ML060830079

NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) to Discuss Cy 2005 Annual Assessment of Millstone Station

ML060830079
Person / Time
Site:	Millstone
Issue date:	03/24/2006
From:	Paul Krohn NRC/RGN-I/DRP/PB6
To:
Krohn P, RI/DRP/PB6/610-337-5120
Shared Package
ML060660562	List: ML060660570 ML060830079
References
MN 06-008
Download: ML060830079 (26)

Text

NRC & NEAC Meeting Concerning Millstone Station Performance Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006

Purpose of Todays Meeting A public forum for discussion of Millstone Stations annual performance for CY 2005 NRC will address Millstone Stations performance as discussed in the NRC annual assessment letter to Dominion Nuclear Connecticut, Inc.

NEAC will be given the opportunity to respond to the information, request clarifications, and ask additional questions as needed

Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Millstone Station Performance Results z NEAC Response and Remarks z NRC and NEAC Closing Remarks z Break z NRC available for public questions and comments

Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Brian E. Holian A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety David C. Lew Marsha K. Gamberoni Deputy Director Deputy Director Paul G. Krohn Regional Specialists Branch Chief Millstone Senior Project Engineers Resident Inspectors Scott Barber Max Schneider Barry Norris Jamie Benjamin Silas Kennedy

NRC Representatives z David C. Lew, Deputy Division Director, DRP

- (610) 337-5229 z Max Schneider, Senior Resident Inspector z Jamie Benjamin, Resident Inspector z Silas Kennedy, Resident Inspector

- (860) 447-3170 z Paul Krohn, Branch Chief

- (610) 337-5120 z Scott Barber, Senior Project Engineer

- (610) 337-5232

NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRC strategic objective

Reactor Oversight Process 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 ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr

Significance Threshold Performance Indicators Green: Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue

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 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103

National Summary z Performance Indicator Results (at end of CY 2005)

Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005)

Green 849 White 10 Yellow 1 Red 0

Millstone Assessment Results (Jan. 1 - Dec. 31, 2005) z Licensee Response Column z No safety significant findings or PIs

Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)

Hours of inspection related activities

- 5021 hours0.0581 days <br />1.395 hours <br />0.0083 weeks <br />0.00191 months <br /> at Millstone Unit 2

- 6115 hours0.0708 days <br />1.699 hours <br />0.0101 weeks <br />0.00233 months <br /> at Millstone Unit 3 Three resident inspectors assigned to the site

- Jamie Benjamin started at Millstone in June 2005 Inspections Regional Team Units 2 & 3 5 1 Unit 2 only 7 0 Unit 3 only 2 2

Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)

Inspection findings

- 3 findings of very low safety significance (Green) at Unit 2

- 12 findings of very low safety significance (Green) at Unit 3

- 2 findings of very low safety significance (Green) common to both units Unit 3 refueling outage (09/29 - 10/27/05)

- no findings related to the outage

Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)

Unit 2 Triennial Fire Protection team inspection

- no findings Unit 2 reactor head replacement inspection

- no findings Unit 3 safety system design team inspection

- no findings Unit 3 Special Inspection Team

- 6 findings of very low safety significance (Green)

Millstone Annual Assessment Summary (Jan. 1 - Dec. 31, 2005) z Dominion operated Millstone Units 2 & 3 in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans baseline inspections at Millstone for the remainder of the assessment period

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

(800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov Select What We Do for Public Affairs z Paul Krohn, Branch Chief pgk1@nrc.gov

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)

NEAC Response and Remarks Millstone Nuclear Power Station Unit 2 and Unit 3

END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006

Potential Public Interest Issues Safety Concerns Brought to the NRC z NRC has a formal process z Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and management z Issues of immediate concern receive prompt attention by NRC and by nuclear power plant management z NRCs process requires reviews of all valid safety issues to ensure they are adequately addressed z NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegation

Potential Public Interest Issues Recent Press Articles on Security Issues z Current NRC policy is to not discuss security matters in a public forum z NRC will not comment on existence of allegations in this area z Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take prompt action to address them

Potential Public Interest Issues Strontium-90 (SR-90) z Fission process byproduct (29 year half-life) z Potential sources in the Environment

- 16,800,000 curies - nuclear weapons testing (UNSCEAR 2001)

- 212,000 curies - 1986 Chernobyl accident (UNSCEAR 2001)

- 0.00012 to 0.001 curies - from all 103 operating nuclear power plants z For nuclear reactor releases, SR-89 (50 day half-life) is always present with SR-90

Potential Public Interest Issues Strontium-90 (SR-90) continued z Mid 1990s - Release levels of SR-90 were so low that nuclear utilities had difficulty measuring the amounts released z NRC allowed SR-90 monitoring by using goat milk samples z Goat milk samples indicated low levels of SR-90 without the presence of SR-89 (indicating not originating from a nuclear power plant) z Most likely source is from 1950s and 1960s atmospheric nuclear weapons testing

Potential Public Interest Issues Radiation Exposure to the Public from Background Sources and from Millstone Power Station z Natural

Background:

z Millstone Station Whole Body Dose 2 z Radon - 200 mrem (Maximum) Offsite Individual:

z Cosmic - 27 mrem z Cosmogenic - 1 mrem z Airborne Effluents - 0.0261 mrem z Terrestrial - 28 mrem z Liquid Effluents - 0.0017 mrem z Internal - 39 mrem z Onsite RadWaste Storage - 0.1400 mrem z Occupational - 0.9 mrem z Nuclear Fuel Cycle - 0.05 mrem z Consumer Products - 5 to 13 mrem

• Approximate Total: 0.17 mrem z Environment - 0.06 mrem z Medical:

z Diagnostic X- X-rays - 39 mrem z Nuclear Medicine - 14 mrem

• Approximate Total 1: 360 mrem

[ 1 USNRC Site Access Training Manual, October 1999 ]

[ 2 Millstone Power Station, 2004 Radioactive Effluents Release Report, Vol. 1 ]