ML14247A261

NRC Slides for 95002 Presentation for Susquehanna & PPL Public Meeting

ML14247A261
Person / Time
Site:	Susquehanna
Issue date:	09/03/2014
From:	Fred Bower Reactor Projects Region 1 Branch 4
To:
BOWER, FL
Shared Package
ML 14247A237	List: ML14247A261
References
ML14232A345
Download: ML14247A261 (21)

Text

Susquehanna Steam Electric Station Susquehanna Steam Electric Station Supplemental Inspection Public Exit Supplemental Inspection Public Exit and Regulatory Performance Meeting f

U it 2 for Unit 2 Nuclear Regulatory Commission - Region I Berwick, PA September 3, 2014

Agenda Overview of Reactor Oversight Process Overview of Reactor Oversight Process Supplemental Inspection Objective and Scope Inspection Results and Observations Inspection Results and Observations PPL Response Action Matrix Next Steps ct o at e t Steps Closing Remarks Questions from the Public Adjourn Meeting

Reactor Oversight Process Safety Cornerstones Strategic Performance Areas Safety Cornerstones Strategic Performance Areas Cornerstones Baseline Inspection Results Performance Indicator Results Cornerstones Baseline Inspection Results Performance Indicator Results Results Significance Threshold Significance Threshold Results Significance Threshold Significance Threshold Threshold Action Matrix Threshold Action Matrix R

l t R

R l t R

Regulatory Response Regulatory Response

Action Matrix Concept Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple Repetitive Degraded Cornerstone Unacceptable Performance p

p g

All Inputs are Green; Cornerstone 1 or 2 White Inputs (in different 2 White or 1 Yellow Input; Cornerstone Objectives Met w/

Multiple Yellow Inputs or 1 Red Input; Cornerstone Objectives Overall Unacceptable Performance; Plants not permitted to 2 White Performance Indicators Unplanned Scrams Cornerstone Objectives Fully Met different cornerstones);

Cornerstone Objectives Fully Met Objectives Met w/

Moderate Degradation in Safety Performance Cornerstone Objectives Met w/ Significant Degradation in Safety Performance not permitted to Operate w/in this Column; Unacceptable Margin to Safety

- Unplanned Scrams with Complications >1

- Unplanned Scrams per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> > 3 Susquehanna Unit 2

• Increasing safety significance

• Increasing NRC inspection efforts Increasing NRC/Licensee management involvement

• Increasing NRC/Licensee management involvement

• Increasing regulatory actions

Safety Significant Performance Indicator

• Unplanned Scrams with Complications Indicator Unplanned Scrams with Complications

- Exceed green/white threshold (more than 1)

- Two scrams with complications Two scrams with complications

• Nov 9, 2012 - Shutdown required in response to a malfunction of the feed water control system.

• Dec 16, 2012 - Operator response to an automatic scram included reactor water level control challenges outside what is expected in a normal challenges outside what is expected in a normal scram.

- Performance Indicator returned to Green during the 4th quarter of 2013.

Unit 2 - 95001 Supplemental Inspection Results Inspection Results

• Inspection completed in September 2013 Inspection completed in September 2013

• All inspection objectives were met

• Focus of the inspection was:

- White Unplanned Scrams with Complications Performance Indicator S

ith C li ti N

b 9 2012

• Scram with Complications - November 9, 2012

• Scram with Complications - December 16, 2012

Safety Significant Performance Indicator

• Unplanned Scrams per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> Indicator p

p

- Exceeded green/white threshold (more than 3)

- Four unplanned scrams p

• November 9, 2012 (Integrated Control System Malfunction)

• December 16, 2012 (Turbine Control Valve Testing)

• December 19, 2012 (Loss of Feedwater)

September 14 2013 (Le el Transient d ring

• September 14, 2013 (Level Transient during Planned Shutdown)

- Performance Indicator returned to Green Performance Indicator returned to Green during the 4th quarter of 2013.

Unit 2 - 95002 Supplemental Inspection Objectives Provide assurance that the root and contributing f i k i

ifi t

f i

Inspection - Objectives causes of risk-significant performance issues are understood.

Independently assess the extent of condition and extent of cause.

Independently determine if safety culture components caused or significantly contributed to the performance issues the performance issues.

Provide assurance that the licensees corrective actions are sufficient to address the root and actions are sufficient to address the root and contributing causes and prevent recurrence.

