05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch

Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch

ML21244A284
Person / Time
Site:	Susquehanna
Issue date:	09/01/2021
From:	Cimorelli K Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7963 LER 2021-001-00
Download: ML21244A284 (4)

LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
3882021001R00 - NRC Website

text

Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Tel. 570.542.3795 Fax Berwick, 570.542.1504 PA 18603 TALEN~

Kevin.Cimorelli@TalenEnergy.com ENERGY

September 01, 2021 Attn: Document Control Desk 10 CPR 50.73 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388/2021-001-00 UNIT 2 LICENSE NO. NPF-22 PLA-7963 Docket No. 50-388

Attached is Licensee Event Report (LER) 50-388/2021-001-00. This LER reports an event involving drifting of a Reactor Pressure Steam Dome-Low permissive switch (Microswitch 2).

This event was determined to be reportable as a condition prohibited by Technical Specifications in accordance with 10 CPR 50.73(a)(2)(i)(B), a condition that could have prevented fulfillment of a safety function in accordance with 10 CPR 50.73(a)(2)(v)(D), and a common cause inoperability of independent trains or channels in accordance with 10 CPR 50.73(a)(2)(vii).

There were no actual consequences to the health and safety of the public as a result of this event.

This letter contains no new or revised regulatory commitments.

Attachment: LER 50-388/2021-001-00

Copy: NRC Region I Ms. A. Klett, NRC Project Manager Mr. C. Highley, NRC Senior Resident Inspector Mr. M. Shields, PADEP/BRP

Abstract

On July 6, 2021, the Unit 2 "D" Reactor Steam Dome Pressure-Low permissive pressure switch, Microswitch 2, was found outside of the Technical Specification (TS) 3.3.5.1 allowable value. The switch drifted outside of the lower allowable value which is intended to ensure that the Emergency Core Cooling System (ECCS) injection prevents the fuel peak cladding temperature from exceeding the limits of 10 CFR 50.46.

Based on the information available, the condition likely existed for longer than allowed by TS 3. 3. 5.1, TS 3. 5.1, and TS 3.0.3. As such, this is a condition prohibited by TS and is being reported in accordance with 10 CFR

50. 73(a)(2)(i)(B). In addition, since the "C" channel (PIS-B21-2N021 C) was surveillance tested just prior to identification of the drift of the "D" channel (PS-B21-2N021 D), redundant channels were inoperable at the same time impacting both Core Spray and LPCI functions; therefore, this is also considered a condition that could have prevented fulfillment of a safety function (10 CFR 50.73(a)(2)(v)(D)) and a common cause inoperability of independent trains or channels (10 CFR 50.73(a)(2)(vii)).

The cause of the event is under investigation and will be provided under a supplement to this LER along with associated corrective actions.

There were no actual consequences to the health and safety of the public as a result of this event.

NRC FORM 366 (06 2020)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150*0104 EXPIRES: 08/31/2023 Susquehanna Steam Electric Station Unit 2 05000-388 NUMBER NO.

2021 001 00

NARRATIVE

CONDITIONS PRIOR TO EVENT

Unit 1 - Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event.

EVENT DESCRIPTION

Prior to September 2017, Susquehanna Steam Electric Station (SSES) had been utilizing International Telephone and Telegraph (ITT)-Barton 288A pressure switches in the Reactor Steam Dome Pressure-Low channels [EllS System/Component Identifier: JE/PS] that provide the injection permissive for the Core Spray system [EllS System Identifier: BM] (Technical Specification (TS) 3.3.5.1, Function 1 d) and the Residual Heat Removal (RHR)/Low Pressure Coolant Injection system (LPCI) [EllS System Identifier:

BO] (TS 3.3.5.1, Function 2d). Due to instrument drift concerns, all eight obsolete ITT-Barton 288A pressure switches were replaced with General Electric (GE) recommended Cameron-Barton 288A pressure switches between September 6, 2017 and November 15, 2017. Following replacement, instrument drift continued to be an issue, and additional corrective action was determined necessary to resolve the drift concerns. The additional corrective action included procuring and installing Cameron-Barton 288A instruments that had been modified to remove an over-range condition and the movement assembly/associated linkages that were determined to be affecting instrument drift. The first of these modified instruments was installed and calibrated on July 8, 2020 in the Unit 2 "D" channel (pressure switch for PS-B21-2N021 D).

On August 10,2020, the new, modified PS-B21-2N021D switch, Microswitch 2, was tested for its first surveillance interval and found to be outside of TS acceptance criteria. The switch drifted 1.2 psig outside of the upper allowable value which is intended to ensure that the reactor dome pressure has fallen to a value below the Core Spray and RHR/LPCI maximum design pressures to preclude over-pressurization of the low pressure systems prior to low pressure injection initiation. This event was reported in LER 50-388/2020-002-01, dated July 1, 2021.

On July 6, 2021, the Unit 2 "D" Reactor Steam Dome Pressure-Low permissive pressure switch, Microswitch 2, was found outside of the TS 3.3.5.1 allowable value. The switch drifted outside of the lower allowable value which is intended to ensure that the Emergency Core Cooling System (ECCS) injection prevents the fuel peak cladding temperature from exceeding the limits of 10 CFR 50.46.

Based on the information available, the condition likely existed for longer than allowed by TS 3.3.5.1, "Emergency Core Cooling System (ECCS) Instrumentation," TS 3.5.1, "EGGS-Operating," and TS 3.0.3.

As such, this is a condition prohibited by TS and is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B). In addition, since the "C" channel (PIS-B21-2N021C) was surveillance tested just prior to identification of the drift of the "D" channel (PS-B21-2N021D), redundant channels were inoperable at the same time impacting both Core Spray and LPCI functions; therefore, this is also considered a condition that could have prevented fulfillment of a safety function (1 0 CFR 50. 73(a)(2)(v)(D)) and a common cause inoperability of independent trains or channels (1 0 CFR 50. 73(a)(2)(vii)).

CAUSE OF EVENT

The cause of the event is under review and will be provided in a supplement to this LER.

ANALYSIS/SAFETY SIGNIFICANCE

Although outside of the TS 3.3.5.1 allowable value, the as-found setpoint remained above the analytical limit assumed in the accident analysis. Therefore, Core Spray and RHR would have been able to perform their safety functions and the condition described herein did not result in a safety system functional failure. Accordingly, this event will not be counted as a safety system functional failure in the Reactor Oversight Process Performance Indicators. There were no actual consequences to the health and safety of the public as a result of this event.

CORRECTIVE ACTIONS

The cause of the event is under review and will be provided in a supplement to this LER.

COMPONENT FAILURE INFORMATION

Component failure information will be provided in a supplement to this LER.

PREVIOUS OCCURRENCES

As indicated by the previous occurrences listed below, the condition of drifting pressure indicating switches is a known issue at SSES. Previously reported Corrective Actions are in progress; additional corrective actions will be dictated by the Susquehanna Corrective Action Program.

LER 50-388/2020-002-01, "Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment", dated July 1, 2021.

LER 50-387(388)/2018-005-02, "Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches", dated July 1, 2021.

LER 50-388/2017-010-02, "Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches", dated July 1, 2021.

LER 50-388(387)/2015-001-01, "Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Steam Dome-Low Switches", dated February 10, 2016.