ML090770625
| ML090770625 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/26/2009 |
| From: | Boska J Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC ME0408, TAC ME0409 | |
| Download: ML090770625 (37) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mrrch 26, xm LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit NO.3
SUBJECT:
TELECON WITH ENTERGY ON MARCH 6, 2009, ON TRANSFERRING UNIT 3 SPENT FUEL TO THE UNIT 2 SPENT FUEL POOL (TAC NOS. ME0408 AND ME0409)
On March 6,2009, a telephone call was held between the Nuclear Regulatory Commission
(!\\IRC) and representatives of Entergy Nuclear Operations, Inc. (Entergy or the licensee). The purpose of the call was to discuss the licensee's plans to submit license amendment applications for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) which would request NRC approval for the transfer of spent fuel from the IP3 spent fuel pool to the IP2 spent fuel pool. Entergy plans to submit the license amendment applications in July 2009.
The reason for the transfer of spent fuel is that Entergy is developing a method to transfer IP3 spent fuel into dry cask storage, at the Independent Spent Fuel Storage Installation (ISFSI),
which already exists onsite. The capacity of the crane in the IP3 fuel storage building (FSB) is insufficient to lift the transfer cask which is currently used by Entergy as part of the dry cask storage system. Entergy previously replaced the crane in the IP2 FSB in order to transfer IP2 spent fuel into dry cask storage. Entergy stated it was more cost effective to transfer the IP3 fuel to the IP2 spent fuel pool and use the new IP2 crane, than to replace the crane in the IP3 FSB.
Holtec is designing a new transfer cask for use at IP3 which is within the 40-ton capacity of the current IP3 crane. The new transfer cask will be placed inside the Holtec Hi-Trac transfer cask and transported across the site from the IP3 FSB to the IP2 FSB using the cask transporter.
Entergy will be requesting to license the new cask and the transfer process under Title 10 of the Code of Federal Regulations, Part 50. See Enclosure 1 for a list of the participants on the call, and Enclosure 2 for the handout provided by Entergy.
Please direct any inquiries to me at 301-415-2901.
O ~
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 Handout cc w/encls: Distribution via Listserv
List of Attendees:
NRC J. Boska J. Commiskey J. Goshen S.Jones S. McCarver R. Nimitz M. Rahimi D. Roberts J. Schmidt K. Wood Entergy A. Stewart J. Defrancesco J. Skonieczny F. Gumble B. Gutherman Holtec K. Phy K. Cummings T. Morin
c:
~-.....
,...~
WQ.
~ Ai*
'a::::l z
~-a:-a
~,... 2. n AI"'~ m ri c,.....,
- T tD c:n-mtD
-I~~
N o..,tD~
om.., ~
\\0 ~ ~
(I' < 0
~n~
tD tD
~
-a,...
.., tD o.......,
tD n,...
Introductions
- Nuclear Regulatory Commission
- Entergy - Indian Point Energy Center Joe Defrancesco (Project Manager)
Ann Stewart (Licensing)
Brian Gutherman (Licensing Consultant)
John Skonieczny (Project Engineer)
Floyd Gumble (Reactor Engineering)
- Holtec International Ken Phy (Project Manager)
Kris Cummings (Nuclear Engineering Manager)
Tammy Morin (Licensing Manager) 2
Goals and Objectives Ensure a common understanding between Entergy and NRC of:
- Project need, alternatives evaluated, and basis for decision
- Fuel Transfer Operations
- Licensing Approach
- Schedule 3
Agenda
- Project Decision and Summary
- Project Roles and Responsibilities
- Project Schedule
- Unit 3 Crane Upgrade
- Integrated Fuel Management
- Equipment Operation
- Equipment Design
- Summary of Analysis Work
- Licensing Approach
- Closing and Q&A 4
Project Decision
- Unit 2/3 Fuel Inventory
- Background
- Upgrade crane from 40 to 100-tons not feasible
