ML090070335
| ML090070335 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/07/2009 |
| From: | Sarah Bakhsh Division of Nuclear Materials Safety III |
| To: | Jim Clay Division of Nuclear Materials Safety III |
| References | |
| Download: ML090070335 (2) | |
Text
From:
Sarah Bakhsh Sent:
Wednesday, January 07, 2009 8:57 AM To:
Subject:
FW: Request for Information Jim Could you please have this put into ADAMS? I will give you the 665 form. Thanks From: Sarah Bakhsh Sent: Tuesday, January 06, 2009 4:19 PM To: 'timothy.spelde@exeloncorp.com' Cc: 'Tracey.Hulbert@exeloncorp.com'; Christine Lipa; John Bozga
Subject:
FW: Request for Information
- Tim, Below I have included a list of the documentation that our Division of Reactor Safety (DRS) inspectors will need to review in preparation for the dry run. This list is not all inclusive, we may find we need additional information/documentation. If items on the list do not apply please note so. This is for informational purposes and will help make the review process and information transmittal simpler. Also, this information is specific to calculations for modifications in preparation for dry fuel storage and may not include information that we will request as part of the CoC and 10 CFR part 72 review. Please note that we need the owner's approved version of the calculations.
Inspection Procedure: IP 60854.1, Preoperational Testing of an Independent Spent Fuel Storage Facility Installations at Operating Plants Inspector: John Bozga, Reactor Inspector (DRS) - 630/829-9613 A. Information Requested for the In-Office Preparation Week The following information (paper copy if practicable, unless otherwise indicated) is requested to be available in Region III on February 23, 2009. 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 independent spent fuel storage installation:
- i. Byron 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. Byron 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 and Nuclear Energy Institute 08-05, Industry Initiative on Control of Heavy Loads 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, and transported to the ISFSI iv.
Current spent fuel cask drop analysis or single failure proof crane evaluation
- 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 for rigging and special lifting devices 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.
Fuel handling building crane vendor recommendations regarding preventative maintenance, and inspection and testing prior to lifting the spent fuel cask.
- x.
Site procedures associated with Fuel handling building crane preventative maintenance, inspection, and testing prior to lifting the spent fuel cask.
xi.
Documentation for Fuel handling building crane preventative maintenance, inspection, and testing performed prior to lifting the spent fuel cask.
- 2) An electronic copy of the Byron UFSAR.
Sarah Bakhsh Reactor Inspector US Nuclear Regulatory Commission Region III/DNMS/DB Phone: 630/829-9816 Email: Sarah.Bakhsh@NRC.gov E-mail Properties Mail Envelope Properties ()
Subject:
FW: Request for Information Sent Date: 1/7/2009 8:56:00 AM Received Date: 1/7/2009 8:56:00 AM From: Sarah Bakhsh Created By: Sarah.Bakhsh@nrc.gov Recipients:
Jim.Clay@nrc.gov (Jim Clay)
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 0 1/1/4501 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: