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GNRO-2020/00028 July 20, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Grand Gulf Nuclear Station, Unit 1 Licensee Event Report 2020-002-00, Reactor Scram Due to Turbine Trip Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 Renewed License No. NPF-29 Attached is Licensee Event Report 2020-002-00, Reactor Scram Due To Turbine Trip.
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, Eric A. Larson EAL/fas Attachments: Licensee Event Report 2020-002-00 Eric A. Larson 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-2020/00028 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-2020/00028 Page 3 of 3 Attachment Licensee Event Report 2020-002-00
NRC FORM 366 (04-2020)
NRC FORM 366 (04-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2020 LICENSEE EVENT REPORT (LER)
(See Page 2 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 Reactor SCRAM Due to Main Turbine 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 05 25 2020 2020
- - 002
- - 00 07 20 2020 Facility Name Docket Number N/A 05000 N/A
- 9. Operating Mode 1
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
- - 002
- - 00 Previous Similar Event:
Entergy conducted a three-year review of the relevant licensee event reports and determined that there were no
similar events
These review results may change based on the causal analysis and a subsequent review of the past SCRAMs.
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| 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip | Reactor Scram Due to Main Turbine Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2020-002, Reactor Scram Due to Turbine Trip | Reactor Scram Due to Turbine Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-003-01, 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-004-01, Automatic Reactor Scram Due to Reactor Feed Pump Trip | Automatic Reactor Scram Due to Reactor Feed Pump Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-004, Automatic Reactor Scram Due to Reactor Feed Pump Trip | Automatic Reactor Scram Due to Reactor Feed Pump Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram | Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(viii)(A) | | 05000416/LER-2020-005-01, Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram | Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-005, Re Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram | Re Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | | 05000416/LER-2020-006-01, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2020-006, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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