ML20083D009
| ML20083D009 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/16/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505230247 | |
| Download: ML20083D009 (2) | |
Text
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Northern States Power Company Pralrie Island Nuclear Generating Plaat 1717 Wakonade Dr. East l
Welch, ennesota 55089 May 16, 1995 U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR CENERATING PIANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR 60 Response to Auxiliary Building Crane Overload Protection System Actuation The following information is provided to confirm commitments made by NSP Management during discussions with the NRC Staff following the premature actuation of a auxiliary building crane overload sensing device during the lifting of a TN-40 cask on May 13, 1995.
As per the discussions with the NRC Staff, NSP will perform a root cause analysis of the premature actuation of the auxiliary building crane overload sensing system prior to placing the loaded TN-40 in the cask transporter for transport to the ISFSI. As part of this root cause analysis, NSP is working with the Crane flanufacturer to gain a thorough understanding of the crane.
loading through the full length of the load travel and to identify appropriate corrective actions. The completion of this root cause analysis will be tracked by the Prairie Island Non Conformance process.
The bypass that was utilized to complete the cask lift on May 13, 1995 has been removed.
The auxiliary building crane is presently in the pre-actuation state and the subject overload sensing device would still conservatively actuate che hoist overload cutout.
As part cf the root cause investigation, and possibly during subsequent calibration of the load sensing device, lifting of the loaded cask may be required. Any lifts of the loaded cask will follow safe load paths as defined in the Prairie Island procedures.
If the loaded TN-40 cask is used for the re-calibration of the load sensing device, separate procedures will be prepared for those operations. Those procedures will be reviewed '.sy the crane manufacturer and NSF prior to their use.
In this letter we have made new Nuclear Regulatory Commission commitments.
Those commitments are identified above as the statements which are in italics.
9505230247 950516 4
PDR ADOCK 05000282 P
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,~e' NORTHERN STATES POWER COMPANY USNRC May 16, 1995 Page 2 Plasse contact Gene Eckholt (612-388-1121) if you have any questions related to this letter.
YYYS M D Wadley Plant Manager Prairie Island Nuclear Generating Plant i
i c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC i
J E Silborg i
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