ML111250238

Summary of Category 1 Public Meeting with Entergy on the Transfer of Spent Fuel from Unit 3 to Unit 2 at Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. ME1671, ME1672, and L24299)

ML111250238
Person / Time
Site:	Indian Point
Issue date:	05/09/2011
From:	Boska J Plant Licensing Branch 1
To:
Boska J, NRR/DORL/LPLI-1, 301-415-290
References
TAC ME1671, TAC ME1672, TAC L24299
Download: ML111250238 (3)

Text

REGlI( UNITED STATES "t;'01l NUCLEAR REGULATORY COMMISSION

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't" ~o May 9, 2011 LICENSEE: Entergy Nuclear Operations, Inc.

FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3

SUMMARY

OF APRIL 28, 2011, MEETING WITH ENTERGY ON THE TRANSFER OF SPENT FUEL FROM UNIT 3 TO UNIT 2 AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. ME1671, ME1672, AND L24299)

On April 28, 2011, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (the licensee) and Holtec International, Inc., one of the licensee's contractors, at the NRC's Executive Boulevard Building, 6003 Executive Boulevard, Rockville, Maryland. The purpose of the meeting was to discuss progress on the project and the NRC staffs request for additional information (RAI) dated March 16, 2011, which is publicly available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML110690446. The NRC's RAlletter was in response to Entergy's license amendment requests to authorize the transfer of spent fuel from the spent fuel pool at Indian Point Nuclear Generating Unit NO.3 (IP3) to the spent fuel pool at Indian Point Nuclear Generating Unit No.2 (IP2) using a newly designed shielded transfer canister (STC) and an external shield cask (the HI-TRAC). From there, Entergy intends to transfer the spent fuel to the independent spent fuel storage installation which already exists at the site.

The licensee presented information on the scope of the project and methods they would use to respond to the RAI questions. Areas of discussion included the following: 1) which section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code would govern the design and fabrication of the STC; 2) which analysis methods and codes could be used for the criticality analyses; 3) what are the expected doses to plant workers from handling the STC, and how can these doses be minimized; and 4) what methods can be used to prevent or detect the loading of fuel assemblies into the STC that do not meet the design requirements of the STC.

A list of attendees is provided as Enclosure 1, but may not be all inclusive. The licensee's slide presentation is provided as Enclosure 2.

-2 No Public Meeting Feedback forms have been received. Please direct any inquiries to me at 301-415-2901, or by email to John.Boska@nrc.gov.

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J hn P. Boska, Senior Project Manager lant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosures:

1. List of Attendees

2. Licensee Slides cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION MEETING ATTENDANCE FORM

Subject:

Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location: Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY NAME ORGANIZATION Enclosure 1

UNITED STATES NUCLEAR REGULATORY COMMISSION MEETING ATTENDANCE FORM

Subject:

Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location: Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY I

NAME ORGANIZATION I

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Introductions

• Nuclear Regulatory Commission

• Entergy - Indian Point Energy Center

- Oscar Limpias (V.P. Engineering)

- John McCann (V.P. Nuclear Safety & Licensing)

- .Tom Orlando (Director of Engineering)

- Pat Conroy (Director Nuclear Safety Assurance)

- Ed Weinkam (Senior Manager Licensing)

- Bob Walpole (Manager Licensing)

- Tom McCaffrey (Manager Design Engineering)

- Joe De Francesco (Project Manager)

- Richard Drake (Supervisor Design Engineering)

- Floyd Gumble (Supervisor Reactor Engineering)

- Roger Waters (Licensing)

- John Skonieczny (Project Engineer)

- Dave Smith (Certified Health Physicist)

Project Goals

1. Transfer Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the Independent Spent Fuel Storage Installation (ISFSI)

2. Restore Full Core Offload Capability for IP3

3. Reduce Spent Fuel Pool Inventory for IP3

Meeting Objectives Ensure a common understanding between Entergy and NRC of:

