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Category:Letter
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[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000454/LER-2024-002, Reactor Vessel Closure Head Penetration 31 Degraded2024-11-0707 November 2024 Reactor Vessel Closure Head Penetration 31 Degraded 05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024 Both Trains of Control Room Ventilation Temperature Control System Inoperable 05000454/LER-2023-001-01, A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR32J2023-10-12012 October 2023 A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR32J 05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking2023-08-31031 August 2023 Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking 05000454/LER-2023-001, A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR032J2023-05-15015 May 2023 A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR032J 05000454/LER-2022-001, Ob Control Room Ventilation Supply Fan Failed to Start Due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock2022-09-0909 September 2022 Ob Control Room Ventilation Supply Fan Failed to Start Due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock 05000454/LER-2021-001-01, Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit2022-08-31031 August 2022 Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit 05000455/LER-2022-001, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking2022-06-22022 June 2022 Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking 05000454/LER-2021-001, Re Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit2021-11-18018 November 2021 Re Pressurizer Safety Valves As-Found Lift Pressure Outside of Tech Spec Limit 05000454/LER-2017-0012017-04-25025 April 2017 1 OF 4, LER 17-001-00 for Byron, Unit 1, Regarding Volumetric and Surface Examinations of Reactor Pressure Vessel Head Penetration Nozzles Identify Indications Attributed to Primary Water Stress Corrosion Cracking and Minor Subsurface Void Enlargement from.. 05000455/LER-2016-0012017-02-15015 February 2017 Manual Reactor Trip due to Circuit Breaker Failure that Caused Actuation of Feedwater Hammer Prevention System with Automatic Isolation of Feedwater to Two Steam Generators and Low Steam Generator Levels, LER 16-001-01 for Byron Station, Unit 2 Regarding Manual Reactor Trip Due to Circuit Breaker Failure that Caused Actuation of Feedwater Hammer Prevention System with Automatic Isolation of Feedwater to Two Steam Generators and Low Steam Generator.... 05000454/LER-2016-0012016-05-0303 May 2016 Auxiliary Feedwater Diesel Intake Design Deficiency Related to Turbine Building High Energy Line Break Resulted in an Unanalyzed Condition Due to Insufficient Validation of Vendor Analysis Inputs, LER 16-001-00 for Byron, Unit 1, Regarding Auxiliary Feedwater Diesel Intake Design Deficiency Related to Turbine Building High Energy Line Break Resulted in an Unanalyzed Condition Due to Insufficient Validation of Vendor Analysis Inputs BYRON 2004-0033, Supplemental One to Licensee Event Report (LER) 454-2003-003-00, Licensed Maximum Power Level Exceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements Caused by Signal Noise Contamination2004-03-31031 March 2004 Supplemental One to Licensee Event Report (LER) 454-2003-003-00, Licensed Maximum Power Level Exceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements Caused by Signal Noise Contamination BYRON 2002-0115, LER 02-S001-00 for Byron Station, Units 1 and 2, Unescorted Access Granted Based on Falsified Information Provided by an Individual2002-10-25025 October 2002 LER 02-S001-00 for Byron Station, Units 1 and 2, Unescorted Access Granted Based on Falsified Information Provided by an Individual 2024-09-05
[Table view] |
LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable |
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4542024001R00 - NRC Website |
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l September 5, 2024 L TR:
BYRON 2024-0047 File:
1D.101 5A.108 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License No. NPF-37 and NPF-66 NRG Docket No. STN 50-454 10CFR50.73 Subject:
Licensee Event Report (LER) No. 454-2024-001 "Both Trains of Control Room Ventilation Temperature Control System Inoperable" Enclosed is Byron Station Licensee Event Report (LER) No. 454-2024-001 regarding both trains of Control Room Ventilation Temperature Control System inoperable. This condition is being submitted in accordance with 10 CFR 50.73, "Licensee Event Report System."
There are no regulatory commitments in this report.
Should you have any questions concerning this submittal, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (779) 231-6606.
Respectfully,
Shane Harvey Plant Manager Byron Generating Station SH/DG/hh Enclosure:
LER 454-2024-001 cc:
Regional Administrator-NRG Region Ill NRG Senior Resident Inspector - Byron Generating Station
NRG FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024)
- 1. Facility Name
~ 050 2, Docket Number 3.Page Byron Station, Unit 1 052 05000454 1 OF 3
- 4. Title Both Trains of Control Room Ventilation Temperature Control System Inoperable 5, Event Date
- 6. LER Number 7, Report Date
- 8. Other Facilities Involved Sequential Revision Facility Name Docket Number Month Day Year Year Number No, Month Day Year Byron Station, Unit 2 rgJ 050 05000455 07 07 2024 2024 001 00 09 05 2024 Facility Name2 Docket Number NIA 052 N/A 9, Operating Mode 110, Power Level 100 1
)
N/A N/A N/A
Abstract
At 1440 CDT on July 7, 2024, the OA and OB trains of the Control Room Ventilation (VC) Temperature Control System were simultaneously inoperable resulting in a condition that could have prevented the fulfillment of a safety function and was reported as an eight-hour, non-emergency notification per 10 CFR 50. 72(b)(3)(v)(D) under ENS 57211 to the NRC.
OB Control Room Ventilation (VC) Temperature Control system was restored to operable status at 1634 CDT on 7/7/2024.
A.
Plant Operating Conditions Before the Event
Event Date:
July 7, 2024
- 2. DOCKET NUMBER
- 3. LER NUMBER SEQUENTIAL REV YEAR NUMBER NO.
