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IDHEAS Suite for Human Reliability Analysis- an Overview and Recent Developmental Focuses (Presentation Slides for PSAM17/ASRAM2024 Conference)
	ML24270A118
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Issue date:	10/07/2024
From:	Chang Y; NRC/RES/DRA/HFRB
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IDHEAS Suite for Human Reliability Analysis

- An Overview and Recent Developmental Focuses Yung Hsien James Chang, Ph.D.

Senior Reliability and Risk Analyst U.S. Nuclear Regulatory Commission Presented at PSAM17/ASRAM2024 Conference Sendai, Japan October 7 - 11, 2024

2 Presentation Outline

IDHEAS suite - The NRCs HRA tools

Near-term work focuses

An example of supporting the development of IDHEAS-ECA desktop guide

Opportunities for collaborations

3 IDHEAS Suite - Developmental Background

The Significance determination process (SDP) and Accident Sequence Precursor (ASP) are the NRCs human reliability Analysis (HRA) applications for reactor safety

Require assess human error probabilities (HEPs) with specific contexts, identified by inspection findings.

The existing methods performance influencing factors (PIFs) generally lack of adequate granularities to represent the context and data basis to assess the HEPs.

The NRC Commission directed the NRC staff to develop HRA methods and HRA database

Two SRMs (M061020 and M140529) on HRA methods development

One SRM (M090204b) on HRA database development

IDHEAS Suite is to achieve the goals of these SRMs

4 IDHEAS Suite - Functions and Products Function Products High-Level HRA guidance IDHEAS-General Methodology (NUREG-2198)

HEP quantification IDHEAS-ECA (NUREG-2256); IDHEAS-AT Power (NUREG-2199);

IDHEAS-Dependency (RIL 2021-14); Error Recovery (TBD);

Time Uncertainty (TBD); and HEP Uncertainty (TBD);

Expert elicitation (NUREG-2255, draft)

Data basis IDHEAS-DATA (in process) and SACADA, Guidance on data generalization and integration.

Software tool IDHEAS-ECA tool (present status: rev. 1.2)

Quality control IDHEAS-ECA desktop guide (in development); independent reviews IDHEAS-ECA Evaluation of SPAR HFEs (in process) - also demonstrate documentation.

NUREGs are available in https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/index.html.

Research Information letters (RIL) are available in https://www.nrc.gov/reading-rm/doc-collections/research-info-letters/index.html.

5 The NRCs 2024 HRA Publications

HRA R&D five-year plan (internal)

RIL 2024-03 Integrated Human Event Analysis System (IDHEAS) - Time and Time Uncertainty.

RIL 2024-04 Human Reliability Analysis for Calculating Effects of Performance Influencing Factors: A Review of Historical Approaches.

RIL 2024-05 Simulator Data Analysis to Inform Digitalized Environment Impacts on Human Reliability

RIL 2024-11 Use of Expert Elicitation Guidance to Inform a Small-Scale Knowledge Judgment Application

NUREG-2255 Expert Elicitation Guidance (in process)

RIL 2024-xx IDHEAS-ECA Evaluation of SPAR HFEs (in process)

RIL 2024-xx IDHEAS-DATA Verification (in process)

IDHEAS-ECA tool rev. 1.3 (in process)

6 Near-Term Work Focuses

Guidance development

Develop IDHEAS-ECA desktop guide

Recommended by an NRC workgroup that use IDHEAS-ECA to analyze SPAR human actions

To improve reliability and consistency of analysts applying IDHEAS-ECA

With support of industry

Verify IDHEAS-Dependency

Develop IDHEAS-Error Recoveries

Develop IDHEAS-Time Uncertainty

IDHEAS-ECA tool rev. 1.3 - add dependency model

Collect HRA data (continuous effort)

Publish the in-process products

7 Develop IDHEAS-ECA Desktop Guide

Revisit references listed in IDHEAS-DATA to

Enhance the existing IDHEAS-ECA guidance on the selection of cognitive failure modes (CFMs) and performance influencing factor attributes (PIFAs)

Provide adequate details about the references contents to supplement guidance to support the analysts in selecting CFMs and PIFAs

Update the data in IDHEAS-DATA

Data Generalization and Integration 8

9 A Data Generalization and Integration Example

Task Complexity: C1 Detection overload with multiple competing signals

Track the states of multiple systems

Monitor many parameters

Memorize many pieces of information detected

Many types or categories of information to be detected

IDHEAS-ECA consolidates multiple data points to estimate human error probabilities (HEPs)

Task Complexity in Detection: C1

- Implemented in IDHEAS-ECA HEP range: 3E 3E-1 10

Data Sources (1/2)

There references are available in IDHEAS-DATA (Draft, ADAMS Accession #: ML20238B982).

