05000244/LER-2021-002, Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level Due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves
| ML21336A082 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/02/2021 |
| From: | Swift P Exelon Generation Co LLC |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 2021-002-00 | |
| Download: ML21336A082 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| 2442021002R00 - NRC Website | |
text
Exelon Generation December 2, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 RE. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 Paul M. Swift Site Vice President R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario. NY 14519 315-791-5200 Office www.exeloncorp.com
Subject:
LER 2021-002, Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves The attached Licensee Event Report (LER) 2021-002 is submitted under the provisions of NUREG-1022, Event Reporting Guidelines. 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 Chris Bradshaw at (315) 791-3246.
Sincerely,
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Paul Swift Attachment: LER 2021-002 cc:
NRC Regional Administrator, Region 1 NRC Project Manager, Ginna NRC Resident Inspector, Ginna (e-mail)
Attachment LER 2021-002, Revision 0
Abstract
R.E. Ginna Nuclear Power Plant, Unit 1 244 4
Valid Auxiliary Feedwater System Actuation on Lowered Steam Generator Level due to Failure to Control Main Feed Water Flow and Delay in Closing Main Steam Isolation Valves 10 04 2021 2021 002 00 12 02 2021 3
000
Christopher Bradshaw, Regulatory Assurance Manager 3157913246 N/A N/A N/A N/A N/A
On 10/4/21 during a shutdown for the 2021 Refueling Outage, following the planned reactor trip, Reactor Coolant Average Temperature (Tavg) lowered due to overfeeding the 'B' Steam Generator (S/G). To maintain Tavg, feed to the S/Gs was minimized. During the cooldown, 'A' S/G lowered and a valid actuation of the Auxiliary Feedwater (AFW) System occurred. The valid actuation of the AFW System is reportable per 10CFR50.72(b)(3)(iv)(A) and 10CFR50.73.(a)(2)(iv)(A).
No equipment position changes were noted as a result of the actuation, which is the expected response for the given plant conditions. The causes of this event were Operators failed to control Main Feedwater Flow following Reactor Trip resulting in a cooldown and did not promptly close the Main Steam Isolation Valves (MSIVs).
Corrective actions include procedures revisions to include specific guidance on FRV Bypass Valve and MSIV closure. Training will be conducted to address gaps in Tavg control following Reactor Trip.
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I ID Page of 05000-
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
V. CORRECTIVE ACTIONS
Operations guidance for closure of both the Main Feedwater Regulating Valves and Main Steam Isolation Valves will be added to the shutdown procedures. Training solutions will be used to address the gaps in temperature control following Reactor Trip.
VI. ADDITIONAL INFORMATION
None A. FAILED COMPONENTS:
None 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 - Flow Control Valve IEEE 803 FUNCTION NUMBER - FCV IEEE 805 SYSTEM IDENTIFICATION - SJ 4
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