05000348/LER-2005-002, Re Technical Specification 3.8.1 Violation Due to 1F Bus Synchroscope Failure
| ML060030364 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/03/2006 |
| From: | Stinson L Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-05-2318 LER 05-002-00 | |
| Download: ML060030364 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3482005002R00 - NRC Website | |
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1. M. Stinson (Mike)
Vice President Southern Nuclear Operating Company, Inc.
40 lnverness Center Parkway Post Office Box 1295 Birm~ngham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 January 3, 2006 Docket No.: 50-348 1
SOUTHERN k COMPANY Energy to Serve Your World SM NL-05-23 18 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2005-002-00 Technical Specification 3.8.1 Violation due to IF Bus Synchroscope Failure Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant Unit 1 Licensee Event Report (LER) No. 2005-002-00 is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B).
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, L. M. Stinson Enclosure: Licensee Event Report 2005-002-00 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, General Manager - Plant Farley RTYPE: CFA04.054; LC# 14372 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector - Farley
~ N R C FORM 366 u.S. NUCLEAR REGULATORY COMMISSION I APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digitslcharacters for each block)
- 1. FACILITY NAME Joseph M. Farley Nuclear Plant - Unit 1 Technical Specification 3.8.1 Violation due to IF Bus Synchroscope Failure
- 4. TITLE
, the NRC may not conduct or sponsor, and a person IS not required to respond to, the information collection.
I 1 On November 14, 2005, with the unit operating at 100% power, it was determined that Unit 1 had operated in a condition prohibited by Technical Specification (TS) 3.8.1 from 1 149 on November 1 1,2005, until 1647 on November 14,2005, in that an unrecognized failure of the IF (Train A Engineered Safety Features 4kv bus) synchroscope existed which rendered the 1 -2A (Train A) Emergency Diesel Generator (EDG) inoperable.
Troubleshooting of a failed 4kv bus voltmeter determined that the voltage indication was lost due to blown fuses that also disabled the bus synchroscope, resulting in TS 3.8.1 required action B.l not being met. The synchroscope is required per TS Surveillance Requirement (SR) 3.8.14 for the ability to synchronize the 1-2A EDG to an offsite source following power restoration after an LOSP. The ability of the EDG to start and load in response to an LOSP was unaffected by this failure. The 1 -2A EDG was declared inoperable for Unit 1 only, per I
TS 3.8.1 on November 14,2005 at 1647, and returned to service at 2200 following fuse replacement.
- 2. DOCKET NUMBER 05000 348 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 1XI NO The synchroscope failure event was caused by a short in a degraded voltmeter phase selector switch. The operation in a condition prohibited by TS was caused by cognitive personnel error and knowledge deficiency in that it was unclear to the operating crew that loss of the voltmeter indicated that the synchroscope might also be inoperable. The switch has been tagged to prevent use pending switch replacement. Guidance on actions to take based on loss of certain unique Emergency Power Board indications has been made.
- 3. PAGE 1 OF 4
- 8. OTHER FACILITIES INVOLVED NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100 FACILITY NAME FACILITY NAME
- 7. REPORT DATE
- 5. EVENT DATE FACTURER MANU-ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
SUBM ISSlON DATE
- 11. THIS REPORT IS SUBMllTED PURSUANT TO THE REQUIREMENTS OF 10 CFRS: (Check all that apply) 20.2201(b)
[7 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
[7 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50,73(a)(2)(viii)(A) 20.2203(a)(l) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50,73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(l )(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(l)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A)
[7 73.71(a)(4) 20.2203(a)(Z)(iv)
[7 50.46(a)(3)(ii) 50.73(4(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(4(2)(v)(C)
[7 OTHER 20.2203(a)(2)(vi)
?4 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 NRC Form 366A) (17)
Additional Information
PAGE (3) 4 OF 4
FACILITY NAME (1)
Jose~h M. Farlev Nuclear Plant Unit - 1 The following LERs have been submitted in the past two years on Technical Specification violations:
LER 2005-001-00 Unit 1 Technical Specification 3.3.2.C Violation due to Solid State Protection System Card Failure Troubleshooting DOCKET (2)
NUMBER 05000-348 LER 2004-001-00 Unit 2 Technical Specification 3.7.8 Violation due to Operation with One Train of Service Water Inoperable LER 2004-002-00 Unit 2 Plant Entered Mode 3 with One Train of Component Cooling Water Inoperable LER NUMBER (6)
LER 2004-003-00 Technical Specification 3.0.4 Violation Due to Turbine Driven Auxiliary Feedwater Pump Inoperable 4RC FORM 366 (7-2001)
JRC FORM 366A (7-2001)
REVISION NUMBER YEAR SEQUENTIAL NUMBER