05000458/LER-2019-003, Manual Reactor Scram Initiated in Response to Loss of Feedwater Due to Abnormal Plant Configuration
| ML19211A854 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/30/2019 |
| From: | Vercelli S Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47964 LER 2019-003-00 | |
| Download: ML19211A854 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4582019003R00 - NRC Website | |
text
Entergy Operations, Inc.
River Bend Station
~ Entergx 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-635-5000 RBG-47964 July 30, 2019 Steven P. Vercelli Site Vice President River Bend Station 10 CFR 50.73 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738
Subject:
Licensee Event Report 50-458 I 2019-003-00, "Manual Reactor Scram Initiated in Response to Loss of Feedwater due to Abnormal Plant Configuration".
River Bend Station, Unit 1 NRG Docket No. 50-458 Renewed License No. NPF-47 In accordance with 10 CFR 50.73, enclosed is the subject Licensee Event Report. This document contains no commitments. If you have any questions, please contact Mr. Tim Schenk at 225-381-4177.
Sincer~/J ~,
SPV/twf
Enclosure:
cc:
Licensee Event Report 50-458 I 2019-003-00, "Manual Reactor Scram Initiated in Response to Loss of Feedwater due to Abnormal Plant Configuration".
NRG Region IV Regional Administrator, w/o Enclosure NRG Senior Resident Inspector - River Bend Station, Unit 1 Ji Young Wiley, Department of Environmental Quality, Office of Environmental Compliance, Radiological Emergency Planning and Response Section Public Utility Commission of Texas, Attn: PUC Filing Clerk NRG Project Manager
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
3.Page River Bend Station - Unit 1 05000 458 1
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- 4. Title Manual Reactor Scram Initiated in Response to Loss of Feedwater due to Abnormal Plant Configuration
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved I
Sequential I Rev Facility Name Docket Number Month Day Year Year Number No.
Month Day Year NA 05000 NA Facility Name Docket Number 05 31 2019 2019 -
003 -
00 07 30 2019 NA 05000 NA
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)
D 20.2201(b)
D 20.2203(a)(3)(i)
D 50. 73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50. 73(a)(2)(ii)(B)
D 50. 73(a)(2)(viii)(B) 1 D
D D
D 20.2203(a)(1) 20.2203(a)(4)
- 50. 73(a)(2)(iii)
- 50. 73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A) 0 50. 73(a)(2)(iv)(A)
D 50. 73(a)(2)(x)
- 10. Power Level D 20.2203(a)(2)(ii)
D 50.36(c)(1 )(ii)(A)
D 50. 73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 32 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50. 73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50. 73(a)(2)(vii)
D 73. 77(a)(2)(ii)
D 50. 73(a)(2)(i)(C)
D Other (Specify in Abstract below or in
- A Standing Order was put in place to provide guidance to Operators in a case where a LPFH string must be removed from service.
The following actions have been assigned to prevent a recurrence of this event and are documented in the station's corrective action program.
- Operating procedures will be revised so that they accurately reflect the correct technical data and required operator actions for operation with one LPFW string in service.
- Create and present a Case Study to station leadership to review the management decisions made throughout this event.
- Revise and implement governance for emergent issue identification, adverse condition monitoring, and operational decision making guidelines.
SAFETY SIGNIFICANCE
No plant parameters requiring the automatic actuation of the Standby Diesel Generators [EK] or the Emergency Core Cooling Systems were exceeded. The RCIC system operated properly in response to the operators' manual control and provided high pressure makeup to the Reactor. A Reactor water level 3 signal was received due to the second FWP trip and the plant responded as designed. Control of Reactor pressure was accomplished by rejecting steam to the Main Condenser [SG]. The plant was safely placed in cold shutdown. There were no actual nuclear or radiological safety consequences due to this event. This event was of minimal significance to the health and safety of the public.
(NOTE: Energy Industry Identification System component function identifier and system name of each component or system referred to in the LER are annotated as (**XX**) and [XX], respectively.) Page 3
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