[26] is SACADA data.

11

12 Data Sources (2/2)

[26] SACADA Detection Data

- Alarm board is dark 13 Desc.

Malfunction TOE (training objective element)

UNSAT SAT SAT SAT+

Total UNSAT Ratio(%)

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Determines 1A CCW pump has tripped 1

13 0

0 14 7.14 RCP Seal Cooling Evaluation Loss of 1A CCW Pump Per 0POP09-AN-02M3 ensures the standby CCW train starts with proper alignment 0

12 0

1 13 0

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Initiate Tech Spec actions 0

14 0

0 14 0

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Determines 1C RCP Thermal Barrier Isolation valve closed 0

14 0

0 14 0

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Per 0POP09-AN-04M7 determines the Thermal Barrier Isolation valve MOV-0390 has closed du 0

13 1

0 14 0

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Enters 0POP04-RC-0002 RCP off-normal 0

13 1

0 14 0

RCP Seal Cooling Evaluation Loss of 1A CCW Pump Briefs loss of ALL seal cooling to be ready in case Seal Injection is lost 1

13 0

0 14 7.14 RCP Seal Cooling Evaluation Loss of 1A CCW Pump Ensures Tech Specs recognition and compliance 0

14 0

0 14 0

RCP Seal Cooling Evaluation Total Loss of RCP Seal Cooling Determines total loss of RCP seal cooling 0

14 0

0 14 0

RCP Seal Cooling Evaluation Total Loss of RCP Seal Cooling Trips the Reactor and ensures Main Turbine is Tripped 0

14 0

0 14 0

RCP Seal Cooling Evaluation Total Loss of RCP Seal Cooling Trips 1C RCP within 1 minute of loss of RCP seal cooling 0

14 0

0 14 0

RCP Seal Cooling Evaluation Total Loss of RCP Seal Cooling Restores cooling with PDP prior to reaching 230 0F on the #1 seal inlet temperature 0

14 0

0 14 0

RCP Seal Cooling Evaluation Small Break LOCA Determines RCS leakage into the Containment building 0

14 0

0 14 0

RCP Seal Cooling Evaluation Small Break LOCA Ensures Safety Injection is actuated and either continues on in 0POP05-EO-EO00 or Transition 0

14 0

0 14 0

RCP Seal Cooling Evaluation Small Break LOCA Determines RCS pressure has reached RCP Trip Criteria value 1

13 0

0 14 7.14 RCP Seal Cooling Evaluation Small Break LOCA Determines that RCP Trip criteria is NOT met due to effectively NOT having a HHSI in service 3

11 0

0 14 21.43 RCP Seal Cooling Evaluation Small Break LOCA (IF time permits) Declares an ALERT due to FA1 any Loss or ANY potential Loss of Fuel Clad o 0

12 0

0 12 0

[26] An Example of SACADA Detection Data

- Alarm board is busy 14 Desc.

Malfunction TOE (training objective element)

UNSAT SAT SAT SAT+

Total UNSAT Ratio(%)

CVCS Issues RC filter 1A plugs Responds to changes in indicated letdown flow (alarm response) 0 11 1

0 12 0

CVCS Issues RC filter 1A plugs Diagnoses indications as plugged RC filter (alarm response directed) 0 12 0

0 12 0

CVCS Issues RC filter 1A plugs Directs swapping of in service RC filter per 0POP02-CV-0004 0

12 0

0 12 0

CVCS Issues RC filter 1A plugs Verifies adequate level exists for Letdown diversion prior to diverting Letdown 0

11 0

0 11 0

CVCS Issues Loss of power to PL125F Diagnoses loss of PL125F (ICS computer point - Point INFO) 0 11 1

