Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable
Person / Time
ML15167A442
Site:	Monticello
Issue date:	06/16/2015
From:	Gardner P Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-15-034 LER 15-001-00
Download: ML15167A442 (4)
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LER-2015-001, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable

Event date:
Report date:
2632015001R00 - NRC Website
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Licensee Event Report

Monticello

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		Reporting criterion
05000263/LER-2015-001, Operations With A Potential To Drain The Reactor Vessel (OPDRV) Without Secondary Containment Operable	Operations With A Potential To Drain The Reactor Vessel (OPDRV) Without Secondary Containment Operable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2015-001, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable	Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable
05000263/LER-2015-002, From Monticello Nuclear Generating Plant Regarding Loss of Shutdown Cooling Due to Improperly Landed Jumper Wire	From Monticello Nuclear Generating Plant Regarding Loss of Shutdown Cooling Due to Improperly Landed Jumper Wire	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)
05000263/LER-2015-003, Regarding Use of the Reactor Water Cleanup System to Lower Level Without Declaring an Operation with a Potential to Drain the Reactor Vessel (OPDRV) with Secondary Containment Inoperable	Regarding Use of the Reactor Water Cleanup System to Lower Level Without Declaring an Operation with a Potential to Drain the Reactor Vessel (OPDRV) with Secondary Containment 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)
05000263/LER-2015-004, Regarding Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements	Regarding Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2015-005, Regarding Use of the Reactor Water Cleanup System to Lower Level Without Declaring an OPDRV with Secondary Containment Inoperable - Extent of Condition Review	Regarding Use of the Reactor Water Cleanup System to Lower Level Without Declaring an OPDRV with Secondary Containment Inoperable - Extent of Condition Review	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2015-006, Regarding Reactor Scram Due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line	Regarding Reactor Scram Due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000263/LER-2015-007, Regarding Loss of Residual Heat Removal Capability	Regarding Loss of Residual Heat Removal Capability	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)(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)

05000263/LER-2015-001, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable

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