ML092960428
| ML092960428 | |
| Person / Time | |
|---|---|
| Site: | Fermi, Holtec  |
| Issue date: | 10/23/2009 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| Download: ML092960428 (4) | |
Text
Enclosure 1
Enclosure 2
INDEPENDENT SPENT FUEL STORAGE INSTALLATION CONTROL OF HEAVY LOADS INSPECTION DOCUMENT REQUEST Inspection Procedures: IP 60854, Preoperational Testing of an ISFSI IP 60854.1, Preoperational Testing of an Independent Spent Fuel Storage Facility Installations at Operating Plants Inspector:
John V. Bozga (630) 829-9613 A.
Information Requested for the ISFSI Control of Heavy Loads The following information (paper copy if practicable, unless otherwise indicated) is requested to be available at least 2 months prior to practice or dry run activities or earlier than 2 months if possible. If you have any questions regarding this information, please contact the inspector as soon as possible.
- 1)
A copy of the following documents related to control of heavy loads during independent spent fuel storage installation operations:
- i. Fermi 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) ii.
Fermi 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 1 Clarification of NRC Guidelines for Control of Heavy Loads, Enforcement Guidance Memorandum 2007-006, Enforcement Discretion for Heavy Load Handling Activities, Nuclear Energy Institute 08-05, Industry Initiative on Control of Heavy Loads and NRC Regulatory Issue Summary 2008-28 Endorsement of Nuclear Energy Institute Guidance for Reactor Vessel Heavy Load Lift iii.
Design documentation, design calculations, safety evaluations (72.48 and 50.59), and resultant structural modifications that demonstrated the fuel cask could be safely placed into the spent fuel pool and loaded with spent fuel, lifted from the spent fuel pool and placed on the designated laydown areas, transferred to the transport vehicle (laydown areas, spent fuel pool structure, etc.)
Enclosure 3
iv.
Design basis calculations and any design modifications for Reactor Building crane trolley, trolley bridge and crane support structure.
- v.
Other supporting documents that demonstrate equipment to maintain safe shutdown will be unaffected (i.e. calculations associated with the spent fuel cask drop analysis) and that potential offsite releases at the exclusion boundary will be within 10 CFR part 100 limits after a postulated spent fuel cask drop.
vi.
Calculations and Fermi licensing commitments for all special lifting devices (lift yoke, trunnions, etc.) and all lifting devices (slings) associated with lifting the spent fuel cask.
vii.
Documents that establish the total lift weight for the ISFSI.
viii.
Site procedures associated with Control of Heavy Loads, transport of independent spent fuel storage installation during plant operations, and any contingency actions taken to mitigate the consequences of a spent fuel cask drop.
ix.
Reactor Building Crane vendor recommendations regarding preventative maintenance, and inspection and testing prior to lifting the spent fuel cask.
- x.
Site procedures associated with Reactor Building Crane preventative maintenance, inspection, and testing prior to lifting the spent fuel cask.
xi.
Documentation for Reactor Building Crane preventative maintenance, inspection, and testing performed prior to lifting the spent fuel cask.
INITIAL DOCUMENT REQUEST Enclosure 4