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

Indian Point License Renewal Inspection Exit Meeting June 18, 2008 1

Welcome & Opening Remarks Sam Collins Regional Administrator, NRC Region I Richard Conte Chief Engineering Branch 1, DRS 2

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 3

Agenda

• License Renewal Process & Status

• Exit Meeting with Entergy

• Break

• Public Questions to NRC 4

LICENSE RENEWAL PROCESS & STATUS Richard Conte, Team Manager 5

License Renewal Process Onsite License Inspection Renewal 71002 Onsite Application Inspection Submitted To 71003 NRC Safety Evaluation Review Plant enters License Period of Safety renewed Extended Review Operation NRC Application Decision accepted by regarding Yes ACRS

• NRC Staff? Issuance of and Renewed Hearings Follow-up License inspection Environmental License Not (if needed)

Review Renewed Site No Environmental Continue Review Current Licensing Basis to

• Independent review by Advisory Committee on Reactor Safeguards (ACRS) is mandatory Expiration

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 7

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 8

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 9

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) 10

INSPECTION EXIT MEETING Glenn Meyer, Team Leader 11 License Renewal Inspection Objective - to verify the in-plant aspects of scoping, material condition, aging management program development, and documentation, supporting the license renewal application.

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 13 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 14

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 15 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 16

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 17 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 18

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 19 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.

Entergy Response 21 NRC Summary 22

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 23 BREAK 24

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.

Meeting Ground Rules (cont.)

• 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.

Public Questions for NRC

• Please use Q&A cards.

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