05000454 2024 -
001 00 Unit 1 - Mode 1 - Power Operations, Reactor Power 100 percent Unit 2 - Mode 1 - Power Operations, Reactor Power 100 percent Reactor Coolant System (RCS)[AB]: Normal Operating Temperature and Pressure No structures, systems, or components were inoperable at the start of this event that contributed to the event.
B.
Description of the Event:
At 1310 CDT on 7 /7 /24 the auxiliary building equipment operator (EO) noted the DA Control Room Ventilation (VC) Temperature Control System chiller oil level had dropped from a previous rounds reading of 37 percent to 15 percent. The EO notified the main control room and the operations field supervisor was dispatched to review the condition. The shift manager notified maintenance to request support to add oil to the DA VC chiller.
At 1355 CDT, a briefing was held in the control room to perform the crosstie of the service building (VS) chilled water system to the 0A VC chilled water system per procedure BOP VC-20. At 1404 CDT, while the briefing was in progress, the auxiliary building EO notified the main control room that the oil level in the DA VC chiller had further decreased to 0 percent in the sight glass, but that oil was still visible with foam present.
Following the briefing, two equipment operators obtained keys to unlock the individual valves needed to perform the crosstie. At approximately 1435 CDT, the operations field supervisor notified the main control room that the oil level in the DA VC chilled water system was no longer visible in the sight glass. At 1440 the DA VC chiller was secured and declared inoperable by Operations and the equipment operators began to perform the procedure steps to establish the VC to VS chilled water crosstie. While attempting to crosstie 0A VC train to the service building (VS) chilled water system, the equipment operators incorrectly operated valves on the OB VC chiller train. This caused the OB VC chiller train to become inoperable. With both trains of control room chillers inoperable, Unit 1 and Unit 2 entered TS 3.7.11 Condition D. Operations personnel returned to the field at 16:34 CDT on 7/7/24 and restored the valve lineup for the OB VC chiller returning the OB VC chiller to operable and exiting Condition D of TS 3.7.11. This event was determined to be a loss of safety function for the control room chilled water system and an 8-hour ENS (57211) was made to the NRC per 10 CFR 50.72(b)(3)(v)(D) at 22:12 CDT on 7/7/24.
C.
Causes of Event:
The root cause of this event was determined to be an inadequate brief performed by the Operations SRO with the Reactor Operator and Equipment Operators. During the brief, the SRO supervisor did not clearly establish that each operator understood their role in the crosstie activity or utilize station prints to clearly establish the intended plant manipulations. As a result, the equipment operators manipulated incorrect valves while establishing the crosstie which resulted in both trains of VC Temperature Control System being declared inoperable.
Contributing causes to the event were a lack of system knowledge and experience combined with less than adequate procedural guidance. The equipment operators performing the crosstie did not fully understand the flow path that needed to be established. Additionally, training provided in 2018 when the VS to VC crosstie
- 2. DOCKET NUMBER YEAR 05000454 2024
- 3. LER NUMBER SEQUENTIAL NUMBER 001 REV NO.
00 modification was implemented, focused on technical specification changes and procedural guidance but did not demonstrate the flow paths between the two systems. Procedural guidance did not provide specific steps for each train or include detail regarding which train valves were associated with each VC train.
D.
Safety Consequences
The temperature control system portion of the VC System (VC Temperature Control System) provides temperature control for the control room normally and following isolation of the control room. The VC Temperature Control System consists of the VC components (arranged in two independent and redundant trains) that provide cooling and heating of recirculated control room air.
This event had no safety consequences impacting plant or public safety. For approximately two hours on 7/7/24, the 0A and OB Control Room Temperature (VC) Control System trains were inoperable requiring entry into TS 3.7.11, Control Room Ventilation (VC) Temperature Control System, Condition D. Temperatures in the main control room, during the approximately two hours both VC trains were inoperable, did not exceed the Tech Spec required limit of</= 80 degrees F and online risk remained green for both units throughout the event.
E.
Corrective Actions
Upon discovery, the OB Temperature Control System (VC) was returned to operable. Immediately following the event, the directly involved individuals were removed from watch-standing and remediated.
Corrective actions taken or planned to be taken include:
- - Review and reinforcement of the requirements for conducting effective pre job briefs with each operating crew.
- - Weekly communications performed by Station Leadership focusing on standards, human performance tool usage, and a review of learnings and examples from observations.
- - Revising the applicable VS to VC crosstie procedures, to better human-engineer the procedure steps and add more detailed drawings.
- - VS to VC crosstie training will be revised to include a review of the flow paths, heat up rates in the control room when cooling is not aligned, and the Technical Specification conditions for VC train inoperability.
F.
Previous Occurrences
LER 454-2023-011-01 On March 18, 2023, at 14:40 CDT, the 0A Control Room Ventilation (VC) failed to actuate when performing the 1A Diesel Generator (DG) sequencer testing due to installed jumpers on 0PR031J and 0PR032J, Main Control Room Outside Air Intake A Monitors. Jumpers that were installed during the Bus 141 outage to defeat Main Control Room Radiation Monitor interlocks were not removed as expected at the conclusion of the bus outage.
These jumpers prevented 0PR031J and 0PR032J, Main Control Room Outside Air Intake A Monitors from causing 0A Train VC actuations when required during 1A DG sequencer testing. 0PR031 J and 0PR032J were declared inoperable. Once identified, the jumpers were removed from 0PR031J and 0PR032J and the monitors were restored to operable status. Page_3_ of _3_