05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator Level
| ML23345A157 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 12/11/2023 |
| From: | Blankenship J Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LER 2023-003-00 | |
| Download: ML23345A157 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| 2442023003R00 - NRC Website | |
text
Constellation December 11, 2023 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 RE. Ginna Nuclear Power Plant James D. Blankenship S,te v,ce President R E. G,nna Nuclear Power Plant 1503 Lake Rd Ontario. NY 14519 315*791*5200 Office 1ames.blankensll1pca constellation.com www.constellation.com Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
LER 2023-003, Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to low Steam Generator Level The attached Licensee Event Report (LER) 2023-003 is submitted in accordance with 10 CFR 50.73 under the provisions of NUREG-1022, Revision 3, Event Reporting Guidelines 10 CFR 50.72 and 50.73. There are no new commitments contained in this submittal. This submittal is for Revision O of the LER.
Should you have any questions regarding this submittal, please contact Justin Knowles at (315) 791 -3393.
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James D. Blankenship Attachment: LER 2023-003, Revision 0 cc:
NRC Regional Administrator, Region 1 NRC Project Manager, Ginna NRC Resident Inspector, Ginna (e-mail)
Attachment LER 2023-003, Revision 0
Abstract
R.E. Ginna Nuclear Power Plant, Unit 1
00244 4
Manual Reactor Trip due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation due to low Steam Generator Level 10 12 2023 2023 003 00 12 11 2023 1
100
Justin Knowles, Regulatory Assurance Manager 315-791-3393 B
LD PCV M0120 Y
03 08 2023 On 10/12/2023, Ginna Unit 1 experienced an uncomplicated manual reactor trip due to high Main Condenser back pressure and a valid Auxiliary Feedwater actuation due to low Steam Generator level. At 2116, Operations received a high limit alarm for Air Ejector Mass Flow Rate and observed condenser vacuum degrading and generator output beginning to lower. Field personnel began bypassing the Main Air Ejector Steam Pressure Control Valve to restore steam to the Air Ejectors. Concurrently with actions in the field, the Main Control Room (MCR) Operators began a procedurally directed downpower. At 2127, the five-minute restriction for turbine operation in the 'Back Pressure' region was exceeded and the MCR Unit Supervisor directed a reactor trip as procedurally required.
Loss of supply air to the Main Air Ejector Steam Pressure Control Valve was due to the Instrument Air (IA) Pressure Control Valve (PCV) not providing adequate output pressure to keep the valve open. The IA PCV was replaced and tested satisfactory prior to return to service. This event is being evaluated and additional information may be provided in the supplement.
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- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050
V. CORRECTIVE ACTIONS
The Instrument Air Pressure Control Valve was replaced and tested satisfactory prior to return to service.
This event is being evaluated and actions taken or planned to prevent occurrence will be provided in the supplement.
VI. ADDITIONAL INFORMATION
None A. FAILED COMPONENTS:
Instrument Air Pressure Control Valve to the Main Air Ejector Steam Pressure AOV B. PREVIOUS LERs ON SIMILAR EVENTS:
A LER historical search was conducted and no similar LER events were identified.
C. THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:
COMPONENT - Pressure Control Valve IEEE 803 FUNCTION NUMBER - PCV IEEE 805 SYSTEM IDENTIFICATION - LD 4
4 R.E. Ginna Nuclear Power Plant, Unit 1 00244 2023 003 00
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