05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String: Difference between revisions

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{{#Wiki_filter::) entergy Randy Crawford Manager Regulatory Assurance 225-381-4177
{{#Wiki_filter::) entergy Randy Crawford Manager Regulatory Assurance 225-381-4177 RBG-48294 10 CFR 50.73 June 4, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject:
 
Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String River Bend Station - Unit 1 NRC Docket Nos. 50-458 Renewed Facility Operating License No. NPF-47 In accordance with 1 O CFR 50.73, enclosed is the subject Licensee Event Report.
RBG-48294 10 CFR 50.73
 
June 4, 2024
 
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
 
Subject: Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
 
River Bend Station - Unit 1 NRC Docket Nos. 50-458 Renewed Facility Operating License No. NPF-47
 
In accordance with 1 O CFR 50.73, enclosed is the subject Licensee Event Report.
 
This document contains no commitments.
This document contains no commitments.
Should you have any questions, please contact Mr. Randy Crawford, Regulatory Assurance Manager, at 225-381-4177.
Should you have any questions, please contact Mr. Randy Crawford, Regulatory Assurance Manager, at 225-381-4177.
Respectfully, Randy Crawford RC/db Enclosure:
cc:
Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String NRC Region IV Regional Administrator - Region IV NRC Senior Resident Inspector - River Bend Station Entergy Operations, Inc., 5485 U.S. Highway 61 N. St. Francisville, LA 70775


Respectfully,
Enclosure RBG-48294 Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String


Randy Crawford
=Abstract=
 
River Bend Station, Unit 1
RC/db
 
Enclosure: Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
 
cc: NRC Region IV Regional Administrator - Region IV NRC Senior Resident Inspector - River Bend Station


Entergy Operations, Inc., 5485 U.S. Highway 61 N. St. Francisville, LA 70775 Enclosure
00458 3
Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String 11 17 2023 2023 005 01 06 04 2024


RBG-48294
Randy Crawford, Regulatory Assurance Manager 225-381-4177 X
 
SJ N/A N/A Y
Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
=Abstract=


On November 17, 2023, at 22:15 CST, with River Bend Station, Unit 1, operating in Mode 1 at 30% power, an isolation of Low-Pressure Feedwater Heater String A occurred. Operators entered the applicable Abnormal Operating Procedure (AOP) and reduced power to mitigate the lowering feedwater temperature. Reactor power was lowered to 24% and a manual reactor scram was inserted at 23:55 CST. All control rods fully inserted and there were no complications. All systems responded as designed.
On November 17, 2023, at 22:15 CST, with River Bend Station, Unit 1, operating in Mode 1 at 30% power, an isolation of Low-Pressure Feedwater Heater String A occurred. Operators entered the applicable Abnormal Operating Procedure (AOP) and reduced power to mitigate the lowering feedwater temperature. Reactor power was lowered to 24% and a manual reactor scram was inserted at 23:55 CST. All control rods fully inserted and there were no complications. All systems responded as designed.
A direct cause of the Heater String isolation cannot be determined.
A direct cause of the Heater String isolation cannot be determined.
This report is made pursuant to 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of the Reactor Protection System.
This report is made pursuant to 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of the Reactor Protection System.
 
1 024
==Event Description==
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On November 17, 2023, at 22:15 CST, River Bend Station (RBS), Unit 1, was operating at 30% power while performing plant startup activities when an isolation of Low-Pressure Feedwater Heater String A [SJ] occurred. Main Control Room Operators entered Abnormal Operating Procedure - Loss of Feedwater Heating (AOP-0007) for transients involving lowering feedwater temperature. AOP-0007, Attachment 1 (Feedwater Temperature vs Core Thermal Power Graph),
, i
provides guidance for power operations with reduced feedwater temperature from 100% reactor power to 25% reactor power. In accordance with AOP-0007, Attachment 1, operators began to manually insert control rods using the Control Rod Drive System [AA] to exit the restricted region for power operations at the lower feedwater temperature. Control rod insertion lowered power to 24%, which placed the unit below the graph start point of AOP-0007, Attachment 1. At 23:55 CST, while RBS was operating at 24% power, a manual reactor scram was inserted due to operation below the graph start point of AOP-0007, Attachment 1, caused by continued lowering of feedwater temperature. All control rods fully inserted and there were no complications. All systems responded as designed. AOP-0007, Attachment 1, contains a graph of feedwater temperature versus core thermal power; however, no information is provided for power levels below 25.7% of rated power. With reactor power lowering to 24%, the operators were not able to determine if the unit was operating in an acceptable region. Therefore, the conservative decision was made to manually scram the reactor. Following the initial investigation, engineering input from calculations performed as part of an engineering change has provided new information for operating at power levels below 25.7%. This event was reported under 10 CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical and 10 CFR 50.72(b)(3)(iv)(A) Specified System Actuation as result of Group 3 isolations (EN 56863). This report is made pursuant to 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of the Reactor Protection System.
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==Event Cause==
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There is insufficient evidence to determine a direct causal factor for the Low-Pressure Feedwater Heater String isolation event. An independent third-party review of this incident has determined the most probable cause of the isolation was a level switch actuation due to steam backflow from the drain receiver tank volume flashing as a result of a rapid pressure transient event.
: 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
 
052 050 Corrective Actions
==Safety Assessment==
The actual consequence was the initiation of a manual scram. Following the scram, reactor pressure was maintained by the Turbine Steam Drains [TF] and reactor water level was maintained by the Feedwater [SJ] system. The RBS power to flow map continued to meet the licensing acceptance criteria parameters. There were no actual consequences to general safety of the public, nuclear safety, industrial safety, and radiological safety for this event.
 
