LER-2007-003, Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability |
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10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
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| 2552007003R00 - NRC Website |
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Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 September 14, 2007 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capabilitv
Dear Sir or Madam:
By letter dated April 25, 2007, Entergy Nuclear Operations, Inc. transmitted Palisades Nuclear Plant Licensee Event Report (LER)07-003, "Potential For Reduced Component Cooling Water Cooling Capability." The LER described the potential effects on the component cooling water (CCW) system from radiant heat damage to associated equipment cable jackets. Specifically, the LER described a combination of two postulated cable faults which could result in the inoperability of CV-0823, CCW Heat Exchanger Service Water Outlet Valve, and P-52B, CCW Pump, causing a condition in which there would be less than 100% of the required post-accident CCW cooling. The occurrence was reported in accordance with 10 CFR 50.73(a)(2)(v)(B) as a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat.
Subsequent evaluation of past operability concluded that these cables would not have failed as conservatively postulated in LER 07-003, and are considered to have been operable. This conclusion was based, in part, on accident simulation testing of the removed cables, which showed acceptable results.
Since the cables were not inoperable, as was previously reported in LER 07-003, there was no condition that could have prevented the fulfillment of the safety function of structures or systems needed to remove residual heat. Consequently, the reporting criterion of 10 CFR 50.73(a)(2)(v)(B) is not applicable. Therefore, LER 07-003 is being canceled.
Document Control Desk Page 2 Summarv of Commitments This letter contains no new commitments and no revision to existing commitments.
Site vice President Palisades Nuclear Plant CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
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| 05000255/LER-2007-001, Failure to Perform Offsite Power Source Check | Failure to Perform Offsite Power Source Check | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-2007-002, Re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw | Re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000255/LER-2007-003, Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability | Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000255/LER-2007-004, Regarding Shutdown Cooling Train Inoperable | Regarding Shutdown Cooling Train Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000255/LER-2007-006, Emergency Diesel Generator Inoperable in Excess of Technical Specification Requirements | Emergency Diesel Generator Inoperable in Excess of Technical Specification Requirements | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-2007-007, Fuel Handling Area Ventilation System Inoperable | Fuel Handling Area Ventilation System Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000255/LER-2007-008, Regarding Auxiliary Feedwater Pump Inoperable in Excess of Technical Specification Requirements Due to a Postulated Steam Line Break | Regarding Auxiliary Feedwater Pump Inoperable in Excess of Technical Specification Requirements Due to a Postulated Steam Line Break | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | | 05000255/LER-2007-009, For Palisades, Regarding Automatic Valve in Emergency Core Cooling System Inoperable in Excess of Technical Specification Requirements | For Palisades, Regarding Automatic Valve in Emergency Core Cooling System Inoperable in Excess of Technical Specification Requirements | 10 CFR 50.73(a)(2)(x) | | 05000255/LER-2007-010, Technical Specification Action Requirements Not Met for Battery Cell Parameter Outside Allowable Limits | Technical Specification Action Requirements Not Met for Battery Cell Parameter Outside Allowable Limits | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) |
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