ML24249A074

Both Trains of Control Room Ventilation Temperature Control System Inoperable

ML24249A074
Person / Time
Site:	Byron
Issue date:	09/05/2024
From:	Harvey S Constellation Energy Generation
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
2024-0047 LER 2024-001-00
Download: ML24249A074 (1)

Text

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September 5, 2024

10CFR50.73 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

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) Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons

!earned are incorporated into the licensing process and fed back to industry. Send comments regarding burden LICENSEE EVENT REPORT (LER) estimate to the FOIA, Library, and Information Collections Branch (T~6 A10M). U. S. Nuclear Regulatory (See Page 2 for required number of digits/characters for each block) Commission, Washington, DC 20555-0001, or by email to lnfocollects.Resource@nrc.gov, and the 0MB reviewer at: OMS Office of Information and Regulatory Affairs, {3150-0104), Attn: Desk Officer for the Nuclear Regulatory (See NUREG-1022, R.3 for instruction and guidance for this form Commission, 725 17th Street NW Washington. DC 20503. The NRC may not conduct or sponsor. and a person is

:: '*,y;.L::, e 1::i,*: :':::;,:"'*" 2 c::: ':c,:.' not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number

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

Month Day Year Year Number No, Month Day Year Byron Station, Unit 2 rgJ 050 05000455 Sequential Revision Facility Name Docket Number

Facility Name2 Docket Number 07 07 2024 2024 001 00 09 05 2024 - - NIA 052 N/A

9, Operating Mode 110, Power Level 100 1

11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 10 CFR Part 20 20.2203(a)(2)(vi) 10 CFR Part 50 50. 73(a)(2)(ii)(A) 50. 73(a)(2)(viii)(A) 73.1200(a) 20.2201(b) 20.2203(a)(3)(i) 50.36(c)(1 )(i)(A) 50. 73(a)(2)(ii)(B) 50. 73(a)(2)(viii)(B) 73.1200(b) 20.2201(d) 20.2203(a)(3)(ii) 50.36( c)(1 )(i i)(A) 50. 73(a)(2)(iii) 50. 73(a)(2)(ix)(A) 73.1200(c) 20.2203(a)(1) 20.2203(a)(4) 50.36(c)(2) 50. 73(a)(2)(iv)(A) 50.73(a)(2)(x) 73.1200(d) 20,2203(a)(2)(i) 10 CFR Part 21 50.46(a)(3)(ii) 50. 73(a)(2)(v)(A) 10 CFR Part 73 73.1200(e) 20.2203( a)(2)(i i) D 21.2(c) 50.69(g) 50. 73(a)(2)(v)(B) 73. 77(a)(1) 73.1200(f) 20.2203(a)(2)(iii) 50.73(a)(2)(i)(A) 50. 73(a)(2)(v)(C) 73. 77(a)(2)(i) 73.1200(9) 20.2203(a)(2)(iv) 50.73(a)(2)(i)(B) rgJ 50. 73(a)(2)(v)(D) 73. 77(a)(2)(ii) 73.1200(h) 20.2203(a)(2)(v) 50.73(a)(2)(i)(C) 50. 73(a)(2)(vi i)

D OTHER (Specify here, in abstract, or NRC 366A).

12. Licensee Contact for this LER Licensee Contact Phone Number (Include area code)

Zoe Cox, Regulatory Assurance Manager (779) 231-6606

13. Complete One Line for each Component Failure Described in this Report

Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS G VI N/A N/A y N/A N/A N/A N/A N/A

14, Supplemental Report Expected Month Day Year

15. Expected Submission Date rgj No Yes (If yes, complete 15. Expected Submission Date) N/A N/A N/A

16. Abstract (Limit to 1326 spaces, i.e., approximately 13 single-spaced typewritten lines)

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.

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024)

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the FOIA. Library. and Information Collections Branch (T-6 A 1 OM). U. S.

Nuclear Regulatory Commission. Washington. DC 20555-0001. or by email to CONTINUATION SHEET lnfocollects.Resource@nrc.gov, and the 0MB reviewer at: 0MB Office of Information and Regulatory Affairs. (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW.

Washington. DC 20503. 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 0MB control number.

1. FACILITY NAME ? 050 2. DOCKET NUMBER 3. LER NUMBER YEAR NUMBER NO. SEQUENTIAL REV Byron Station, Unit 1 052 05000454 2024 - 001 00

NARRATIVE

A. Plant Operating Conditions Before the Event:

Event Date: July 7, 2024 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

NRC FORM 366A (04-02-2024) Page_2_ of _3_

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024) Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported

lessons learned are incorporated into the licensing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the FOIA. Library, and Information Collections Branch (T-6 A 1 OM), U. S.

Nuclear Regulatory Commission. Washington. DC 20555-0001, or by email to CONTINUATION SHEET lnfocollects.Resource@nrc.gov. and the 0MB reviewer at: 0MB Office of Information and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW Washington. DC 20503 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 0MB control number.

1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER

? 050 YEAR SEQUENTIAL REV NUMBER NO.

Byron Station, Unit 1 052 05000454 2024 -001 00

NARRATIVE 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.

NRC FORM 366A (04-02-2024) Page_3_ of _3_