05000348/LER-2005-001, Unit 1 Regarding Technical Specification 3.3.2.C Violation Due to Solid State Protection System Card Failure Troubleshooting
| ML051790041 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/23/2005 |
| From: | Stinson L Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-05-1061 LER 05-001-00 | |
| Download: ML051790041 (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)(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 |
| 3482005001R00 - NRC Website | |
text
L M. Stinson (Mike)
Vice President Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 4
SOUTHERN A COMPANY Energy to Serve YourWorld' NL-05-1061 June 23, 2005 Docket No.: 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit I Licensee Event Report 2005-001 -00 Technical Specification 3.3.2.C Violation due to Solid State Protection System Card Failure Troubleshooting Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant - Licensee Event Report (LER) No. 2005-001 -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 LMS/was/sdl Enclosure: Licensee Event Report 2005-001-00 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, General Manager - Plant Farley RTYPE: CFAO4.054; LC# 14291 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
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
'6-2004)
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, the NRC may digits/characters for each block) not or sponsor, and a person Is not required to respond to, the
- 3. PAGE Joseph M. Farley Nuclear Plant - Unit 1 05000348 OF 4
- 4. TITLE Technical Specification 3.3.2.C Violation due to Solid State Protection System Card Failure Troubleshooting
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED S
U I
RFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SENUENRTIAL EV.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 04 28 2005 2005 - 001 -
00 06 23 2005 05000
- 9. OPERATING MODE
- 11. THI S
REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) 0 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
E 50.73(a)(2)(viii)(A) o 20.2203(a)(1)
El 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) a 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
E 50.73(a)(2)(iv)(A)
Dl 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2) 0l 50.73(a)(2)(v)(A)
Dl 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5) 100 El 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
[I 50.73(a)(2)(v)(C)
D OTHER El 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B)
El 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 Forn 366A) (17)
Corrective Action
The failed card was replaced and has been returned to the vendor for analysis.
Preplanned systematic diagnostic guidance will be developed and provided to planning personnel that will include lessons learned from this event by August 15, 2005.
Additional Information
The following LERs have been submitted in the past two years on Technical Specification violations:
LER 2003-002-00 Unit I, Reactor Vessel Head Set in Place with Technical Specification 3.4.12 Not Met.
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 2004-003-00 Technical Specification 3.0.4 Violation Due to Turbine Driven Auxiliary Feedwater Pump Inoperable.
NRC FORM 366 (7-2001)