==Corrective Actions==
: 1. Clarifying information and technical basis was added to AOP-0007 to help operators better understand the applicable guidance for power operations at reduced feedwater temperatures.
: 1. Clarifying information and technical basis was added to AOP-0007 to help operators better understand the applicable guidance for power operations at reduced feedwater temperatures.
: 2. The Feedwater Temperature vs Core Thermal Power Graph in AOP-0007 has been updated for power operations below 25.7%.
: 2. The Feedwater Temperature vs Core Thermal Power Graph in AOP-0007 has been updated for power operations below 25.7%.
Line 90: Line 68:
==Previous Similar Events==
==Previous Similar Events==
A similar event occurred at RBS in 1986. As documented in LER-1986-001, a reactor scram resulted from a Low-Pressure Feedwater Heater String isolation due to a false high level indication. The false high level was caused by flashing in the level transmitter pots. A modification was made to the system which relocated the level switches to a leg of downward sloped pipe. The modification prevents water from accumulating that would result in steam flashes during power ascension. Although this is a similar event, the failure mechanism in LER-1986-001 is different from the one as described in this LER.
A similar event occurred at RBS in 1986. As documented in LER-1986-001, a reactor scram resulted from a Low-Pressure Feedwater Heater String isolation due to a false high level indication. The false high level was caused by flashing in the level transmitter pots. A modification was made to the system which relocated the level switches to a leg of downward sloped pipe. The modification prevents water from accumulating that would result in steam flashes during power ascension. Although this is a similar event, the failure mechanism in LER-1986-001 is different from the one as described in this LER.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX]. River Bend equipment codes are identified as (XX).
3 3
River Bend Station, Unit 1 00458 2023 005 01


Energy Industry Identification System (EIIS) codes are identified in the text as [XX]. River Bend equipment codes are identified as (XX).
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Revision as of 18:07, 24 November 2024

Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
ML24156A040
Person / Time
Site: River Bend 
Issue date: 06/04/2024
From: Crawford R
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RBG-48294 LER 2023-005-01
Download: ML24156A040 (1)
v • d • e


LER-2023-005, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation
4582023005R01 - NRC Website
v • d • e

text

) entergy Randy Crawford Manager Regulatory Assurance 225-381-4177 RBG-48294 10 CFR 50.73 June 4, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Subject:

Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String River Bend Station - Unit 1 NRC Docket Nos. 50-458 Renewed Facility Operating License No. NPF-47 In accordance with 1 O CFR 50.73, enclosed is the subject Licensee Event Report.

This document contains no commitments.

Should you have any questions, please contact Mr. Randy Crawford, Regulatory Assurance Manager, at 225-381-4177.

Respectfully, Randy Crawford RC/db Enclosure:

cc:

Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String NRC Region IV Regional Administrator - Region IV NRC Senior Resident Inspector - River Bend Station Entergy Operations, Inc., 5485 U.S. Highway 61 N. St. Francisville, LA 70775

Enclosure RBG-48294 Licensee Event Report 50-458 / 2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String

Abstract

River Bend Station, Unit 1

00458 3

Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String 11 17 2023 2023 005 01 06 04 2024

Randy Crawford, Regulatory Assurance Manager 225-381-4177 X

SJ N/A N/A Y

On November 17, 2023, at 22:15 CST, with River Bend Station, Unit 1, operating in Mode 1 at 30% power, an isolation of Low-Pressure Feedwater Heater String A occurred. Operators entered the applicable Abnormal Operating Procedure (AOP) and reduced power to mitigate the lowering feedwater temperature. Reactor power was lowered to 24% and a manual reactor scram was inserted at 23:55 CST. All control rods fully inserted and there were no complications. All systems responded as designed.

A direct cause of the Heater String isolation cannot be determined.

This report is made pursuant to 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of the Reactor Protection System.

1 024

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3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.

052 050 Corrective Actions

1. Clarifying information and technical basis was added to AOP-0007 to help operators better understand the applicable guidance for power operations at reduced feedwater temperatures.
2. The Feedwater Temperature vs Core Thermal Power Graph in AOP-0007 has been updated for power operations below 25.7%.
3. Installation of a time delay in the level sensing circuit that will aid in diagnosing a valid level instead of a pressure transient to prevent future occurrences of heater string isolation.

Previous Similar Events

A similar event occurred at RBS in 1986. As documented in LER-1986-001, a reactor scram resulted from a Low-Pressure Feedwater Heater String isolation due to a false high level indication. The false high level was caused by flashing in the level transmitter pots. A modification was made to the system which relocated the level switches to a leg of downward sloped pipe. The modification prevents water from accumulating that would result in steam flashes during power ascension. Although this is a similar event, the failure mechanism in LER-1986-001 is different from the one as described in this LER.

Energy Industry Identification System (EIIS) codes are identified in the text as [XX]. River Bend equipment codes are identified as (XX).

3 3

River Bend Station, Unit 1 00458 2023 005 01

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