person = 
| case reference number = LIC-16-0107
| document type = Letter type:LIC, Response to Request for Additional Information (RAI)
| page count = 2
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:Omaha Public Power District                                                                   10 CFR 50.54(f)
November 18, 2016 LIC-16-01 07 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285

==References:==
: 1. NRC Letter, USNRC to All Power Reactor Licensees, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (NRC-12-0021 )(ML12053A340)
: 2. Letter from OPPD (T. Burke) to NRC (Document Control Desk), "Certification of Permanent Cessation of Power Operations," dated June 24, 2016 (LIC-16-0043)
(ML16176A213)
: 3. Letter from OPPD (T. Burke) to NRC (Document Control Desk), "Certification of Permanent Cessation of Power Operations," dated August 25, 2016 (LIC-16-0067)(ML16242A127)
: 4. Letter from OPPD (T. Burke) to NRC (Document Control Desk), "Certification of Permanent Removal of Fuel from the Reactor Vessel," dated November 13, 2016 (ML16319A254)(LIC-16-0074)

==Subject:==
Fort Calhoun Station Final Response to the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident and Corresponding Commitments On March 12, 2012, the NRC issued "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" (Information Request) to all NRC power reactor licensees and holders of construction permits in active or deferred status (Reference 1). The enclosures of Reference 1 contain specific requested actions, requested information, and required responses associated with Recommendations 2.1 (Seismic), 2.3 (Flooding) and 9.3 (Emergency Preparedness).
444 South 16th Street Mall Omaha, NE 68102-2247

U.S. Nuclear Regulatory Commission LIC-16-01 07 Page 2 Reference 2 notified the NRC that the Omaha Public Power District (OPPD) had decided to permanently cease power operations of Fort Calhoun Station (FCS) before December 31, 2016.
Reference 3 provided the required notification date of permanent cessation of power operation per 10 CFR 50.82(a)(1 ). Reference 4 submitted the certification of permanent removal of fuel from the reactor vessel. As specified in 10 CFR 50.82(a)(2), the 10 CFR Part 50 license for FCS no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel.
The recommendations in Reference 1 are intended for operating units. As Reference 1 indicates, "Operating power reactor licensees under 10 CFR Part 50 are required to respond to all of the information requests." The list of licensees to which Reference 1 applies does not include permanently shutdown units. FCS is no longer an operating plant, but is rather a plant where the reactor has been permanently shutdown and defueled. Therefore, OPPD considers the requests of Reference 1 to no longer be applicable to FCS and no longer plans on proceeding with any further implementation of the recommendations in Reference 1 or any alternative approach for Recommendations 2.1, 2.3 and 9.3.
This letter contains no regulatory commitments. If you should have further questions, please contact Mr. Bradley H. Blome, Manager- Site Regulatory Assurance, at 402-533-7270.
I declare under penalty of perjury that the foregoing is true and correct; executed on November 18, 2016.
~~
Shane M. Marik Site Vice President and CNO SMM/epm c:      K. M. Kennedy, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager T. V. Govan, NRC Project Manger S. M. Schneider, NRC Senior Resident Inspector}}