ML051600329
| ML051600329 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 06/08/2005 |
| From: | Cobey E NRC Region 1 |
| To: | |
| Cobey, Eugene W. RI/DRP/PB3 610-337-5171 | |
| Shared Package | |
| ML050750455 | List: |
| References | |
| Download: ML051600329 (34) | |
Text
1 Salem and Hope Creek Annual Assessment Meeting Nuclear Regulatory Commission - Region I King of Prussia, PA June 8, 2005 Reactor Oversight Process 2004 Assessment
2 Agenda Opening Remarks NRC Presentation
- ROP Overview
- National Summary of Plant Performance
- Salem and Hope Creek Performance Results PSEG Presentation
- Response to Performance Results
- Update on Progress to Improve Work Environment Closing Remarks Break NRC Available to Address Questions
3 NRC Representatives S. Collins, Regional Administrator, Region I A. Randolph Blough, Director, Division of Reactor Safety M. Gamberoni, Deputy Director, Division of Reactor Projects E. Cobey, Chief, Projects Branch 3 M. Gray, Senior Resident Inspector, Hope Creek M. Ferdas, Resident Inspector, Hope Creek D. Orr, Senior Resident Inspector, Salem G. Malone, Resident Inspector, Salem S. Bailey, Salem Project Manager, NRR D. Collins, Hope Creek Project Manager, NRR J. Persensky, Senior Human Factors Specialist, RES A. Kock, Assistant Agency Allegations Advisor, OE
4 Purpose of Todays Meeting Provide a public forum for discussion of the Salem and Hope Creek stations performance NRC will address Salem and Hope Creek performance as discussed in the annual assessment letters PSEG will respond to the annual assessment and provide the NRC an update on their actions to improve performance in the following areas:
- Safety conscious work environment;
- Problem identification and resolution;
- Procedure adherence and other elements of human performance; and
- Quality of engineering products particularly as they relate to evaluation of degraded equipment and associated operational decision making.
5 NRC Performance Goals Safety: Ensure protection of public health and safety and the environment Security: Ensure the secure use and management of radioactive materials Openness: Ensure openness in our regulatory process Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely Management: Ensure excellence in agency management to carry out the NRCs strategic objective
6 Regulatory Framework REACTOR SAFETY PUBLIC HEALTH AND SAFETY AS A RESULT OF CIVILIAN NUCLEAR REACTOR OPERATION RADIATION SAFETY SAFEGUARDS NRCs Overall Safety Mission Strategic Performance Areas INITIATING EVENTS MITIGATING SYSTEMS BARRIER INTEGRITY EMERGENCY PREPAREDNESS PUBLIC RADIATION SAFETY OCCUPATIONAL RADIATION SAFETY PHYSICAL PROTECTION Cornerstones HUMAN PERFORMANCE SAFETY CONSCIOUS WORK ENVIRONMENT PROBLEM IDENTIFICATION AND RESOLUTION Cross-Cutting Areas
7 Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas
8 Examples of Baseline Inspections Equipment Alignment
~92 hrs/yr Triennial Fire Protection
~200 hrs every 3 yrs Operator Response
~125 hrs/yr Emergency Preparedness
~80 hrs/yr Rad Release Controls
~100 hrs every 2 yrs Worker Radiation Protection ~100 hrs/yr Corrective Action Program
~250 hrs every 2 yrs Corrective Action Reviews
~60 hrs/yr Safety System Design
~420 hrs every 2 yrs
9 Significance Threshold High safety issue Red:
Substantial safety issue Yellow:
Low to moderate safety issue White:
Very low safety issue Green:
Inspection Findings Requires more NRC oversight Red:
Requires more NRC oversight Yellow:
May increase NRC oversight White:
Only Baseline Inspection Green:
Performance Indicators
10 NRC Response Plan or "Action Matrix" Increased Safety Significance Increased NRC Inspection Efforts Increased NRC/Licensee Management Involvement Increased Regulatory Actions Licensee
Response
Regulatory
Response
Degraded Cornerstone Multiple/Rep.
