05000348/LER-2008-002, Unit 1 TS 3.0.3 Entry Due to Inoperability of Residual Heat Removal System
| ML081640619 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/11/2008 |
| From: | Jerrica Johnson Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-08-0797 LER 08-002-00 | |
| Download: ML081640619 (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)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3482008002R00 - NRC Website | |
text
J. R. Johnson Southern Nuclear Vice President Farley Operating Company, Illc.
Post Office Draws, 470 Ashford. Alabama 36312 -0470
)81334.814.4511 Fax 334.814.4728 SOUTHERN A COMPANY June 11, 2008 Energy to Serve lOurWorld-'
Docket No.:
50-348 NL-08-0797 U. S. Nuclear Regulatory Commission AITN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2008-002-00 TS 3.0.3 Entry Due to Inoperability of Residual Heat Removal System Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B), 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.
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. R. Johnson Vice President - Farley JRJ/CHM/daj Enclosure: Unit 1 Licensee Event Report 2008-002-00 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; LC # 14771 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. A. Jervey, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2008-002-00 TS 3.0.3 Entry Due to Inoperability of Residual Heat Removal System Enclosure Unit 1 Licensee Event Report 2008-002-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010
, 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 1
- 2. DOCKET NUMBER 05000 348
- 3. PAGE 1 of 4
- 4. TITLE TS 3.0.3 Entry Due to Inoperability of Residual Heat Removal System
- 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 05000 04 15 2008 2008 - 002 - 00 06 11 2008 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100
- 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 (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) PRINTED ON RECYCLED PAPER)
Safety Assessment
This event had no adverse effect on the safety and health of the public.
The RHR system at FNP consists of two independent, redundant, 100% capacity, high volume low pressure pumps that supply water from the Refueling Water Storage Tank (RWST) or the containment sump, to the Reactor Coolant System. The Service Water system consists of two independent, multi-pump, 100% capacity supporting systems that provides a cooling medium to the Engineered Safety Feature which includes the associated RHR Pump Room Coolers and heat exchangers.
During the 100 minutes that the B-Train Service Water system was declared inoperable and the A-Train Unit 1 RHR pump was inoperable due to planned maintenance, no demands were placed on the Unit 1 RHR or Service Water systems and the B-Train battery was at full capacity. The basic function of the battery system at Service Water is to provide control power to breakers. Even if an event had required the repositioning of Service Water breakers, adequate power was available in the B-Train on service battery with an additional 100% capacity available in the standby B-Train battery with operator action. These two fully charged batteries provided 100% redundancy. In addition, Operations and Maintenance personnel were present at the Service Water structure troubleshooting the problem with the 1-2L LCC. If required power could have been restored to the battery chargers in short order by opening the 1-2L LCC tie breaker and supplying the battery chargers from the Unit 2 side of the LCC. Thus this event did not adversely affect the safety and health of the public.
Corrective Action
The 1-2L LCC has been fully inspected and the damaged bus bar replaced.
Based on the extent of condition review, a corrective action plan has been developed to perform periodic testing or inspection of the 4160 volt switchgear, 600 volt LCCs, and 600 volt MCCs to ensure the integrity of the bolted connections on the bus bars.
The A-Train LCC 1-2K will be inspected by June 30, 2008.
Additional Information
LER 2007-001-00 Unit 1 Technical Specification 3.8.1 Violation Due to Failure of Breaker /
Mechanism-Operated Cell Switch LER 2008-001-00 Unit 1 Emergency Diesel Generator 1B Exhaust Pipe Failure