ML081840487

NRC/DRS/EB1 Slides for Indian Point License Renewal Exit Meeting, June 18, 2008

ML081840487
Person / Time
Site:	Indian Point
Issue date:	07/02/2008
From:	Collins S, Conte R Engineering Region 1 Branch 1, Region 1 Administrator
To:
Valentin-Olmeda, M
References
Download: ML081840487 (15)

Text

1 Indian Point License Renewal Inspection Exit Meeting June 18, 2008 2 Welcome & Opening Remarks Sam Collins Regional Administrator, NRC Region I Richard Conte Chief Engineering Branch 1, DRS 3 Introductions

• NRC meeting representatives:

-S. Collins, Regional Administrator

-D. Roberts, Deputy Director, DRS, Region 1

-R. Conte, Chief, Engineering Branch 1, DRS, Region I

-R. Franovich , Chief, License Renewal Branch B, NRR

-G. Meyer, Sr. Reactor Inspector/Team Leader, DRS, Region I

• Entergy meeting representatives:

-F. Dacimo , Vice President, License Renewal, IPEC

-G. Young, Manager, License Renewal, Entergy

-J. Curry, Sr. Project Manager, License Renewal, IPEC

-M. Stroud, Manager, Business Development, Entergy

-A. Cox, Manager, Project Management, Entergy 4 Agenda*License Renewal Process & Status

• Exit Meeting with Entergy

• Break*Public Questions to NRC 5 LICENSE RENEWAL PROCESS & STATUS Richard Conte, Team Manager ACRS *and Hearings Safety Evaluation Review Onsite Inspection 71002 Safety Review Environmental Review License Renewal Application Submitted To NRC Site Environmental Review* Independent review by Advisory Committee on Reactor Safeguard s (ACRS) is mandatory License Renewal Process Plant enters Period of Extended Operation Onsite Inspection 71003 Follow-up inspection (if needed)

Yes No License Not Renewed Continue Current Licensing Basis to Expiration Application accepted by NRC Staff?

NRC Decision regarding Issuance of Renewed License License renewed 7 Key Dates*April 23 / May 3 / June 21, 2007

-Entergy submits application for IP Units 2 & 3

• July 25, 2007

-Application accepted by NRC

• January 28

-February 14, 2008

-Planned onsite inspection

• April 30, 2008

-Entergy reports Unit 2 Station Blackout (SBO)

Diesel installed and operational 8 Key Dates*Tentative Dates for NRC Decision:

-July 2009 (No Hearing)

-April 2010 (Hearing)

• License Expiration Dates:

-IP2: Sep. 28, 2013

-IP3: Dec. 12, 2015

-Note: IP1 is in safe storage status not subject to license renewal 9 Environmental Review

• Environmental review in progress

-Planned site reviews completed by NRC staff

• Review Entergy responses

• September 2008

-Tentative schedule for draft Supplemental Environmental Impact Statement (SEIS)

• October 2008

-Tentative public meeting on draft SEIS 10 Safety Review

• Safety review is in progress

-Planned site reviews completed by NRC Staff

• Inspection completed

-Major effort completed February 2008

-Follow-up weeks March 30 and June 2, 2008

• June 18, 2008

-Public Inspection Exit

• September 2008

-Initial Safety Evaluation Report (SER) 11 INSPECTION EXIT MEETING Glenn Meyer, Team Leader License Renewal Inspection O bjective -to verify the in

-plant aspects of scoping, material condition, aging management program development, and documentation, supporting the license renewal application.

