ML021510026

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Meeting Handouts from 05/30/2002 Meeting on Status of Fuel Performance, Control Rod Replacement, & Implementation of Approved Cents Code, at Palo Verde Nuclear Generating Station, Units 1, 2, & 3
ML021510026
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 05/30/2002
From: Donohew J
NRC/NRR/DLPM/LPD4
To:
References
Download: ML021510026 (15)


Text

NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9- 1999)

TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed)by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attachedcopy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.

Do not include proprietarymaterials.

DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 05/30/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:

Docket Number(s) 50-528, 50-529, and 50-530 Plant/Facility Name Palo Verde Nuclear Generating Station, Units 1, 2, and 3 TAG Number(s) (if available)

Reference Meeting Notice Meeting Notice dated May 2, 2002 Purpose of Meeting (copy from meeting notice) The licensee will provide the NRC staff with the status of fuel performance, control rod replacement, and imple mentation of the approved CENTS Code, at the units.

NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Jack Donohew Senior Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licensing Project Management BRANCH Project Directorate IV Distribution of this form and attachments:

Docket File/Central File PUBLIC NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using InForms

Nuclear Fuel Update Palo Verde Nuclear Generating Station May 30, 2002 Meeting with US NRC Review of 2001

  • March 2001 Meeting with NRR

+ Approval of new MDNBR Limit

  • Progress with Clad Performance
  • Alloy A LFA Approved For 4 th Burn
  • CENTS Code Added to COLR
  • Begin Transition to Westinghouse Rod
  • Zirlo Tech Spec Submitted I

Agenda Today

  • Review of Unit 2 Cycle 11

+ CENTS Implementation & Licensing

  • Integrated Clad Performance Strategy
  1. Update on CEA Investigation

+ Dry Cask Storage Update Unit 2 Cycle 11 Activities Incorporated in the Reload Safety Analyses 2

U2CK 1 Reload Analyses

+ Implementation of New MDNBR Limit

  • Manufacturing Transition to Columbia

+ Implementation of Zirlo Clad & New LOCA Methodology

  1. Implementation of New CENTS AORs CENTS System Code Implementation & Licensing

CENTS Impiementation Plan

+ All UFSAR Chapter 15 Analyses

+ Two Events Remain In Progress

- Steam Generator Tube Rupture

- CEA Ejection Dose Consequences Steam Generator Tube Rupture

  1. Consequences Increase > Minimal
  • Principal Contributors

- Timing of Aux FW & ADV opening

- New Limiting SG Level

  1. Retain Current CESEC AOR Until CENTS Analysis Reviewed & Approved
  • Consistent With RSG/PUR Submittal

CEA Ejection Dose Consequences

  • Evaluating CENTS Applicability
  • Will Submit if Required
  • Retain Current CESEC AOR Until CENTS Implemented
  • Will Not Impact RSG/PUR Submittal Palo Verde Integrated Clad Performance Strategy Review of Recent Capabilities U2 Uprate Corrosion Strategy 10

Integrated Fuel Clad Strateg~y

  • Advanced Clad Alloys

+ Primary System Chemistry

  • Higher Order Modeling
  • Low Duty Core Designs 11 A Advanced Clad Alloys
  • Full Batch Zirlo starting U2C1 1 (Spring 2002)
  • Alloy A LTA in U3C10 (Spring 2003)
  • Continuing Discussions with Westinghouse 12 6

Primary Chemistry

  • Additional RCS Cleaning at EOC Shutdown
  • Early Lithium Injection During Startups

+ Elevated-Coordinated Lithium Strategy

- Currently 7.1 pH

- Inspection Ul R1 0 (Fall 2002)

- Gradual Increase to > 7.2 pH 13 Higher Order Modeling

+ Uncertainty in Behaviors = Multiple Models

+ Steaming Rate Function in Design Tools

- U3C9 Benchmark

  • APS CRUD/Oxide Model

- Pin x Pin Colorset and Coarse Mesh Octant

  • Vendor Fuel Duty Model

- Oxide and FDI for all Clads 14 7

Low Duty Core Designs

  • Increase Feed Batch Size

- 104 vs 96 Assemblies

  • Minimal Feed-Face-Feed
  • U2 Uprate Corrosion Strategy

- 3% Power and 22 F Coolant Temperature

- Zirlo Clad

- Re-design Lattice Pattern 8

Palo Verde CEA ReplacemenR Update on CEA Investigation 17 Review of CEA Replacement

  • CEA Finger Failures Observed - all Units

- Significant Cracks in High Fluence CEAs

- Boron Loss in U1 Lead Group

- Some Medium Fluence CEA Cracking

- U2R8 CEA Found Cracked (Jan. 2002)

+ All Full Length CEAs Replaced

- Two Different Tip Designs

- Replaced by Design with Smallest Pellet 9

Apparent Cause of Failures

- Irradiation Sensitized Inconel

- Swelling-induced Strain

  1. Less than Adequate Design Testing

- Feltmetal Properties Unverified at High Duty

- Pellet-Feltmetal Interaction

+ Lifetime Predictive Software

- Models Not Fully Benchmarked 11)

Remaining Actions

+ Determine Conservative Estimate of Life

- 2 Cycle Fingers OK

- Possible YGN Inspections

- Possible Hot Cell Exams

- 2x1 021 n/cm 2 Threshold?

+ CEA re-Design for the Future 20 10

Palo Verde Dry Cask Storage Plan Overview 21 11

Project Schedule

  • Concrete Cask fab completed 3/31/02
  • First Canister delivery 6/28/02
  • ISFSI Construction complete 8/1.9/02
  • Security features installed 9115/02

+ Dry run practice begins 8/1/02

+ NRC dry run observations mid Noverr iber

  • First system on the pad by Christmas i I

Palo Verde Dry Cask Storage Principal Components (Cut-away View)

Transportable Storage Canister Dimensions:

Transfer cask Ht. 16 ft. 11 in.

Dia. 7 ft. 1 in.

Loaded canister Ht. 15 ft. 11 in.

Dia. 5 ft. 7 in.

vCC Ht. 18 ft. 10 in.

Dia. 11 ft. 4 in.

Weight:

Transfer cask 60 tons Loaded canister 35 tons vCC 119 tons Loaded system 154 tons