IR 05000220/2011010

From kanterella
Revision as of 05:30, 8 August 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
IR 05000220/2011010 and 05000410/2011010; 04/063/2011 - 04/29/2011; Nine Mile Point, Units 1 and 2; Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event
ML111320448
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 05/13/2011
From: Doerflein L T
Engineering Region 1 Branch 2
To: Belcher S
Nine Mile Point
Shared Package
ML111300168 List:
References
IR-11-010
Download: ML111320448 (23)


Text

W UNITED STATES N UCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KlNG OF PRUSSIA. PA 19406-1415 May 13, ?Att Mr. Sam Belcher Vice President Nine Mile Point Nuclear Station. LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT: NINE MILE POINT NUCLEAR STATION - NRC TEMPORARY INSTRUCTION 25151183 INSPECTION REPORT O5oOO22ot2o11010 AND 0500041 ot2o11o1o

Dear Mr. Belcher:

on April 29,2011, the.U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Nine Mile Point Nuclear Station Units t and2, using Temporary Insiruction 2515/183,"Followup to the Fukushima Daiichi Nuclear Station rueioamige Event.;' ine enclosed inspection leport documents the inspection results which were Jiscu6"o on Ap ril Zg, 2011 , with you and other members of your staff.The objective of this inspection was to promptly assess the capabilities of Nine Mile point Nuclear Station to respond to extraordinary consequences similar to those that have recenly occurred at the Japanese Fukushima Daiichi Nuclear Station. The results from this inspection, along with the results from this inspection performed at other operating commercial nuclear plants in the United States will be used to evaluate the United States iuclear industry's r-eadiness to safely respond to similar events. These results will also help the NRC to determine if additional regulatory actions are warranted.

All of the potential issues and observations identified by this inspection are contained in this report' The NRC's Reactor Oversight Process will further evaluate any issues to determine if they are regulatory findings or violations.

Any resulting findings or violations will be documented by the NRC in a separate report. You are noi requireo-to respond to this letter. ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).

Sincerely,Engineering Branch 2 Division of Reactor Safety Docket Nos.: 50-220, 50-410 License Nos.: DPR-63, NPF-69

Enclosure:

lnspection Report 050002201201 1 01 0 and 05000 41 01201 1 010 cc Mencl: Distribution via ListServ