05000348/LER-2007-003, Regarding Component Cooling Water Pump Breaker Failures
| ML072990364 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/19/2007 |
| From: | Jerrica Johnson Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-07-1965 LER 07-003-00 | |
| Download: ML072990364 (8) | |
| 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 |
| 3482007003R00 - NRC Website | |
text
J, R,Johnson Soulhern Nuclear Vice President* Farlev Operating Company. Inc.
Post Office DI awer 470 Ash/lord, Alabilma.36312-0470 Tel 334 81H~11 hl_ 3348144728 October 19, 2007 SOUIHERNA COMPANY Enug'110 Strut! You,' World' Docket Nos.: 50-348 NL-07-1965 50-364 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unil1 and 2 Licensee Event Report 2007-003-00 Component Cooling Water Pump Breaker Failures Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 73.71 (a){4), Southern Nuclear Operating Company (SNC) is submitting the enclosed Licensee Event Report.
This letter contains no NRC commitments. If you have any questions, please advise.
Si,/!'I! /J~
JZ:~nson 7 v
Vice President - Farley JRJ/JWK
Enclosure:
Licensee Event Report 2007-003-00
U. S. Nuclear Regulatory Commission NL*07*1965 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice Presiden1-Farley Mr. D. H. Jones. Vice Presiden1-Engineering RTYPE: CFA04.054; LC # 14659 U. S. Nuclear Regulatory Commission Dr. W. D. Travers. Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 1 Bnd 2 Licensee Event Report 2007-003-00 Component Cooling Water Pump Breaker Failures Enclosure Licensee Event Report 2007-003-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Joseph M. Farley Nuclear Plant - Unit I 05000348 1 OF 5
- 4. TITLE Component Cooling Water Pump Breaker Failures
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 09 05 2007 2007 - 003. 00 10 19 2007 05000 9, OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check a/1 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)
I 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) 100 o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) 181 50.73(a)(2)(v)(B) o 73.71 (a)(5) 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) 181 50.73(a)(2)(v)(D)
Specify in Abstract below or in =
(If mors space is required, use additional copies 01 (If more space is required, use additional copies of NRC Form 366A) (1n
Safety Assessment
FNP Unit 1 operated at 100 percent power in steady state throughout this event. System function would not have been lost unless an LOSP had occurred, since the 1A CCW pump was in fact already running. Based on subsequent troubleshooting, the failure of the 1A CCW pump breaker was an intermittent failure. The next close attempt for the breaker, with it undisturbed following the failure, was succesSful. Existing emergency procedures for an lOSP require a manual start attempt in the event of an automatic start failure. This indicates that the likelihood of successful manual restoration of system function from the control room was high. The total time system function would not have been available in the event of an LOSP was 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 15 minutes. An LOSP did not occur; system function other than auto-start was not lost, and therefore the health and safety of the public were unaffected by this event.
Cutler-Hammer breaker reliability: This was the first demand failure of a Cutler-Hammer breaker at FNP due to breaker problems and followed the changed operating practice in foot pedal manipulation.
Investigation determined that mechanical linkage was set up with inadequate margin on this breaker.
In conjunction with the incorrect linkage specification, the slight movement of the mechanical interlock induced by the foot pedal caused the breaker to fail to close on demand.
Allis-Chalmers breaker reliability: FNP has a project in progress to replace all safety related Allis Chalmers breakers with Cutler-Hammer breakers due to their aging and obsolescence.
Corrective Action
Both breakers were replaced and functionally tested satisfactorily.
Operations night orders were issued and procedures revised to eliminate manipulation of the foot pedal during pre-start breaker checks, and to lift the foot pedal following racking to properly reset the mechanical interlock linkage. This action ensures proper breaker operation.
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).
Cutler-Hammer breakers scheduled for installation will be verified to be within revised breaker linkage setup specifications prior to installation. The installation procedure has been revised to reflect the revised specifications and in accordance with the existing maintenance procedure development program will be incorporated into applicable new breaker PM procedures when they are developed.
All Allis-Chalmers 4kv breakers supplying safety related loads will be replaced by March 31, 2008.
NRC FORM36e (7-2001)
NRC FORM 3ll6A (7*2001)
NRC FORM 3&6A (7-2001)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
FACIUTV NAME (1)
DOCKET (2)
NUMBER LER NUMBER (6)
PAGE(3}
Joseph M. Farley Nuclear Plant Unit 1 05000348 YEAR I SEQUENTIAL IREVISION NUMBER NUMBER 5
OF 5
2007 003 00 NARRAllVE (ff more space is required, use additional copies ofNRC Form 366A) (11)
Additional Information
The following LEA has been submitted in the last two years on 4kv breaker issues:
LEA 2007-001-00 Units 1 and 2 Technical Specification 3.8.1 Violation Due to Failure of Breaker I Mechanism-Operated cell Switch The NAC has conducted an Augmented Inspection in response to this event.
NRC FORM 3ClO (7-2001)
NRC FORM 36M (7-2001)