ML081770217: Difference between revisions

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| number = ML081770217
| number = ML081770217
| issue date = 06/23/2008
| issue date = 06/23/2008
| title = 06/23/2008 Public Meeting Slides, Braidwood Annual Assessment Meeting, Reactor Oversight Program - Cy 2007
| title = Public Meeting Slides, Braidwood Annual Assessment Meeting, Reactor Oversight Program - Cy 2007
| author name =  
| author name =  
| author affiliation = NRC/RGN-III
| author affiliation = NRC/RGN-III

Latest revision as of 06:09, 7 December 2019

Public Meeting Slides, Braidwood Annual Assessment Meeting, Reactor Oversight Program - Cy 2007
ML081770217
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 06/23/2008
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NRC/RGN-III
To:
References
FOIA/PA-2010-0209
Download: ML081770217 (30)


Text

Braidwood Annual Assessment Meeting Reactor Oversight Program - CY 2007 Nuclear Regulatory Commission - Region III Braidwood, IL June 23, 2008

Purpose of Todays Meeting z To provide a public forum for the discussion of Braidwood Stations performance z The NRC will address licensee performance issues identified in the annual assessment letter z The Licensee will be provided an opportunity to respond to any information in the letter and discuss new or existing programs to maintain or improve performance

Agenda z Description of NRC Activities z Introduction z Review of the Reactor Oversight Process (ROP) z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z The NRC will be available after the meeting to address any public questions

Our Mission To license and regulate the nations civilian use of byproduct, source and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment.

NRC Goals Safety: Ensure adequate protection of public health and safety and the environment.

Security: Ensure adequate protection in the secure use and management of radioactive materials.

Some Nuclear Facts More than 100 nuclear power plants supply about 20 percent of the electricity in the U.S.

Nuclear materials are used in medicine for cancer treatment and diagnosis.

Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices and irradiators.

The NRC Regulates:

Nuclear reactors - commercial power reactors, research and test reactors, new reactor designs; Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial and academic use; Nuclear waste - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities; and Nuclear security - physical security of nuclear facilities and materials from sabotage or attacks.

What We Dont Do:

Regulate nuclear weapons, military reactors or space vehicle reactors. (These are regulated by other federal agencies.)

Own or operate nuclear power plants.

Regulate some radioactive materials, such as naturally occurring radon, X-rays and material produced in particle accelerators.

(These are regulated by states or other federal agencies.)

How We Regulate Establish rules and regulations Issue licenses Provide oversight through inspection, enforcement, and evaluation of operational experience Conduct research to provide support for regulatory decisions Respond to events and emergencies

Assurance of Plant Safety Require defense-in-depth Require long-term maintenance of equipment Require continual training of operators Verify compliance with regulations

What We Do - Nuclear Waste The NRC regulates:

  • Storage of spent reactor fuel in fuel pools or dry storage casks, and
  • Any potential national spent fuel storage site.

What We Do - Nuclear Security The NRC Requires:

  • Well-armed and well-trained security forces,
  • Surveillance and perimeter patrols,
  • State-of-the-art site access equipment and controls,
  • Physical barriers and detection zones, and
  • Intrusion detection systems and alarm stations.

Region III Organization James Caldwell Regional Administrator Mark Satorius Deputy Regional Administrator Cynthia Pederson Steve West Director Division of Reactor Projects (DRP) Director Division of Reactor Safety (DRS)

Gary Shear Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Project Engineer Resident Inspectors Billy Dickson Reactor Engineer Alex Garmoe Jennifer Dalzell