• Fuel Transfer Operations

• Licensing Approach

• Schedule

Agenda

• Need for Project

• Project Description

• Overview of Spent Fuel Transfer Project

• Fuel Transfer Operation

• Transfer Schedule

• Licensing Summary

- Submittals

- Request For Additional Information (RAI's)

• Path Forward

• Closing and Q&A

Project Description

• Qbtain License Amendment approvals

• Perform Site modifications

• Fabricate equipment to support the transfer of spent fuel from the Unit 3 Spent Fuel Pool to the Unit 2 Spent Fuel Pool

• Transfer Unit 3 Spent Fuel from Unit 2 to the ISFSI

Fuel Transfer Operation

• Position HI-TRAC containing empty STC in Unit 3 Fuel Storage Building (FSB)

• Move Shielded Transfer canister (STC) into Unit 3 spent fuel pool

• Fuel loading, lid installation

• Remove STC from pool and place in Transfer Cask (HI-TRAC)

• Install STC lid bolting

• Perform leak testing of STC lid to shell area

• Perform STC Pressure Rise Test

• Perform leak testing of STC lid Vent & Drain ports

• Install H 1-TRAC solid Top Lid

• Perform pressure test of HI-TRAC sealing surfaces

• Using Air Pads, Move Hi-TRAC outside Unit 3 FSB .

• HI-TRAC moved with Vertical Cask Transporter (VCT)

• Move HI-TRAC/STC into Unit 2 FSB with existing Low Profile Transporter (LPT)

• Remove HI-TRAC Top Lid

• Using Unit 2 Gantry Crane lift STC and place in spent fuel pool cask handling area

• Remove STC Lid and move fuel to Unit 2 racks

• Dry cask and transfer Unit 3 fuel from Unit 2 to the ISFSI

Fuel Transfer Sequence A HI-TRAC CONTAINING AN EMPTY SHIELDED TRANSFER CANISTER IS POSITIONED IN THE IP-3 CASK RECEIVING BAY HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

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THE HI-TRAC TOP LID IS REMOVED AND THE SHIELDED TRANSFER CANISTER LID NUTS ARE REMOVED HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS REMOVED FROM HI-TRAC HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

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Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS LOWERED INTO THE CASK LOADING AREA OF THE SPENT FUEL POOL HOlTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cant.)

THE SHIELDED TRANSFER CANISTER LID IS REMOVED HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

SPENT FUEL ASSEMBLIES ARE LOADED INTO THE SHIELDED TRANSFER CANISTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS FULLY LOADED WITH SPENT FUEL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER LID IS INSTALLED UNDERWATER HOlTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS RAISED TO THE TOP OF THE SPENT FUEL POOL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS REMOVED FROM THE SPENT FUEL POOL AND PLACED DIRECTLY IN HI-TRAC HOlTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE SHIELDED TRANSFER CANISTER IS FULLY SEATED IN HI-TRAC, THE LID NUTS ARE TIGHTENED AND TESTING PERORMED PRIOR TO TRANSFER TO UNIT 2 HOlTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

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THE HI-TRAC TOP LID IS INSTALLED, THE BOLTS ARE TIGHTENED AND HI-TRAC INTEGRITY TESTING PERFOMED PRIOR TO TRANSFER TO UNIT 2 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

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HI-TRAC IS MOVED FROM THE IP-3 FSB TRUCK BAY AREA TO THE AWAITING VERTICAL CASK TRANSPORTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL

Fuel Transfer Sequence (Cont.)

THE VERTICAL CASK TRANSPORTER LIFTS THE HI-TRAC FROM THE AIR-PADS AND MOVES IT TO IP-2 HOlTEC INTERNATIONAL COPYRIGHTED MATERIAL

Project Overview

- Relocate Protected Area (PA) Fence to support fuel transfer inside PA at all times. - COMPLETED February 2011.

