05000458/LER-2020-001, Loss of Control Building Chill Water Due to Chiller Control Panel Installation Error
| ML20064D511 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/04/2020 |
| From: | Vercelli S Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-48008 LER 2020-001-00 | |
| Download: ML20064D511 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(i) |
| 4582020001R00 - NRC Website | |
text
-=- Entergy.
Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-635-5000 RBG-48008 March 4, 2020 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 / 2020-001-00, "Loss of Control Building Chill Water due to Chiller Control Panel Installation Error".
River Bend Station, Unit 1 NRC Docket No. 50-458 Renewed License No. NPF-47 In accordance with 1 O 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 225-881-4177.
SPV/twf
Enclosure:
cc:
Licensee Event Report 50-458 / 2020-001-00, "Loss of Control Building Chill Water due to Chiller Control Panel Installation Error".
NRC Region IV Regional Administrator, w/o Enclosure NRC 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 NRC Project Manager
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a
'_lt*ilr1(:t'.'
person is not required to respond to, the information collection.
3.Page River Bend Station 05000 458 1
OF 3
- 4. Title Loss of Control Building Chill Water due to Chiller Control Panel Installation Error
- 5. Event Date
- 6. LER Number
/ I
- 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 04 20 Facility Name Docket Number 01 09 20 20 001 00 03 NA 05000 NA
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 1 O 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)
D 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) 0 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) 100 D 20.2203(a)(2)(v)
D 50. 73(a)(2)(i)(A) 0 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 thorough investigation was performedwhich encompassed all possible component failures and human performance errors to determine the cause of the HVK-CHL 1 B failure. All possible causes were refuted.
CORRECTIVE ACTION TO PREVENT RECURRENCE An evaluation has been completed which credits manual action of dedicated operators when. assessing the Operability of HVK in similar events.
Although there were no faulted components identified for the HVK-CHL 1A failure, all components that were identified as having a potential intermittent failure will be replaced. This action is documented in the RBS corrective action program.
SAFETY SIGNIFICANCE
The Environmental Design Criteria maximum temperatures for the critical areas that the HVK system cools were not challenged. 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
of 3