Degraded Cornerstone Unacceptable Performance
11 National Summary of Plant Performance 102*
TOTAL UNITS 0
Unacceptable 3
Multiple/Repetitive Degraded Cornerstones 0
Degraded Cornerstone 21 Regulatory Response 78 Licensee Response Status at End of CY 2004
- Davis-Besse was in Shutdown with Enhanced Oversight in 2004
12 National Summary 0
Red:
0 Yellow:
11 White:
778 Green:
Total Inspection Findings (2004) 0 Red:
0 Yellow:
6 White:
1834 Green:
Performance Indicator Results (at end of 2004)
13 Salem Inspection Activities 7290 Hours of Inspection Related Activities Baseline Inspections and Performance Indicator Verifications Completed 2 Full-Time Resident Inspectors at Salem Station 18 Regional Specialist Inspection Activities 2 Team Inspections (January 1 - December 31, 2004)
14 Salem 1 Assessment Inputs Inspection Findings
- 16 Findings of Very Low Safety Significance (Green)
- 1 Finding of Low to Moderate Safety Significance (White)
- Individual Findings Evaluated for Common Themes (Cross-Cutting Issues)
Performance Indicators
- All Indicators Green
15 Salem 2 Assessment Inputs Inspection Findings
- 14 Findings of Very Low Safety Significance (Green)
- Individual Findings Evaluated for Common Themes (Cross-Cutting Issues)
Performance Indicators
- All Indicators Green
16 Salem Assessment Summary Overall, both units operated in a manner that preserved public health and safety At the end of CY 2004
- Salem Unit 1 - Regulatory Response One inspection finding classified as having low to moderate safety significance (White)
- Salem Unit 2 - Licensee Response Substantive cross-cutting issues
- Problem identification and resolution (PI&R)
- Safety conscious work environment (SCWE)
January 1 - December 31, 2004
17 ROP Deviation Memorandum August 23, 2004 Salem 1 Performance 2004 2003 2002 2001 2000 WHITE Finding Insufficient Switchgear Room CO2 Concentration WHITE Performance Indicator Unplanned Scrams WHITE Performance Indicator Unplanned Power Changes WHITE Finding Emergency Diesel Generator Turbo Charger Failure Regulatory Response Licensee Response RR LR Regulatory Response NRC Action Matrix and Oversight PI&R SCWE Cross-Cutting Issues ROP Dev.
18 Salem 2 Performance 2004 2003 2002 2001 2000 WHITE Finding Insufficient Switchgear Room CO2 Concentration NRC Action Matrix and Oversight ROP Deviation Memorandum August 23, 2004 Regulatory Response PI&R SCWE Cross-Cutting Issues ROP Dev.
Licensee Response
19 Hope Creek Inspection Activities 8088 Hours of Inspection Related Activities Baseline Inspections and Performance Indicator Verifications Completed 2 Full-Time Resident Inspectors 14 Regional Specialist Inspection Activities 4 Team Inspections (January 1 - December 31, 2004)
20 Hope Creek Assessment Inputs Inspection Findings
- 24 Findings of Very Low Safety Significance (Green)
- 2 Findings of Low to Moderate Safety Significance (White)
- Individual Findings Evaluated for Common Themes (Cross-Cutting Issues)
Performance Indicators
- All Indicators Green
21 Hope Creek Assessment Summary Overall, Hope Creek operated in a manner that preserved public health and safety At the end of CY 2004
- Hope Creek - Regulatory Response Two inspection findings classified as having low to moderate safety significance (White)
Substantive cross-cutting issues
- Problem identification and resolution (PI&R)
- Safety conscious work environment (SCWE)
January 1 - December 31, 2004
22 Hope Creek Performance 2004 2003 2002 2001 2000 WHITE Finding Moisture Separator Level Control Valve Failure WHITE Finding A Service Water Traveling Screen Failure NRC Action Matrix and Oversight ROP Deviation Memorandum August 23, 2004 Licensee Response PI&R SCWE Cross-Cutting Issues ROP Dev.