NRC Representatives z Billy Dickson, Senior Resident Inspector

- (815) 458-2853 z Gregory Roach, Senior Resident Inspector - LaSalle

- (815) 358-8611 z Alex Garmoe, Resident Inspector

- (815) 458-2853 z Richard Skokowski, Branch Chief, DRP

- (630) 829-9620 z Marshall David, Project Manager, NRR

- (301) 415-1547

NRC Representatives z Viktoria Mitlyng, Office of Public Affairs

- (630) 829-9662 z Prema Chandrathil, Office of Public Affairs

- (630) 829-9663 z Steve Orth, Branch Chief - Radiation Protection Branch, DRS

- (630) 829-9827 z Stephanie Bush-Goddard, Branch Chief -

Health Effects Branch, RES

- (301) 415-6293

Reactor Oversight Process (ROP)

Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response

Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~250 hrs/3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Radiological Release Controls ~110 hrs/2 yrs z Worker Radiation Protection ~95 hrs/yr z Corrective Action Program ~250 hrs/2 yrs z Corrective Action Reviews ~60 hrs/yr

Significance Threshold Performance Indicators Green:

Green Baseline Inspection only White:

White May increase NRC oversight Yellow:

Yellow Requires more NRC oversight Red:

Red Requires more NRC oversight Inspection Findings Green:

Green Very low safety significance White:

White Low to moderate safety significance Yellow:

Yellow Substantial safety significance Red:

Red High safety significance

Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions

National Summary of Plant Performance Status at End of CY 2007 Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104

National Summary z Performance Indicator Results (End of CY 2007)

Green 1942 White 8 Yellow 1 Red 0 z Total Inspection Findings (CY 2007)

Green 759 White 9 Yellow 2 Red 0

Braidwood Assessment Results (Jan 1 - Dec 31, 2007) z Safety performance for the last 3 quarters of 2007 Braidwood Units 1 and 2 were within the Licensee Response column of the NRC Action Matrix.

z Braidwood Units 1 and 2 were within the Regulatory Response column for the 1st quarter of 2007 due to a White finding in the Public Radiation Safety Cornerstone that occurred in the 1st quarter of 2006.

Safety Significant Findings or PIs z No safety significant findings were identified during this assessment period.

z During the week of January 29, 2007, the NRC conducted a supplemental inspection using Inspection Procedure 95001 for the 1st quarter 2006 White finding in the Public Radiation Safety Cornerstone. No findings of significance were identified.

NRC IP 95001 Evaluation Inspections encompassed activities from the initial response through evaluating Braidwoods root cause evaluation &

corrective actions.

z Initial Response Source of contamination and evaluation Storage of water while repairing the discharge path z Review of remediation actions and resumption of liquid releases Integrity of blowdown line Integrity of modified vacuum breaker valve vaults including leak detection and alarm system z Independent dose calculation z Independent and duplicate analyses of water samples z External communications

Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z 12 findings during the assessment period:

8 in mitigating systems 2 in barrier integrity 2 in occupational radiation safety z One additional finding was evaluated separately using the traditional enforcement process.

Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z Unit 1:

- power operations

- automatic reactor trip due to an offsite grid disturbance

- refueling outage z Unit 2:

- power operations

- manual reactor trip due to a loss of condenser vacuum z Independent Groundwater Monitoring Activities:

- Supplemental Inspection 95001 conducted in January 2007

- Walkdowns of the Circulating Water blowdown line quarterly

- Independent validation of groundwater sample results

Braidwood Annual Assessment Summary (Jan 1 - Dec 31, 2007) z Exelon Nuclear operated Braidwood Units 1 and 2 in a manner that preserved public health and safety z All cornerstone objectives were met during this assessment period.

z NRC plans to conduct baseline inspections at Braidwood for the remainder of the current assessment period.

z A supplemental 95001 inspection was conducted during the week of January 29, 2007 with no significant findings.

Licensee Response and Remarks Bryan Hanson Site Vice President Braidwood Generating Station

Contacting the NRC z To Report an emergency (301) 816-5100 (call collect) z To Report a safety concern:

(800) 695-7403 Allegation@nrc.gov z For general information or questions www.nrc.gov Select What We Do for Public Affairs

Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.

html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)