Transmittal of Special LER 10-003-00 Report for Joseph M. Farley Nuclear Units 1 and 2, on Alternate AC Source Out-of-Service
Person / Time
ML103260374
Site:	Farley
Issue date:	11/09/2010
From:	Ajluni M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-2251 LER 10-003-00
Download: ML103260374 (3)
v • d • e

LER-2010-003, Transmittal of Special LER 10-003-00 Report for Joseph M. Farley Nuclear Units 1 and 2, on Alternate AC Source Out-of-Service

Event date:
Report date:
3482010003R00 - NRC Website
v • d • e

text

Mark J. Ajiluni, P.E.

Nuclear Licensing Director Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 November 19, 2010 Docket Nos.: 50-348 50-364 SOUTHERN COMPANY NL-10-2251 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2 Special Report 2010-003-00. Alternate AC Source Out-of-Service Report Ladies and Gentlemen:

In accordance with the requirements of Technical Specification 5.6.11, the enclosed Special Report No. 2010-003-00 is submitted.

This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.

Sincerely, M. J. Ajluni Nuclear Licensing Director MJA/WDO Enclosure: Special Report 2010-003-00 cc:

Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. P. G. Boyle, NRR Project Manager Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley iI5~C>

Joseph M. Farley Nuclear Plant, Unit I and Unit 2 Special Report 2010-003-00, Alternate AC Source Out-of-Service Report Enclosure Special Report 2010-003-00

Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2 Special Report 2010-003-00, Alternate AC Source Out-of-Service Report Enclosure Special Report 2010-003-00 This Special Report is being submitted due to the Unit 1 and Unit 2 Alternate AC (AAC) source, 2C Diesel Generator (DG), not being restored to operable status within 10 days.

Technical Specification 5.6.11 requires notification to the NRC if the AAC source is out of service for greater than 10 days.

At 8:20 p.m. on October 22, 2010 the 2C DG was declared inoperable, for Unit 1 only, due to scheduled Service Water (SW) piping replacement work during the Unit 1 refueling outage. The duration of the SW piping replacement went beyond 10 days and therefore a notification to the NRC is required.

The 2C DG was placed back in a fully available status on November 4, 2010 at 3:27 p.m. when SW was restored. Surveillance testing was completed for the 2C DG on November 4, 2010 at 5:27 p.m.

E-I

Licensee Event Report

Farley

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000364/LER-2010-001, Regarding Unplanned LOSP During SI with LOSP Testing	Regarding Unplanned LOSP During SI with LOSP Testing	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)
05000348/LER-2010-001, Regarding Failure to Deactivate Containment Isolation Valve	Regarding Failure to Deactivate Containment Isolation 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)(B)
05000364/LER-2010-002, Reactor Trip Due to Failed Feedwater Regulating Valve Controller	Reactor Trip Due to Failed Feedwater Regulating Valve Controller	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)(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)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000348/LER-2010-002, Regarding Two Auxiliary Feedwater Pumps Inoperable	Regarding Two Auxiliary Feedwater Pumps 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)
05000348/LER-2010-003, Transmittal of Special LER 10-003-00 Report for Joseph M. Farley Nuclear Units 1 and 2, on Alternate AC Source Out-of-Service	Transmittal of Special LER 10-003-00 Report for Joseph M. Farley Nuclear Units 1 and 2, on Alternate AC Source Out-of-Service
05000364/LER-2010-003, Regarding Power Supply to 1-2R Load Center Unavailability	Regarding Power Supply to 1-2R Load Center Unavailability	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)(i)(8)
05000348/LER-2010-004, Joseph M Farley Nuclear Plant, Unit 1, Regarding Loss of Refueling Integrity	Joseph M Farley Nuclear Plant, Unit 1, Regarding Loss of Refueling Integrity	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)

05000348/LER-2010-003, Transmittal of Special LER 10-003-00 Report for Joseph M. Farley Nuclear Units 1 and 2, on Alternate AC Source Out-of-Service

text

Navigation menu

Search