ML070330485
| ML070330485 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/29/2007 |
| From: | Dave Hills NRC/RGN-III/DRS/EB1 |
| To: | Harden P Nuclear Management Co |
| References | |
| Download: ML070330485 (6) | |
Text
January 29, 2007 Mr. Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES NUCLEAR PLANT - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Harden:
On March 19, 2007, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure (IP) 71111.20) prior to the 2007 refueling outage scheduled for the Palisades Nuclear Plant. Specifically, this inspection will review applicable design and licensing bases, engineering design and analysis, and procedures associated with reactor vessel head lifting and rigging including: (1) crane and rigging equipment; (2) reactor vessel head component drop analysis; and (3) safe load paths. This inspection will focus on the impact of load handling activities on the reactor core and its cooling and plant support systems. This inspection will also utilize NRC IP 71007. The on-site inspection is scheduled to take place on March 19 through March 23, 2007, and April 2 through April 6, 2007.
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 to the Regional Office by no later than March 12, 2007. During the in-office preparation week, the inspector may identify additional information needed. This information should be available by March 19, 2007, (on-site 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 Ms. B. Dotson, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Neurauter, at (630) 829-9828.
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
P. Harden Room, or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), 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. 50-255 License No. DPR-20
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl:
M. Sellman, President and Chief Executive Officer R. Fenech, Senior Vice President, Nuclear Fossil and Hydro Operations D. Cooper, Senior Vice President - Group Operations L. Lahti, Manager, Regulatory Affairs J. Rogoff, Vice President, Counsel and Secretary A. Udrys, Esquire, Consumers Energy Company S. Wawro, Director of Nuclear Assets, Consumers Energy Company Supervisor, Covert Township Office of the Governor State Liaison Office, State of Michigan L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division
P. Harden 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-255 License No. DPR-20
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl:
M. Sellman, President and Chief Executive Officer R. Fenech, Senior Vice President, Nuclear Fossil and Hydro Operations D. Cooper, Senior Vice President - Group Operations L. Lahti, Manager, Regulatory Affairs J. Rogoff, Vice President, Counsel and Secretary A. Udrys, Esquire, Consumers Energy Company S. Wawro, Director of Nuclear Assets, Consumers Energy Company Supervisor, Covert Township Office of the Governor State Liaison Office, State of Michigan L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division DOCUMENT NAME: C:\\FileNet\\ML070330485.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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 RIII RIII RIII NAME JNeurauter: ls DHills CLipa DATE 01/26/07 01/29/07 01/26/07 OFFICIAL RECORD COPY
P. Harden ADAMS DISTRIBUTION:
MLC TEB RidsNrrDirsIrib GEG KGO GLS JBG JAE CAA1 DRPIII DRSIII PLB1 TXN
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Enclosure 1
Inspection Dates:
March 19 - April 6, 2007 Inspection Procedures:
IP 71007, Reactor Vessel Head Replacement Inspection IP 71111.20, Refueling and Other Outage Activities Inspector:
Jim Neurauter (630) 829-9828 A.
Information Requested for the In-Office Preparation Week The following information (paper copy if practicable, unless otherwise indicated) is requested to be available at the Region III Office no later than March 12, 2007. If you have any questions regarding this information, please call the inspector as soon as possible.
1)
A copy of the following documents related heavy load control during removal or installation of the reactor vessel head:
a.
Palisades submittals as a result of NRC December 22, 1980, generic letter (GL) (unnumbered) and GL 81-07, Control of Heavy Loads regarding NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, 6-month response (Phase I) and 9-month response (Phase II).
b.
Reactor head drop analysis associated with above Phase II submittals, if applicable.
c.
Palisades corrective action report that evaluated NRC Regulatory Issue Summary 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads.
d.
Current reactor head drop analysis, EA-CAP047706-01, Palisades Reactor Head Drop Analysis, if revised from Revision 0.
e.
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.
f.
Calculations for rigging and special lifting devices associated with lifting the reactor vessel head.
g.
Documents that establish the total lift weight for the existing reactor vessel head.
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Enclosure 2
h.
Site and/or NMC Fleet 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.
2)
An electronic copy of the Palisades UFSAR.