- Unit 2 type Gantry Crane not feasible for Unit 3
- Greater elevation +23'
- Existing plant system interferences
- Project Scope
- 40 ton Crane Upgrade to single-failure-proof
- Facility Mods and Transport Path Upgrades
- Spent Fuel Transfer 5
Project Status
- Milestone Schedule developed
- Evaluating Crane vendor proposals
- Preliminary transfer canister design complete
- Licensing plan developed 6
Project Schedule
- Transfer Canister Design Complete Apr2009
- Submit LAR to NRC Jul2009
- Crane Design & Fabrication Complete Apr2010
- NRC Issues Amendment Jul2010
- Crane Installation Complete Sep2010
- Pre-Operational Testing Oct2010
- Transfer 96 Assemblies Complete Dec2010
- Load 3 Casks from U2 2011 7
Roles and Responsibilities
- Entergy
- Project ownership and oversight
- Review and accept Holtec deliverables
- Process and submit LAR to NRC
- Interface with NRC
- Holtec
- Turnkey project
- Transfer Canister (TC) design and fabrication
- HI-TRAC modifications and Ancillary Equipment
- Unit 3 crane upgrade
- Prepare analyses supporting fuel transfer
- Develop LAR package 8
Integrated Fuel Management
- Unit 2 Preparation and Inventory
- Unit 3 Inventory
- Unit 2 versus Unit 3 Fuel Design &
Operation
- Unit 2 Tech Spec Compliance
- Unit 2 Thermal Loading
- Special Nuclear Material Control 9
Terms and Definitions
- FSB is the Indian Point Fuel Storage Building
- TC is the Holtec designed Transfer Canister
- HI-TRAC 1000 is the licensed transfer cask part of the HI-STORM
- VCT is the Vertical Cask Transporter
- LPT is a Low Profile Transporter that uses Hilman rollers or Air Pallet System 10
Unit 3 Crane Upgrade
- Whiting Bridge &Trolley Crane
- Maintaining 40-ton capacity
- Replace trolley with single-failure proof design
- Reevaluate building loads
- NUREG 0554 and ASME NOG-1-2004
- Implement under 50.59 11
HI-STORM 100 Cask System MULTI=PURPOSE CANISTER LOADED WEIGHT: 42 TONS (US)
HEIGHT: 17 FEET DIAMETER: 6 FEET HI-STORM OVERPACK LOADED WEIGHT: 180 TONS (US)
HEIGHT: 19 FEET DIAMETER: 11 FEET HI-TRAC TRANSFER CASK LOADED WEIGHT: 100 TONS (US)
HEIGHT: 17 FEET DIAMETER: 7-J FEET 12
VCTand LPT MPC UPENDING CRADLE CASK CRAWLER LENGTH: 19 FEET WIDTH:
LOW PROFILE TRANSPORTER 12 FEET LOADED WEIGHT: 182 TONS (US)
WIDTH: 8 FEET MATING DEVICE LENGTH: 20 FEET 10-~ FEET LOADED WEIGHT 27.000 LBS HI-TRAC UPENDING CRADLE LENGTH 20 FEET WIDTH: 9 FEET LENGTH: 25 FEET WIDTH: 18-j FEET LOADED WEIGHT 262 TONS (US)
LENGTH WIDTH: 13 FEET 13
Equipment Operation
- Move TC into Unit 3 spent fuel pool
- Fuel loading, lid installation
- Remove TC from pool and place in HI-TRAC lOaD
- Remove water for air space and install lid bolting
- Using Air Pallets Move outside Unit 3 FSB
- Transport Operations: HI-TRAC moved with VCT
- Move TC into Unit 2 FSB with existing LPT
- Use Unit 2 Gantry Crane lift TC and place in spent fuel pool cask handling area
- Remove TC Lid and move fuel to Unit 2 racks 14
f-C 1
r
\\
HI-TRAC Transfer Cask Design
- Using Unit 2 existing HI-TRAC 1000
- New solid Top Lid with relief valves
- Lid closure bolting with elastomer seal
- Maintenance requirements - per Part 72 FSAR and calibration RVs
- Codes and standards
- ASME B&PV Code Section III, Subsection NF
Transfer Canister Design
- Approximate Dimensions - 52" diameter x 183" high
- Lifting attachments - Trunnions for Lift Yoke
- Handling weight - < 40-tons with rigging
- TC fuel capacity - 12 fuel assemblies
- Fuel basket design - Stainless Steel with Metamic
- Lid closure design - bolted flat head with elastomer seaI
- Safety features - relief valves
- Maintenance requirements - calibration RVs, Trunnion inspections, general inspections
-I I>>
- s (ft til' n
I>>
- s _.