- 40 ton Crane Upgrade to single-failure-proof COMPLETED December 2010

- Facility and Transport Path Modifications 60% COMPLETE

- Spent Fuel Transfer - To include the following:

• Training

• Procedures

• Dry Runs

2012 2013 2014 Training Procedures Dry Runs

Licensing Summary

• License Amendment Request (LAR) History

-Public meetings/telecoms held:

-March 6, 2009

-June 15, 2009

-June 11, 2010

-Submitted July 08, 2009, supplemented September 28, 2009

- 1st round RAls:

-received April 20, 2010

-responses submitted October 5, 2010

- 2nd round RAls:

-received March 16, 2011

-responses due May 15, 2011

Summary of RAI's Round 1 RAI -100 total Operating General ProcedureslTS Inform ation (4)

(9) Principal Design Criteria (4)

Materials Evaluation (11)

--Criticality (33)

Shielding Design (19)

Structural Thermal Evaluation (7) Hydraulics (13)

Summary of RAI's (cont.)

ROUND 1 Progress General Information Fully integrated response - revised licensing report Principal Design Criteria Tip-over analysis performed, FMEA, tornado missile Criticality NRC approved Part 71 methodology adopted for STC I

Thermal Hydraulics Operational changes to address detection of fuel misload - STC steam void, STC pressure rise LCO and SR I I

Structural Provided justifications and clarifications Shielding Design and Isolation zone adjacent to HI-TRAC haul path, Non I ALARA Fuel Hardware analyzed Materials Evaluation, etc STC use of ASME Code III NO I Operating ProcedureslTech. NRC Control of CoC type information via Specs Appendix C to the Technical Specifications.

Captures both accident based and non accident based specifications

Summary of RAI's Round 2 RAI - 73 total General Information (2) Principal Operating Design Criteria Procedures/TS (0)

(21 ) Criticality (18)

Materials Thermal Evaluation (4) Hydraulics (10)

Shielding Structural Design (17) Evaluation (1)

Summary of RAI's (cont.)

ROUND 2 Progress General Information Fully integrated response - revised licensing report Principal Design Criteria -

Criticality Justifications and clarifications provided for model assumptions and benchmarking Thermal Hydraulics Justification of thermal model and properties Severe thermal misload analyzed Structural Further justification of tipover analysis Shielding Design and ALARA Estimated doses reduced/ Model justifications I Credit for a "Leak Tight" confinement boundary Requested analyses performed to address Neutron Source Assemblies, Cobalt, Tipover I

STC lid design change to address streaming Materials Evaluation, etc STC qualifies as a "Leak Tight" confinement boundary /ASME Code NC/ND reconciliation I Operating ProcedureslTech. New TS proposed to isolate public/haul path Specs New TS proposed to limit dose rates

Summary of RAI's (cont.)

ROUND 2 Resolution Challenges General Information Per Thermal Hydraulics and TS below Principal Design Criteria -

Criticality Some of the proposed RAI responses require further technical resolution Thermal Hydraulics Predicted hourly STC pressure rise Validation of no air in the vapor space Structural -

Shielding Design and -

ALARA Materials Evaluation, etc STC ASME Code NO Operating Procedures/Tech. TS based on hourly STC pressure rise Specs Adoption of a surface contamination LCO

Path Forward

• Entergy to develop and submit RAI responses by 5/15/11

• Entergy to provide continued support for RAI review process

• Continued Entergy / NRC Interface is essential

Closing Statements In order to meet Entergy's goals of:

1. Transferring Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the ISFSI

2. Restoring Full Core Offload Capability

3. Reducing Spent Fuel Pool inventory The following items need to be accomplished:

• Continued Entergy/NRC Technical Review Interactions to Ensure Resolution of All outstanding Issues

• Continued Entergy/NRC Management Engagement at all levels to monitor progress and facilitate resolution of

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-2 No Public Meeting Feedback forms have been received. Please direct any inquiries to me at 301-415-2901, or by email toJohn.Boska@nrc.gov.

/RAJ John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosures:

1. List of Attendees

2. Licensee Slides cc w/encls: Distribution via Listserv DISTRIBUTION:

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