05000348/LER-2007-003-01, Component Cooling Water Pump Breaker Failures
| ML083190816 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/14/2008 |
| From: | Jerrica Johnson Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-08-1712 LER 07-003-01 | |
| Download: ML083190816 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3482007003R01 - NRC Website | |
text
J.R.Johnson Southern Nuclear Vice President - Farley Operating Company, Inc.
Post Office Drawer 470 Ashford, Alabama 36312-0470 Tel 334.814.4511 Fax 334.814.4728 SOUTHERN A.
November 14, 2008 COMPANY Energy to Serve :Your Wor/d SM Docket Nos.: 50-348 NL-08-1712 50-364 U. S. Nuclear RegUlatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 and 2 Revision to Licensee Event Report 2007-003-01 Component Cooling Water Pump Breaker Failures Ladies and Gentlemen:
By letter dated October 19, 2007 Southern Nuclear Operating Company (SNC) provided Licensee Event Report (LER) 2007-003-00, "Component Cooling Water Pump Breaker Failure'" for Joseph M. Farley Nuclear Plant (FNP) Units 1 and 2 (ML072990364). In this LER, SNC detailed an event in which the 4160 volt Cutler-Hammer breaker failed to operate on demand which resulted in the Component Cooling Water (CCW) system being inoperable. SNC determined that the failure of the Cutler-Hammer breaker was due to a combination of depressing the breaker foot pedal inappropriately and inadequate linkage margin caused by the setup of the breaker linkage in the trip latch plunger interlock.
In LER 2007-003-00, SNC presented as one of the corrective action the following:
"To provide additional reliability margin and assurance of breaker closure for reliable operation, the breaker linkage setup specifications were revised.
Cutler-Hammer breakers in safety related applications will be verified to be within the revised linkage setup specifications by November 30,2008 (end of Unit 2 Refueling Outage 19)."
SNC has determined that it will not be able to complete this inspection on 13 of 80 Cutler-Hammer breakers in safety related applications by November 30, 2008.
SI\\JC has scheduled the remaining inspections for completion by August 31, 2009. The revised LER 2007-003-01 is provided in the enclosure and includes the basis for this extension.
U. S. Nuclear Regulatory Commission NL-08-1712 Page 2 This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, 9;J~
Vice President - Farley
- .JRJ/CHM
Enclosure:
Licensee Event Report 2007-003-01 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; LC # 14856 U. S. Nuclear Regulatorv Commission Mr. L. A. Reyes, Regional Administrator Mr. K. D. Feintuch, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 1 and 2 Revision to Licensee Event Report 2007-003-01 Component Cooling Water Pump Breaker Failures Enclosure Licensee Event Report 2007-003-01
EXPIRES: 08/31/2010 incorporate<;t into the burden
- - 5 F52), U.S.
of 7 DOCKET NUMBER 05000 DOCKET NUMBER 05000 REPORTABLE TO EPIX Y
YEAR DAY NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 (9-2007)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Joseph M. Farley Nuclear Plant - Unit 1 05000348 1
~. TITLE Component Cooling Water Pump Breaker Failures
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NUMBER NO.
FACILITY NAME 09 05 2007 2007 - 003 -
01 11 14 2008
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) 1 o 20.2201(d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1 )(i)(A) o 50.73(a)(2)(iii) o 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1 )(ii)(A) o 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71 (a)(4) o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71 (a)(5) 100 o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(B)
~ 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required. use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required. use additional copies of (If more space is required. use additional copies of NRC Form 366A) (17)
The remaining 13 breakers were subjected to a multi-point inspection during their installation.
Two of these checks together provide confidence that the mechanical trip plunger is positioned correctly and the closing circuit will function when called upon. First, a continuity reading was taken on the closing control circuits for the breakers and second, the interlock plunger at the end of the linkage assembly is verified to be properly engaged within the switchgear cubicle guide rail notch whenever the breaker is racked to the connect position. A sample of the breaker population has been re-inspected after the initial multipoint inspections to ensure that the inspection points have remained consistent. The interlock plunger position is also verified after any breaker racking operation to be properly engaged in the guide rail notch. Knowing the proper position of the switch and proper position of the interlock plunger gives assurance the breaker will function as designed.
Therefore, the inspections that have been performed on these 13 breakers, the requirement to verify the interlock plunger position after each racking operation, and the fact that all installed Cutler-Hammer breakers at FNP have functioned properly in over 1,600 demands since December 2007, with no linkage related failures, provide confidence that the current plunger setting of 2 1/16 inch is adequate for these 13 breakers to continue to function properly until August 31,2009, when the setting adjustment can be made to provide additional margin. PRINTED ON RECYCLED PAPER)