(ft r-I tD.,
r I>>
-< o C
r-I tv a
Summary of Analysis Work
- StructuraI
- Criticality
- Thermal
- Shielding
- Effluent Controls
- Postulated Events 21
TC &. HI-TRAC Structural Design
- Stress Limits per ASME B&PV Code Section III Subsection NF and ANSI N14.6
- Lifting Points
- Internal Pressure
- 40-ton Max Weight (including lifting device)
- Stainless Steel Basket with Metamic
- Fuel Assembly Drop on Basket
- End Drop of HI-TRAC with Loaded TC
- Postulated Events Evaluated 22
TC Criticality Design
- Same methodology as used for spent fuel pool rack criticality analyses, 10 CFR 50.68, boron credited only for accidents
- CASMO-4 for differential reactivity effects and isotopic inventory of spent fuel
- MCNP for l<eff calculations of the Transfer Canister
- Depletion Parameters and Axial Burnup Distribution chosen to bound Unit 3 fuel assemblies 23
TC Criticality Design (cant)
- Core Depletion Parameters to bound all cycles from Unit 3 operation.
- Maximum l<eff < 0.95 for normal and accident conditions.
- Credit for soluble boron to offset accidents
- Consideration for misloaded fresh fuel assembly in center of basket 24
TC Thermal Design
- Fuel Integrity (SFST ISG-ll, Rev. 3)
- Transport Evaluation, Cladding Temperature Limit of 752°F (400°C) (normal) Design Basis Decay Heat Load
- Cask Components
- All components must remain below their design temperature limits.
- Cask Decay Heat - 9 kW in a regionalized configuration.
- Four inner cells with higher allowable decay heat than eight outer cells
- Boundary integrity will be maintained by ensuring the internal pressure is lower than the pressure limit.
25
TC Thermal Design (cant)
- Methodology USNRC Approved three-dimensional quarter-symmetric model in FLUENT.
The thermal solution employs all modes of heat transfer within the cask cavity - convection, conduction and radiation.
- Heat transfer from the surface of the cask to the ambient is via natural convection and radiation.
- Ambient Environment Conditions Outside Temperature: 100°F (38°C) (10CFR71)
FSB Temperature: 120°F Incident insolation: 10CFR71 specified 12-hr caloric inputs
- Equilibrium Temperature lower than Saturation Temperature, no time limits 26
TC Shielding Design
- Steel-Lead-Steel Construction with Metamic Basket
- Source term based on Unit 3 Fuel inventory
- Three-dimensional continuous energy Monte Carlo code MCNPS
- Regionalized Loading Burnup of 45 GWd/MTU and 20 Years Cooling Time in Outer Region
- 55 GWd/MTU Fuel Burnup with 10 Years Cooling Time in Inner Region
- Dose Rate ALARA 27
TC Effluent Control
- Transferring Intact Fuel
- Transfer Canister Seal
- TC filled with pool water
- HI-TRAC Top and Bottom Lid Seal
- HI-TRAC filled with Demin Water
- No release based on postulated events 28
TC Postulated Events
- Natural Events
- Seismic
- Tornado
- Flood
- Environmental; wind, rain, snow, temperature
- Fire and Explosion
- End Drop during VeT Lifting
- Fuel Drop on Basket 29
Licensing Approach
- Reviewed Fuel Transfer within scope of Parts 72 and 71
- Not an ISFSI-related activity - Part 72 does not apply
- Part 71 applies if the licensee (10 CFR 71.0(c)):
Delivers the material to a carrier for transport Transports the material outside the site of usage specified in the license Transports the material on a public highway
- Part 71 does not apply
- Part 50 applies Transfer Cask is a Part 72-licensed component Transfer Canister - Uniquely-designed component for this project
- Part 72 acceptance criteria used where none exist in Part 50 30
Licensing Approach (cant)
- St. Lucie Precedent as starting point
- Similarities
- Differences
- Lessons learned
- Spent Fuel Storage and Handling under Part 50
- Meeting 10CFRSO, Appendix A
- Criterion 61 and 62
