05000424/LER-2014-004, Regarding Manual Reactor Trip Due to Loss Feedwater Flow
| ML14268A363 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/23/2014 |
| From: | Madison D Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-14-1442 LER 14-004-00 | |
| Download: ML14268A363 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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) 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)(i)(B), Prohibited by Technical Specifications |
| 4242014004R00 - NRC Website | |
text
Dennis R. Madison Vice President Vogtle-Unitsi & 2 Southern Nuciear Operating Company, inc.
7821 River Road Waynesboro, GA 30830 Tel 706.848.3151 Fax 205.980.3321 September 23,2014 Docket No:
50-424 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 A
NL-14-1442 Vogtle Electric Generating Plant - Unit 1 Licensee Event Report 1-2014-004-00 Manual Reactor Trio due to Loss of Feedwater Flow Ladies and Gentlemen:
In accordancewith the requirements of10CFR 50.73(a){2)(iv)(A), Southern Nuclear Operating Company (SNC)is submitting the enclosed Licensee EventReport, 1-2014-004-00. Thisletter contains no NRC commitments. If you haveanyquestions, pleasecontact Kevin Walden at(706) 848-4290.
Respectfully submitted, Dennis R. Madison Site Vice President - Vogtle DRM/KCW Enclosure: Unit 1 Licensee Event Report 1-2014-004-00 cc: Southern Nuclear Ooeratina Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. E. Tynan, Vice President - Fleet Operations Mr. B. L. Ivey,Vice President - Regulatory Affairs Mr. D. R. Madison, Vice President - Vogtle 1 &2 Mr. B. J. Adams, \\flce President - Engineering RType: CVC7000 U. S. Nuclear Reoulatorv Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Vogtle1 &2 Mr. L. M. Cain, Senior Resident Inspector - Vogtle 1 &2
Vogtle ElectricGenerating Plant - Unit1 Licensee Event Report 1-2014-004-00 Manual Reactor Trio due to Loss of Feedwater Flow Enclosure Unit1 Licensee Event Report 1-2014-004-00
NRC FORM 366 U.S. NUCLEAR REGUUTORY COMMISSION (02-2014)
^
licensee EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
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- 1. FACILITY NAME Vogtle Electric Generating Plant
- 2. DOCKET NUMBER 05000424
- 3. PAGE 1
OF 3
- 4. TITLE Manual Reactor Trip due to Loss of Feedwater flow
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAH VCAQ sequential rev NUMBER NO.
MONTH day YEAR FACILITY NAME N/A DOCKET NUMBER 7
27 2014 2014 -
004 00 09 25 2014 FACILITY NAME N/A DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTEDPURSUANTTO THE REQUIREMENTS OF 10 CFR §; (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(l) 50.73{a)(2)(l)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(il) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(li)(B) 50.73(a)(2)(vill)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73{a){2)(iil) 50.73(a)(2){ix)(A)
- 10. POWER LEVEL 100 20.2203(a)(2)(li) 50.36(c)(1)(ii)(A) 13 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 InAbstract below or In
A.
REQUIREIVIENT FOR REPORT This report is required per 10CFR 50.73(a)(2)(iv)(A) due to an unplanned manual actuation of the Reactor Protection System (RPS) and automatic actuation of the Auxiliary Feedwater System (AFW).
B.
UNIT STATUS AT TIIVIE OF EVENT Mode 1,100 percent power C.
DESCRIPTION OF EVENT
While operating at ICQ percent power, the Unit1 Main Feed Pump A speed began to lower resulting in a loss of sufficient feedwater flow to maintain Steam Generator levels. The Operators in the Control Room obsen/ed the loweringfeedwater flowand manually actuated the RPS, tripping the reactor priorto reaching any automatic RPS actuation setpoints. All rods fully inserted and the plant was stabilized in Mode 3. Decay heat was discharged to the condenser and no complications were experienced during the tripas all systems responded as designed.
The cause of the event was a loss in MFP A speed due to control oil leakage on the lockout solenoid valve.
D. CAUSE OF EVENT
The direct cause of the event was internal control oil leakage of the lockout solenoid valve which resulted inless than adequate controloil pressure. As a result, total feedwater flow to the Steam Generators lowered due to decreasing MFP A speed.
E.
SAFETY ASSESSMENT
When the reactor tripped, all rods fully inserted and allsafety systems actuated as designed. The unit was stabilized in Mode 3 at normal temperature and pressure and decay heat was discharged to the condenser. Because the plant responded as designed and there were no complications with plant shutdown, there was no adverse effect on plant safety or the health and safety of the public.
F.
CORRECTIVE ACTION
The solenoid valve was replaced and post maintenance testing was performed satisfactorily.
G. ADDITIONAL INFORMATION
1.
Failed Components:
MainFeed Pump A lockout solenoid valve.
2.
Previous Similar Events
INPO OE 21051 Recurring Solenoid and Relay Failures in Main Feedwater Pump Turbine Overspeed Test Circuit.
- 3. Energy Industry Identification System Code:
[JC]- Reactor Protection System [BA] - Auxiliary Feedwater [JB] - Feedwater/Steam GeneratorWaterLevel Control System NRCFORM36fiA(02'j014)