ML092950414
| ML092950414 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/21/2009 |
| From: | Dave Hills NRC/RGN-III/DRS/EB1 |
| To: | Costanzo C Duane Arnold |
| References | |
| Download: ML092950414 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 October 21, 2009 Mr. Christopher R. Costanzo Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Costanzo:
On January 19, 2010, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20) prior to the next refueling outage scheduled for the Duane Arnold Energy Center. This inspection will utilize NRC Operating Experience Smart Sample: (OpESS) FY 2007-03, Revision 2, Crane and Heavy Lift Inspection, supplemental guidance for IP-71111.20, issued September 12, 2008. This inspection will focus on the impact of load handling activities on the reactor core and its cooling and plant support systems.
Specifically, this inspection will review applicable design and licensing bases, engineering design and analysis, procedures, and surveillances associated with the reactor vessel head removal and installation during refueling outages including: (1) Reactor building crane preventative maintenance, inspections and testing; (2) reactor vessel head rigging equipment; (3) reactor vessel head drop analysis (or single failure proof crane or equivalency); and (4) reactor vessel head safe load paths. The on-site inspection is scheduled to take place on January 19-22, 2010, and February 1-5, 2010.
Experience has shown that inspection of these activities is resource intensive both for the NRC inspector and licensee staff. In order to minimize the inspection impact to the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection. This information should be available in Region III by January 11, 2010, (preparatory week). It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. R. Murrell, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. V. Meghani, at (630) 829-9751.
C. Costanzo In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-331 License No. DPR-49
Enclosure:
Crane and Heavy Lift Inspection Document Request w/Enclosure (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl:
Distribution via ListServ
CRANE AND HEAVY LIFT INSPECTION DOCUMENT REQUEST Enclosure 1
Inspection Dates:
January 19-22 and February 1-5, 2010 Inspection Procedures:
IP 71111.20, Refueling and Other Outage Activities Lead Inspector:
Vijay Meghani (630) 829-9751 Vijay.meghani@nrc.gov I.
Information Requested for In-Office Preparation Week The following information is requested to be available in Region III on January 11, 2010. If you have any questions regarding this information, please call the inspector as soon as possible.
A copy of the following documents related to the control of heavy loads during removal or installation of the reactor vessel head:
(1)
Duane Arnold submittals as a result of NRC December 22, 1980, unnumbered Generic Letter (GL) (now NRC numbered as GL 80-113) and GL 81-07, Control of Heavy Loads regarding NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, six-month response (Phase I) and nine-month response (Phase II). Final Supplement to Safety Evaluation Report related to NUREG 0612, Phase I and Phase II, if applicable.
(2)
Reactor head drop analysis associated with above Phase II submittals, if applicable.
(3)
Duane Arnold corrective action program reports related to NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads, NRC Regulatory Issue Summary 2005-25, Supplement I Clarification of NRC Guidelines for Control of Heavy Loads, Enforcement Guidance Memorandum 2007-006, Enforcement Discretion for Heavy Load Handling Activities, and Nuclear Energy Institute 08-05, Industry Initiative on Control of Heavy Loads.
(4)
Current reactor head drop analysis (if different from Phase II submittals) or single failure proof crane/equivalency evaluation.
(5)
Other supporting documents that demonstrate equipment to maintain safe shutdown will be unaffected (i.e., calculations associated with the reactor head drop analysis) and that potential offsite releases at the exclusion boundary will be within 10 CFR Part 100 limits after a postulated reactor vessel head drop.
(6)
Calculations for crane and crane support structure, lifting lug on reactor vessel head, and special lifting devices associated with lifting the reactor vessel head (RPV Head strongback and Dryer/Separator strongback).
CRANE AND HEAVY LIFT INSPECTION DOCUMENT REQUEST Enclosure 2
(7)
Documents that establish the total lift weight for the existing reactor vessel head.
(8)
Site procedures associated with Control of Heavy Loads, removal of the reactor vessel head during refueling operations, installation of the reactor vessel head during refueling operations, and any contingency actions taken to mitigate the consequences of a postulated reactor vessel head drop.
(9)
Reactor building crane vendor recommendations regarding preventative maintenance, and inspection, and testing prior to use.
(10)
Site procedures associated with Reactor building crane preventative maintenance, inspection, and testing prior to lifting the reactor vessel head.
(11)
Documentation for Reactor building crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor vessel head.
(12)
An electronic copy of the Duane Arnold UFSAR.
If you have questions regarding any of the information requested, please contact the lead inspector.
C. Costanzo In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-331 License No. DPR-49
Enclosure:
Crane and Heavy Lift Inspection Document Request w/Enclosure (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl:
Distribution via ListServ DISTRIBUTION:
Susan Bagley RidsNrrDorlLpl3-1 Resource RidsNrrPMDuaneArnold Resource RidsNrrDirsIrib Resource Cynthia Pederson Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource DOCUMENT NAME: G:\\DRS\\WIP\\Ltr 102109 Duane Arnold Notification of Inspection and RFI VLM.doc Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII NAME VMeghani:ls DHills DATE 10/21/09 10/21/09 OFFICIAL RECORD COPY