- Use approved Part 72 analysis for HI-TRAC Operations, where applicable 31
Licensing Approach (cant)
- IPEC Unit 2/3 Current Licensing Basis Reviewed
- Proposed Changes
- Unit 2 Operating License
- Add Unit 2/3 TS 3.7.X for TC Burnup versus Enrichment Curves
- Add Unit 2/3 TS 4.X for Design Features of the TC
- Unit 2/3 UFSAR Changes for TC loading pattern, decay heat limits, and transport program
- Supporting analysis work as needed 32
Licensing Approach (cant)
- Fuel Assembly Design Westinghouse 15x15 both units
- Spent Fuel Pool Design Unit 3 fuel meets Unit 2 burnup and enrichment curves
- Spent Fuel Transfer Loaded TC remains under Crane limit Basket design maintains fuel in subcritical configuration
- Analysis provided to justify the design (criticality, shielding, structural, thermal)
- Heavy Load Path Evaluation Cask drop not credible
- Transport haul path upgraded as necessary
- Environmental Considerations No changes to type or total amount effluents 33
Closing Statements
- Transfer Canister Design 80%
- LAR Development 60% Complete
- Requesting one year turnaround to support project schedule
- Future NRC Interactions
- Pre-submittal conference call
- Monthly status conference calls 34
w V1
March 26, 2009 LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
TELECON WITH ENTERGY ON MARCH 6, 2009, ON TRANSFERRING UNIT 3 SPENT FUEL TO THE UNIT 2 SPENT FUEL POOL (TAC NOS. ME0408 AND ME0409)
On March 6, 2009, a telephone call was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (Entergy or the licensee). The purpose of the call was to discuss the licensee's plans to submit license amendment applications for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) which would request NRC approval for the transfer of spent fuel from the IP3 spent fuel pool to the IP2 spent fuel pool. Entergy plans to submit the license amendment applications in July 2009.
The reason for the transfer of spent fuel is that Entergy is developing a method to transfer IP3 spent fuel into dry cask storage, at the Independent Spent Fuel Storage Installation (ISFSI),
which already exists onsite. The capacity of the crane in the IP3 fuel storage building (FSB) is insufficient to lift the transfer cask which is currently used by Entergy as part of the dry cask storage system. Entergy previously replaced the crane in the IP2 FSB in order to transfer IP2 spent fuel into dry cask storage. Entergy stated it was more cost effective to transfer the IP3 fuel to the IP2 spent fuel pool and use the new IP2 crane, than to replace the crane in the IP3 FSB.
Holtec is designing a new transfer cask for use at IP3 which is within the 40-ton capacity of the current IP3 crane. The new transfer cask will be placed inside the Holtec Hi-Trac transfer cask and transported across the site from the IP3 FSB to the IP2 FSB using the cask transporter.
Entergy will be requesting to license the new cask and the transfer process under Title 10 of the Code of Federal Regulations, Part 50. See Enclosure 1 for a list of the participants on the call, and Enclosure 2 for the handout provided by Entergy.
Please direct any inquiries to me at 301-415-2901.
IRA!
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 Handout cc w/encls: Distribution via Listserv DISTRIBUTION:
See next page Memo: ML090770625 OFFICE LPL 1-1/PM LPL1-2/LA LPL 1-1/BC NAME JBoska ABaxter MKowal DATE 3/26/09 3/25/09 3/26/09 Official Record Copy
DATED: M3rch 26, xrn SUB.IECT:
TELECON WITH ENTERGY ON MARCH 6, 2009, ON TRANSFERRING UNIT 3 SPENT FUEL TO THE UNIT 2 SPENT FUEL POOL (TAC NOS. ME0408 AND ME0409)
PUBLIC LPL1-1 R/F RidsNrrDorlLpl1-1 RidsNrrPM.IBoska RidsNrrLASLittle RidsOGCRp RidsAcrsAcnw_MailCTR RidsRgn1 MailCenter JGoshen, NMSS cc w/encls: Distribution via Listserv