ML20083Q192
| ML20083Q192 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/17/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505250166 | |
| Download: ML20083Q192 (2) | |
Text
+ t Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 May 17, 1995 U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 j
\\
PRAIRIE ISLAND NUCLEAR GENERATING PIANT Docket Nos. 50 282 License Nos. DPR-42 50-306 DPR-60 Revised 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.
This letter provides additional information beyond that included in our May 16, 1995 letter and is intended to supersede that letter.
As per the discussions with the NRC Staff, NSP is performing a root cause analysis of the premature actuation of the auxiliary building crane overload sensing system. As part of this root cause analysis, NSP is working with the Grane Manufacturer to gain a thorough understanding of the crane loading through the full length of the load travel and to identify appropriate corrective actions which may include recalibration, setpoint changes or j
repair.
The root cause analysis will be completed, and all corrective actions necessary to ensure the cask can be lifted safely will be implemented, prior to placing the loaded TN-40 in the cask transporter for transport to the ISFSI.
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 the hoist overload cutout.
As part of 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 by the crane manufacturer and NSP prior to their use.
M' b
9505250166 950517 PDR ADOCK 05000282 P
.... i a
USNRC NORTHERN STATES POWER COMPANY May 17, 1995 Page 2 Prior to placing the loaded TN-40 cask in the cask transporter, NSP will ensure the auxiliary building crene overload sensing system is fully operational to protect against overloads resulting from load hangup or two blocking events.
In this letter we have made new Nuclear Regulatory Commission commitments.
Those commitments are identified above as the statements which are in italics.
Please contact Gene Eckholt (612-388-1121) if you have any questions related to this letter.
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?-y M D Wadley Plant Manage Prairic Island Nuclear Cenerating Plant c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg CRNLTR. DOC