Regulatory Response
23 Hope Creek Performance Indicators Reactor Safety Radiation Safety Safeguards Performance Indicators Unplanned Scrams (G)
Emergency AC Power System Unavailability (G)
Reactor Coolant System Activity (G)
Drill/Exercise Performance (G)
Occupational Exposure Control Effectiveness (G)
RETS/ODCM Radiological Effluent (G)
Initiating Events Mitigating Systems Barrier Integrity Emergency Preparedness Occupational Radiation Safety Public Radiation Safety Physical Protection (NOT PUBLIC)
Scrams With Loss of Normal Heat Removal (G)
High Pressure Injection System Unavailability (G)
Reactor Coolant System Leakage (G)
ERO Drill Participation (G)
Unplanned Power Changes (G)
Heat Removal System Unavailability (G)
Alert and Notification System (G)
Residual Heat Removal System Unavailability (G)
Safety System Functional Failures (G)
24 Hope Creek Inspection Findings Reactor Safety Radiation Safety Safeguards Most Significant Inspection Findings No findings this quarter Initiating Events Mitigating Systems Barrier Integrity Emergency Preparedness Occupational Radiation Safety Public Radiation Safety Physical Protection (NOT PUBLIC)
No findings this quarter No findings this quarter No findings this quarter G
No findings this quarter No findings this quarter No findings this quarter No findings this quarter No findings this quarter No findings this quarter No findings this quarter No findings this quarter G
No findings this quarter No findings this quarter No findings this quarter G
Miscellaneous findings G
G W (1)
W (1)
No findings this quarter No findings this quarter 4Q/2004 3Q/2004 2Q/2004 1Q/2004
25 Cross-Cutting Issues Problem Identification and Resolution (PI&R)
- PI&R cross-cutting issue continued throughout 2004 at Salem and Hope Creek based on a continuation of inspection findings and documented shortcomings within the PI&R area
- 27 (14 Salem and 13 Hope Creek) inspection findings attributable, at least in part, to weaknesses in problem identification, problem evaluation and effectiveness of corrective actions
- Fifth consecutive assessment with substantial cross-cutting issue in PI&R
26 Cross-Cutting Issues Safety Conscious Work Environment (SCWE)
- Established during the 2004 mid-cycle performance assessment based on the results of the NRCs review of the work environment at Salem and Hope Creek.
- PSEG has taken significant steps to evaluate the stations work environment and initiated actions to begin addressing deep-seated causes.
- It is too early to effectively assess whether or not the work environment at the station is significantly improving.
- The SCWE cross-cutting issue will continue.
27 ROP Deviation On August 23, 2004 the NRC Executive Director for Operations approved a deviation from the Action Matrix for Salem and Hope Creek Result of the substantive cross-cutting issue in SCWE and the longstanding cross-cutting issue in PI&R Authorizes a greater level of oversight for the Salem and Hope Creek stations than would typically be called for by the Regulatory Response Column of the Action Matrix including:
- More frequent and an elevated level of NRC management involvement in meetings, site visits, and correspondence
- Established an internal NRC coordination team Assist Region I staff in review and evaluation of PSEG efforts Regional and headquarters experts in reactor oversight, SCWE and related performance attributes
- Review of PSEGs improvement plans with respect to SCWE and related performance attributes
- Enhanced baseline inspections, as necessary, to verify the effectiveness of PSEG improvement The heightened oversight will continue until PSEG has concluded that substantial, sustainable progress has been made; and the NRC has completed a review, the results of which confirm PSEGs assessment results.
28 Ways for the Public To Become Informed &
Involved in the Regulatory Process Participate in NRC Public Meetings Sign up to be on the NRC mailing list Visit the NRC website on a regular basis Publicly comment on proposed licensing actions or file a Petition for Rulemaking Implement 10 CFR 2.206 petition process Contact the NRC via E-mail, mail or phone to address questions or areas of concern Participate in open NRC/industry symposiums Request information through the Freedom of Information Act (FOIA)
29 Reference Sources Reactor Oversight Process
- http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Public Electronic Reading Room
- http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)
Public Comment & Involvement in Rulemaking
30 Contacting the NRC Report an emergency
- (301) 816-5100 (call collect)
Report a safety concern
- (800) 695-7403
- Allegation@nrc.gov General information or questions
- www.nrc.gov/what-we-do/public-affairs.html
- Diane Screnci, Senior Public Affairs Officer (610) 337-5330
- Neil Sheehan, Public Affairs Officer (610) 337-5331 Main Contact
- Eugene Cobey, Branch Chief, Division of Reactor Projects
- (610) 337-5171
- Email at: EWC@nrc.gov
31 PSEG Response/Remarks PSEG response to annual assessment and remarks regarding their actions to improve performance in the following areas:
- Safety conscious work environment;
- Problem identification and resolution;
- Procedure adherence and other elements of human performance; and
- Quality of engineering products particularly as they relate to evaluation of degraded equipment and associated operational decision making.
32 NRC Closing Remarks
33 BREAK Following a 10 minute break, the NRC will take questions/comments from the public.
34 Public Questions/Comments CONTACTING THE NRC
- Report an emergency (301) 816-5100 (call collect)
- Report a safety concern (800) 695-7403 Allegation@nrc.gov
- General information or questions www.nrc.gov/what-we-do/public-affairs.html Diane Screnci, Senior Public Affairs Officer
- (610) 337-5330 Neil Sheehan, Public Affairs Officer
- (610) 337-5331
- Main Contact Eugene Cobey, Branch Chief, Division of Reactor Projects (610) 337-5171 Email at: EWC@nrc.gov