Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station
Person / Time
ML102230421
Site:	Fort Calhoun
Issue date:	08/04/2010
From:	Reinhart J Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-10-0054 LER 09-003-00
Download: ML102230421 (1)
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LER-2009-003, Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station

Event date:
Report date:
2852009003R00 - NRC Website
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Omaha Public Power Disrid 444 South 1 6th Street Mall Omaha, NE 68102-2247 August 4, 2010 LIC-10-0054 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

References:

Subject:

Docket No. 50-285

Letter from OPPD (R. A. Reinhart) to NRC (Document Control Desk), dated August 10, 2009 (LIC-09-0053)

Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station This letter constitutes notification to the NRC of the cancellation of Fort Calhoun's Licensee ýEvent-Report-. (LER)..2009-003, "Void in Safety Injection Piping During Operation Due to Inadequate Procedural Guidance."

A detailed: analysis wa s performed. on: the effect: of the void on the safety injection system. The analysis,.concludes that"the void will pass through the safety injection pump with. little or no affect on.the,operation: of the.pump and that no water hammer affects would be induced. Based on these results it is concluded that the pump and piping would perform their intended safety function and would not be affected by the void. Therefore, the condition was not reportable.

If you should have any questions, please contact me.

Sincerely, JAR/EPM c:

E. E., Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project.Manager.

J. C. Kirkland, NRC Senior; Resident Inspector-.

INPO Records Center I

I Employment with Equal; Opportnit.y.

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Licensee Event Report

Fort Calhoun

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		Reporting criterion
05000285/LER-2009-001, Failure to Monitor Waste Gas Transfer Due to Operator Error	Failure to Monitor Waste Gas Transfer Due to Operator Error	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)
05000285/LER-2009-002, Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor	Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor	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)
05000285/LER-2009-003, Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station	Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station
05000285/LER-2009-004, Regarding Containment Integrity Was Unknowingly Violated During Performance of Leak Test	Regarding Containment Integrity Was Unknowingly Violated During Performance of Leak Test	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)
05000285/LER-2009-005, From Fort Calhoun Station Inoperable Auxiliary Feedwater Train Due to an Inoperable Injection Valve	From Fort Calhoun Station Inoperable Auxiliary Feedwater Train Due to an Inoperable Injection Valve	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)

05000285/LER-2009-003, Cancellation of Licensee Event Report 2009-003 for the Fort Calhoun Station

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