13 Scope of Inspection

• NRC team -approximately 1,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> to date (8 inspectors)

• Reviewed:-Effects of non

-safety structures & components on safety related equipment-Aging Management Programs (AMP)

• Implementation checks for existing programs

• Feasibility of implementation for modified or new programs

-Documentation is auditable, retrievable and supports the application

• Methods:-Walkdowns in plant areas

-Reviews of procedures & records

-Interviews 14 Overall Results of the Inspection

• Observations will be documented in the following areas:-Scoping of non

-safety systems

-Existing and Modified/New Aging Management Programs*These observations will be used to;

-Provide for Headquarters consideration on its safety evaluation

-Be incorporated into the licensing corrective action process 15 Observations Resulting in Application Revision

• Structural Monitoring Program

-IP3 service water pump fiberglass baffling not included

• Selective Leaching Program for certain alloys and various water environments

-Sampling technique unclear

• Diesel Fuel Monitoring Program

-Inappropriate testing for wall thickness of IP3 fuel storage tanks

-Deficient procedures for IP2 sample location and process-Procedures omitted fuel tank for IP2 security diesel generator 16 Observations Resulting in Application Revision

• Water Chemistry

-Closed Cooling Program

-Testing for pH and glycol not specified

• Bolted Cable Connections Monitoring Program

-Inspection methods inconsistent with NRC draft guidance*Metal Enclosed Bus (MEB) Monitoring Program

-Unclear acceptance criteria for internal inspections

• Lubricating Oil Program

-Reactor Coolant Pump (RCP) motor coolers not included 17 Other Observations For Applicant Review

• Material conditions not in corrective action program-Boric acid leaks

-Concrete-Fire protection equipment

• Containment visual indications

-Additional measurements are being considered to supplement visual observations of exposed rebar 18 Other Observations For Applicant Review

• Operating experience review on MEB

-Basis documentation did not include inoperable bus example in 2004

• IP2 Instrument air heat exchangers

-Not included in heat exchanger monitoring program

• Cable separation material

-Transite material used in some locations not identified in aging management review 19 Follow-up Inspection Observations

• Containment Internal Inspection

-Inspectors confirmed acceptable material condition*Manhole Inspection

-Water found

-pumped out

-cables used with water submergence being reviewed by Headquarters

• Station Blackout (SBO) Diesel Inspection

-SBO was included in the current licensing basis to supplement the LRA

-For purposes of license renewal, scoping and screening was consistent with LRA

-Current operation issues addressed by ROP Summary of observation results*The effects of non

-safety structures &

components on safety related equipment are adequately addressed with few

exceptions noted.

• AMPs can be implemented with few exceptions noted.

• Documentation is auditable, retrievable and supports the application

-no exceptions noted.

21 Entergy Response 22 NRC Summary 23 Additional Information

• NRC Homepage

-www.nrc.gov

• Indian Point 2 Current Performance Summary

-www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip2_chart.html

• Indian Point 3 Current Performance Summary

-www.nrc.gov/NRR/OVERSIGHT/ASSESS/IP2/ip3_chart.html

• Indian Point "Specific Plant of Interest" Page

-www.nrc.gov/reactors/plant

-specific-items/indian

-point-issues.html

• Indian Point License Renewal Review Status

-www.nrc.gov/reactors/operating/licensing/renewal/applications/in dian-point.html 24 BREAK Meeting Facilitator Richard Barkley, PE Nuclear & Environmental Engineer

-Technical Communications Assistant for Region I Meeting Ground Rules

• Please be respectful of the speaker

-only one speaker at a time.

• To be fair to the other questioners, please limit your remarks to about 5 minutes (There are many people who want to speak).*The moderator will alternate between elected officials and the public at the start

of the meeting.

Meeting Ground Rules (cont.)*Speakers will be called to the microphone up front -NRC can not field questions from the audience due to its size.

• Order called will vary from the sign

-up order to ensure all groups are heard.

• See NRC staff if you have procedural questions / concerns or still want to sign

up.*Please silence cell phones and pagers

-Thank you!

• If you posed a question that NRC has committed to reply to later, please make

sure of exchanging contact information.

• NRC staff members will be available after the meeting.

Meeting Ground Rules (cont.)

29 Public Questions for NRC

• Please use Q&A cards.