Unit 2 - 95002 Supplemental Inspection Areas Covered

• Problem Identification Inspection - Areas Covered Problem Identification

• Root Cause Evaluation Corrective Actions

• Corrective Actions

• Independently Assess Extent of Condition

• Independently Assess Extent of Cause

• Safety Culture Assessment y

Inspection requirements that were common to the successfully completed 95001 inspection were not re successfully completed 95001 inspection were not re-inspected

Unit 2 - 95002 Supplemental Inspection Dates and Team

• Conducted July 14 July 31 2014 Inspection - Dates and Team

• Conducted July 14 - July 31, 2014 S

i R

id t I t

(L d)

• Senior Resident Inspector (Lead),

• Senior Reactor Inspector,

• 2 Resident Inspectors,

• 2 Project Engineers and 2 Project Engineers, and

• Safety Culture Expert

Unit 2 - 95002 Supplemental Inspection Conduct

• Document Review Inspection - Conduct Document Review

• Independent Safety Culture Review (F

G i t i

)

(Focus Group interviews)

• Interviews, observations, and verification Interviews, observations, and verification

• Independent review of Root Cause E

l ti Evaluations

• Related issue review; Extent of Cause Related issue review; Extent of Cause and Extent of Condition

Unit 2 - 95002 Supplemental Inspection Focus

• Degraded Cornerstone for Initiating Events Inspection - Focus Degraded Cornerstone for Initiating Events

• White Unplanned Scrams Per 7000 Critical Hours Performance Indicator

• Previously inspected scrams on November

• Previously inspected scrams on November 9, 2012 and December 16, 2012

• Scrams on December 19, 2012 and September 14, 2013 p

Common Cause Assessment for Degraded Cornerstone

• 2 Root Causes Degraded Cornerstone 2 Root Causes

- Less Than Adequate Decision-making Related to Integrated Control System Design Related to Integrated Control System Design Scope (Single Point Vulnerabilities) and Operating Experience Reviews Operating Experience Reviews

- Less Than Adequate Management Reinforcement and Personal Accountability for Procedure Use and Adherence in O

ti d E i

i D

t t

Operations and Engineering Departments

Common Cause Assessment Key Corrective Actions

• Accountability with Respect Model Key Corrective Actions Accountability with Respect Model

- Change Organizational Behavior R

i H

P f

T l I l

t ti

• Revise Human Performance Tools Implementation Guide (additional tools for Engineers and Workers)

• Modify Integrated Control System to address Single Point Vulnerabilities

• Revise Design Guide for Failure Modes and Effects Analysis - Provide specific guidance on how to Analysis Provide specific guidance on how to disposition Single Point Vulnerabilities

Unit 2 - 95002 Supplemental Inspection Results

• Green Non-cited Violation Inspection - Results Green Non cited Violation

- TS 5.4.1 for improperly maintaining a required procedures for operation of the Integrated procedures for operation of the Integrated Control System G

l W k

• General Weaknesses

- Operator Performance

- Accountability with Respect

- Operating Experience Process

- Design Control Process

PPL Response and Remarks Robert Franssen General Manager - Operations g

p PPL S h

LLC PPL Susquehanna, LLC

Action Matrix Follow Up Assessment Assessment Ho Nieh Director Division of Reactor Director, Division of Reactor Projects USNRC Region I g

Action Matrix Process and Next Steps

• Perform Onsite 95002 Inspection Steps Perform Onsite 95002 Inspection

- Complete and Objectives Met

• Conduct Public Performance Assessment Meeting

- Completed Tonight

• Assess Colors of Current Performance Indicators and Inspection Findings

- Currently All Green

• Issue 95002 Inspection Report and Follow up

• Issue 95002 Inspection Report and Follow-up Assessment Letter

- within 45 days y

Open to the Public

• The NRC places a high priority on keeping The NRC places a high priority on keeping the public and stakeholders informed of its activities.

activities.

• At WWW.NRC.GOV, you can:

- Find public meeting dates and transcripts;

- Read NRC testimony, speeches, press releases, and policy decisions; and policy decisions; and

- Access the agencys Electronic Reading Room to find NRC publications and documents.

Contacting the NRC

• Report an emergency Report an emergency

- (301) 816-5100 (call collect)

Report a safety concern

• Report a safety concern

- (800) 695-7403

- Allegation@nrc.gov

• General information or questions

- www.nrc.gov

- Select What We Do for Public Affairs

Reference Sources

• Reactor Oversight Process g

- http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index

.html Public Electronic Reading Room

- http://www.nrc.gov/reading-rm.html Public Document Room 800-397-4209 (Toll Free)