0 12 0

CVCS Issues Loss of power to PL125F Enters 0POP04-DA-0001 Loss of Non-Class 125 vdc 0

12 0

0 12 0

CVCS Issues Loss of power to PL125F Notes power exceeding limits and reduces power per Immediate Actions of 0POP04-MS-0001 0

9 2

1 12 0

CVCS Issues Loss of power to PL125F Determines need for additional CD flow, and directs/starts an additional CD pump per 0POP04-CD-000 0

11 1

0 12 0

CVCS Issues Loss of power to PL125F Throttles DA LVL valves to <80% to prevent CP bypass and slowly controls flow to restore level. (power 2

8 2

0 12 16.67 CVCS Issues Loss of power to PL125F Notifies QSE by ring down if power reduction of more than 25Mwe is necessary.

0 12 0

CVCS Issues Loss of CCW to LD HX Responds to alarms/indications on CP004. Performs alarm response 4M08/C3 1

11 0

0 12 8.33 CVCS Issues Loss of CCW to LD HX Diagnoses loss of cooling to Letdown HX 0

11 1

0 12 0

CVCS Issues Loss of CCW to LD HX Dispatches PO to CC-TV-4494 to inspect 0

12 0

0 12 0

CVCS Issues Loss of CCW to LD HX Enters and directs applicable steps of 0POP04-CV-0004.

0 12 0

CVCS Issues Loss of CCW to LD HX Directs bypass of CC-TV-4494 or directs placing Excess letdown in service to control inventory 0

12 0

0 12 0

CVCS Issues Loss of CCW to LD HX Directs swapping CVCS seal return to the VCT due to failure 0

10 0

0 10 0

CVCS Issues Loss of CCW to LD HX Controls Excess Letdown parameters to prevent lifting of seal return relief (150#)

1 9

0 0

10 10 CVCS Issues Low Stator Cooling Water DP Turbine trip Dispatches Operator to ZLP 119 to respond to Stator Cooling TRBL alarm 0

11 0

0 11 0

CVCS Issues Low Stator Cooling Water DP Turbine trip Diagnose Turbine trip due to low Stator Cooling Water DP 0

11 0

0 11 0

CVCS Issues Low Stator Cooling Water DP Turbine trip Enters 0POP05-EO-EO00 Reactor trip response 0

11 0

0 11 0

CVCS Issues Low Stator Cooling Water DP Turbine trip Performs Immediate actions from memory 0

11 0

0 11 0

[26] An Example of SACADA Detection Data -

- Alarm board is overloaded 15 Desc.

Malfunction TOE (training objective element)

UNSAT SAT SAT SAT+

Total NSAT Ratio(%

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Determines Temperature Indicator has Failed High 0

13 0

0 13 0

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Enters 0POP09-AN-08M3 window D-2 MSR TRBL 0

13 0

0 13 0

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Dispatches a Plant Operator to investigate 0

13 0

0 13 0

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Determines that computer point BD7400 indicates trouble 0

13 0

0 13 0

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Performs Addendum 1 of 0POP09-AN-08M3 window D-2 MSR TRBL 0

13 0

0 13 0

RCS LOCA to ES12 LP Turbine 11 Inlet Temperature Fails High Places the MSR Controller in Manual and restores MSR temperature 0

13 0

0 13 0

RCS LOCA to ES12 ECW Strainer Clogging Enters 0POP09-AN-02M4 and dispatches a Plant Operator to the ECW Structure 0

13 0

0 13 0

RCS LOCA to ES12 ECW Strainer Clogging Enters 0POP04-EW-0001 and takes actions to restore ECW 0

13 0

0 13 0

RCS LOCA to ES12 ECW Strainer Clogging Directs/Places ESF DG 13 in PTS and secures C train ECW/CCW 0

13 0

0 13 0

RCS LOCA to ES12 ECW Strainer Clogging Makes Plant Page to get other licensed personnel back into the Control Room 0

12 0

0 12 0

RCS LOCA to ES12 ECW Strainer Clogging Determines Essen Chiller 12C has tripped 0

13 0

0 13 0

RCS LOCA to ES12 ECW Strainer Clogging Determines that 1C ECW pump and all the cascading Train C equipment is INOPERABLE and enters 0

13 0

0 13 0