05000364/LER-2013-001, Regarding 2C Steam Generator Flow Transmitter Inoperable Longer than Allowed by Technical Specifications
| ML13207A374 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/26/2013 |
| From: | Lynch T Southern Co, Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-13-1514 LER 13-001-00 | |
| Download: ML13207A374 (6) | |
| 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 |
| 3642013001R00 - NRC Website | |
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Thomas A. Lynch Vice President - Farley July 26, 2013 Southern Nuclear Operating Company, Inc.
Farley Nuclear Plant Post Office Drawer 470 Ashford. Alabama 36312 Tel334.814.4511 Fax 334.814.4728 Docket Nos.: 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant-Unit 2 Licensee Event Report 2013-001-00 SOUTHERN<<\\
COMPANY NL-13-1514 2C Steam Generator Flow Transmitter Inoperable Longer Than Allowed By Technical Specifications Ladies and Gentlemen:
In accordance with the requirements of 10CFR50.73(a)(2)(i)(B) Southern Nuclear Operating Company hereby submits the enclosed Licensee Event Report. This letter contains no NRC commitments. If you have any questions, please contact Bill Arens at (334) 814-4765.
Sincerely, 1L;J-T. A. Lynch Vice President - Farley TALJWNA Enclosure: Unit 2 Licensee Event Report 2013-001-00 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. B. L. lvey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President-Fleet Operations Mr. C. R. Pierce, Director-Regulatory Affairs Mr. J. G. Horn, Regulatory Affairs Manager-Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident-Farley
Joseph M. Farley Nuclear Plant - Unit 2 NL-13-1514 2C Steam Generator Flow Transmitter Inoperable Longer Than Allowed By Technical Specifications Unit 2 Licensee Event Report 2013-001-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Joseph M. Farley Nuclear Plant, Unit 2
- 2. DOCKET NUMBER 05000 364
- 3. PAGE 1 OF 4
- 4. TITLE 2C Steam Generator Flow Transmitter Inoperable Longer Than Allowed by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05 29 2013 2013 - 001 - 00 07 26 2013 FACILITY NAME DOCKET NUMBER
- 9. OPERATING MODE 1
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(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) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in Based on the above considerations and on the FT-494 setpoint being slightly above allowable tolerance but otherwise operable this condition is considered to have low safety significance.
Corrective Action
FT-494 was rescaled per work order SNC 459224 and returned to service at 1642 on June 1, 2013. Further corrective actions for the FT-494 high steam flow setpoint being above the allowable value have yet to be determined. Upon completion of the causal analysis, this Licensee Event Report will be supplemented by September 13, 2013.
The failure of the plant staff to identify the event that occurred on January 4, 2012 as requiring a Licensee Event Report has been entered in the plant corrective action program as condition report 675409.
Additional Information
A review of previously submitted Licensee Event Reports identified no similar issues being reported within the previous three years. There have been three other instances in the previous three years of steam flow transmitters requiring re-normalization following the evaluation of beginning-of-cycle data. In all of these cases, the high steam flow setpoints remained within the accuracy requirements of Technical Specifications and operability of the steam flow channel was not affected. These occurrences are documented in condition reports 55575 (for Unit 1 FT-485), 485511 (for Unit 1 FT-484), and 646824 (for Unit 2 FT-485).