05000416/LER-2020-003, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram

Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram

ML20280A586
Person / Time
Site:	Grand Gulf
Issue date:	10/06/2020
From:	Franssen R Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2020/00037 LER 2020-003-00
Download: ML20280A586 (7)

LER-2020-003, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation
4162020003R00 - NRC Website

text

GNRO-2020/00037 October 6, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Grand Gulf Nuclear Station, Unit 1 Licensee Event Report 2020-003-00, Manual Reactor SCRAM Due To Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level SCRAM Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 Renewed License No. NPF-29 Attached is Licensee Event Report 2020-003-00, Manual Reactor SCRAM Due To Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level SCRAM. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(A), 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 2020-003-00 Robert Franssen Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500 Entergy Operations, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150 10 CFR 50.73

GNRO-2020/00037 Page 2 of 2 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

Attachment to GNRO-2020/00037 Licensee Event Report 2020-003-00

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 4

4. Title Manual Reactor SCRAM Due To Turbine High Pressure Control Valve Malfunction And Automatic Reactor Water Level SCRAM

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 08 2020 2020 - 003 -

00 10 6

2020 Facility Name Docket Number N/A 05000 N/A

9. Operating Mode

10. Power Level 1

86 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

- 003

- 00 Actions to correct the second Root Cause will include revision to process procedure for critical procurements to incorporate requirements to document and track specific methods utilized to verify critical characteristics are met.

The volume booster on the Feedwater startup level control valve was replaced.

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