05000416/LER-2020-004, Automatic Reactor Scram Due to Reactor Feed Pump Trip
| ML20294A213 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/20/2020 |
| From: | Franssen R Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2020/00038 LER 2020-004-00 | |
| Download: ML20294A213 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(B), System Actuation |
| 4162020004R00 - NRC Website | |
text
GNRO-2020/00038 October 20, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Robert Franssen Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 10 CFR 50.73
SUBJECT:
Grand Gulf Nuclear Station, Unit 1 Licensee Event Report 2020-004-00, Automatic Reactor SCRAM due to Reactor Feed Pump Trip Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 Renewed License No. NPF-29 Attached is Licensee Event Report 2020-004-00, Automatic Reactor SCRAM due to Reactor Feed Pump Trip. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(B),
for any event or condition that resulted in manual or automatic actuation of the Reactor Protection System.
This letter contains no new Regulatory Commitments. Should you have any questions concerning the content of this letter, please contact Jim Shaw, Manager Regulatory Assurance at 601-437-2103.
Sincerely, Robert Franssen RF/fas Attachments: Licensee Event Report 2020-004-00
GNRO-2020/00038 Page 2 of 3 cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
GNRO-2020/00038 Page 3 of 3 Attachment Licensee Event Report 2020-004-00
NRC FORM 366 (08-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023 LICENSEE EVENT REPORT (LER)
(See Page 3 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 1. Facility Name Grand Gulf Nuclear Station, Unit 1
- 2. Docket Number 05000 416
- 3. Page 1 OF 3
- 4. Title Automatic Reactor SCRAM Due To Reactor Feed Pump Trip
- 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 N/A Docket Number 05000 N/A 08 24 2020 2020 - 004 -
00 10 20 2020 Facility Name Docket Number N/A 05000 N/A
- 9. Operating Mode
- 10. Power Level 1
14 Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; e-mail: oira_submission@omb.eop.gov. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 3. LER NUMBER Grand Gulf Nuclear Station, Unit 1 05000-416 YEAR SEQUENTIAL NUMBER REV NO.
2020
- - 004
- - 00 The root cause of the event was the failure of the minimum flow valve positioner for RFP B, which was installed during Preventive Maintenance activities. This caused the malfunctioning pilot valve condition, resulting in the minimum flow valve going closed and tripping RFP B on low suction flow.
Corrective Actions
The failed positioner for the RFP B Minimum Flow Valve was replaced and tested satisfactorily prior to unit restart.
Additionally, the positioner for the RFP A Minimum Flow Valve was also replaced as part of the initial extent of condition review.
The corrective action for the root cause is to develop work instructions for those Air Operated Valves (AOV) using ABB/Bailey AV1 or AV2 series positioners to inspect the positioners prior to installation.
Previous Similar Events
None.