ML13011A338

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Slides Re Meeting with Tennessee Valley Authority Regarding Bellefonte Nuclear Plant, Unit 1, Fuel and Safety Analyses Methodologies
ML13011A338
Person / Time
Site: Bellefonte Tennessee Valley Authority icon.png
Issue date: 12/10/2012
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
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ML13011A250 List:
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Download: ML13011A338 (17)


Text

[i!lJ NRC Meeting - Bellefonte Methodology - FSAR Chapters 4 and 15 December 10, 2012 NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15

um Bellefonte Path Forward Project Licensing Risk Reduction QVP Review and Approval Regulatory Framework Agreement q

FSAR Development Plan Agreement Project Licensing Work Enablers Chapter 3 Civil I&C System Design Criteria Architecture and Review and 03 Strategy Approval Agreement NRC Meeting December 10, 2012 - Bellefonte Methods Chapter4 and 15 1

Ii!a]

Objective

  • Provide overview of methods to be used for Bellefonte fuel design and safety analyses
  • Discuss submittal schedule and process for NRC acceptance of methods NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 2

1m]

Introduction - Technical Methodology Reports

  • Plant Specific Reports
  • Purpose of Technical Methodology Reports To gain early NRC acceptance of the methodology to be used for the analyses presented in Chapters 4 and 15 of the Bellefonte FSAR To avoid the need for the development of a modified methodology late in the FSAR review process and to avoid the need for a significant re-analyses late in the FSAR review schedule To provide a place for details required for regulatory review by the NRC but which are more detailed than the standard content of an FSAR and which may be proprietary NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 3

~ List of Technical Reports for Bellefonte - FSAR Chapter 4 and 15

  • Codes and Methods Applicability
  • Fuel Assembly Mechanical Design
  • Setpoints
  • Non-LOCA Events
  • Bellefonte Safety Criteria and Reload Analyses 4

NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15

mJ Codes and Methods Applicability

  • Purpose

- This report will provide a justification of the applicability of the current topical reports which are intended to be used to support the Bellefonte FSAR Chapter 4 analyses with no modifications or only minor modifications. It is desirable to obtain NRC feedback as to the acceptability of the methodology early in the process (and in particular for any modifications).

  • List of NRC Approved Topical Reports

- BAW-10025PA (reactor vessel flow tests)

- BAW-10084PA (CROV, creep collapse evaluation)

- BAW-10147PA (rod bow)

- BAW-10156PA (LYNXT the fuel assembly thermal-hydraulic code)

NRC Meeting December 10,2012 - Bellefonte Methods Chapter4 and 15 5

rmJ Codes and Methods Applicability

  • List of NRC Approved Topical Reports (continued)

- BAW-I0170PA (statistical core design)

- BAW-I0180PA (NEMO) (core physics parameters)

- BAW-I0183PA (fuel rod internal pressure criteria)

- BAW-I0186PA (extended burnup evaluation)

- BAW-I0199PA (BWU CHF correlation)

- BAW-I0221PA (NEMO-K) (kinetics)

- BAW-I0227PA (MS cladding)

- BAW-I0241PA (BHTP CHF correlation)

- BAW-I0243PA (statistical hold down)

- BAW-2149PA (replacement rods)

- ANP-89-0060PA and EMF-93-074PA (fuel assembly design)

NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 6

[I!lJ Control Rod Eiection

  • Purpose

- This report is required to demonstrate compliance with Appendix B to Section 4.2 of the 2007 version of the Standard Review Plan (revised control rod ejection criteria)

- A methodology exists that has been reviewed and approved by the NRC on a plant specific basis to-date.

¢ U.S. EPR

¢ Crystal River (B&W)

  • The report will include a sample problem for Bellefonte that will also form the basis of Section 15.4.8 of the FSAR NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 7

[I!

Fuel Assembly Mechanical Desiqn

  • Purpose

- This report will describe in detail the fuel rod and assembly mechanical design for Bellefonte

- The level of detail will be significantly greater than in the FSAR and will contain a significant amount of proprietary material

  • The material in this report will form the basis for portions of Section 4.2 of the FSAR
  • Fuel is a TVA focus area and thus early interaction is beneficial NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 8

ml Setpoints

  • Purpose

- This report is a replacement for the topical report BAW-l0121PA which describes the techniques and procedures used to establish safety limits and setpoints for the reactor protection system

- The level of detail will be greater larger than in the FSAR and will contain a significant amount of proprietary material

- A digital hardware protection system will be used for Bellefonte in place of the original analog reactor protection system and thus a new setpoint methodology is required NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 9

lIm Non-LOCA Events

  • Purpose

- The report will address the applicability of B&W non-LOCA methodology to the Bellefonte plant and to describe and justify modifications to address current NRC identified issues.

¢ BAW-10193PA (non-LOCA methodology)

  • Modifications

- Parameter biases

- Cycle exposure for analyses

- Power levels for analyses

- IEOTSG steam generator benchmarks (open item in BAW-10193PA)

NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 10

~ LOCA

  • Purpose

- The report will address the applicability of the B&W LOCA methodology to Bellefonte and will address changes to the LOCA methodology o BAW-l0192PA Revision 0 (LOCA methodology)

  • Modifications

- To address thermal conductivity degradation with burnup (GALl LEO)

- Long term cooling

- Changes since BAW-10192PA Revision 0 NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 11

[ml Bellefonte Safety Criteria and Reload Analyses

  • Purpose

- The purpose of this report is to describe the reload analyses methodology and to support the use of a Core Operating Limits Report in association with the Technical Specifications

  • Background

- Generic Letter 88-16 (Removal of Cycle Specific Parameter Limits from Technical Specifications)

- BAW-10179PA was developed for the B&W owners group for B&W 177 fuel assembly plants

- A similar report is planned for Bellefonte NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 12

List of New AREVA Topical Reports to mil be Referenced for Bellefonte

  • GALILEO
  • PWR fuel assembly mechanical accident analysis methodology (seismic & LOCA)

NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 13

Submittal Schedule for Technical rml Reports for Bellefonte

  • Codes and Methods Applicability December 2013
  • Non-LOCA Events December 2014
  • Setpoints 2015
  • Fuel Assembly Mechanical Design 2017
  • Safety Criteria and Reload Analyses 2017 NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 14

um Technical Report Specific NRC Interaction

  • Each report should have the following interactions

- A pre-submittal meeting nominally a year or more in advance of submittal to obtain feedback from the NRC on the content of the report

- A pre-submittal meeting about three months in advance of submittal to reaffirm the input originally received from the NRC on the content of the report

- A post-submittal meeting about a month after the report submittal

- Interactions with the NRC during review process

  • NRC feedback on plant specific technical reports

- Technical meetings

- RAIs

- Safety Eva Iuation Report NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 15

lim Proposed Pre-submittal Meetinqs - 2013

  • Codes and Methods Applicability

- February 2013

- May 2013

  • Non-LOCA

- August 2013

- October 2013 NRC Meeting December 10, 2012 - Bellefonte Methods Chapter 4 and 15 16