ML18059A410
| ML18059A410 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 09/30/1993 |
| From: | Slade G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9310060277 | |
| Download: ML18059A410 (2) | |
Text
consumers Power PDWERINli MICHlliAN'S PROliRESS Palisades Nuclear Plant:
27780 Blue Star Memorial Highway, Coven. Ml 49043 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 September 30, 1993
. GB Slade General Manager DOCKET 50-255 - LICENSE DPR PALISADES PLANT - ROOT CAUSE, CORRECTIVE ACTIONS AND INDEPENDENT.ASSESSMENT REGARDING DAMAGE TO FUEL ASSEMBLY I-024 AND INADVERTENT LIFTING OF FUEL ASSEMBLY SAN FUEL ACCOUNTABILITY AND FAILURE DETECTION As the result of damage to fuel assembly 1-024 and the inadvertent lifting of fuel assembly SAN-08, Consumers Power Company has performed analyses to determine their root causes and has taken actions to prevent their recurrence during fuel-cycle 11.
The analyses and corrective actions have been independently assessed to ensure their appropriateness and adequacy.
Additionally, actions to locate fuel -released from fuel assembly I-024 and to ensure that future similar fuel assembly failures will be promptly detected have been completed.
The analyses, corrective actions and assessments were verbally described to the NRC staff on September 9, 1993. This letter serves to document them.
Enclosure I documents our investigation to determine the root cause of the fuel ~od failure in fuel assembly I-024 and our planned and implemented and corrective actions to prevent recurrence. Enclosure I also provides updated failed fuel root cause information as conunitted in our August 16, 1993 response to the August 3, 1993 NRC request for additional information regarding the failure of fuel assembly I-024.
Enclosure II documents our investigation to determine the root cause of the inadvertent lifting of fuel assembly SAN-8 and our planned and implemented corrective actions to prevent recurrence.
Enclosure III documents our efforts to locate the fuel released from the damaged fuel assembly I-024, addresses the impact of not finding all of the released fuel in a discrete location within the primary coolant system or the fuel handling areas of the Containment and Auxiliary Building, and provides a description of our efforts to ensure that if there was a recurrence of a fuel RA 00
~gfi6~ 0930930
~
?)
sooo2ss Ei;t PDR
~CMS E:NE'l?GY COMPANY r:£22.
f I '
assembly failure similar to that of assembly 1-024, it would be promptly detected.
2 Enclosure IV documents the results of the independent safety assessment performed determine the appropriateness of the root cause analyses and corrective actions and to review the facts surrounding damage to fuel assembly 1-024 and the recent and previous inadvertent lifting of fuel assemblys with the upper guide structure.
/<S~ft~-----
Gerald B Slade General Manager CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Enclosures