ML072010174

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Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate
ML072010174
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/23/2007
From:
TXU Generation Co, LP
To:
Office of Nuclear Reactor Regulation
Thadani, M C, NRR/DORL/LP4, 415-1476
Shared Package
ML072050495 List:
References
Download: ML072010174 (11)
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Text

Enclosure 2 Comanche Peak SES Transition to Westinghouse Safety Analysis Methodologies

/ TXU Power May 23, 2007

5/22/2007 CPSES Stretch Power Uprate 4TXU Power Purpose of meeting is to inform the NRC of our plans & schedule to facilitate resource allocation by the NRC CPSES Stretch Power Uprate

  • OeTXU W*P"Power Meeting Agenda
  • Project team
  • Project objectives, milestones & overview

" Plant modifications

" Testing

" Submittal format

" Active & planned licensing submittals

" Summary and Q&A 2

5/22/2007 Methodology Transition Project - What and 0?%TXU Why? W ?Power Prior to 2006:

  • TXU Power's Core Design & Safety Analysis organizations performed FSAR Chapter 4, 6, 7 and 15 analyses in-house, using vendor-independent methods May of 2006:

" TXU Power transferred in-house Core Design & Safety Analysis and Risk

& Reliability functions to Westinghouse Electric Co.

" Teaming arrangement developed, where Westinghouse performs these functions in the best interests of Comanche Peak

" Agreement includes application of latest NRC-approved Westinghouse analysis methodologies' Allows power uprates, longer cycles, more efficient core designs, newer technologies for more efficient plant operation Agenda IVh TXU Power

" Purpose of today's discussions

" Overview of the Accident Analysis Methodology Transition Project

.° Specifics of Technical Specification Changes

  • Generic, enabling changes

. Submitted for NRC review April 10, 2007 Conforming changes

. Submitted for NRC review April 10, 2007

  • Cycle Specific Applications
  • To be submitted upon completion of analyses

. Licensing Action Submittal Schedules

  • Concluding discussions 3

5/22/2007 Project Objectives ISTXUPower

" Increase Rated Thermal Power from 3458 to 3612 MWt (-4.5%)

  • increase plant output

- Unit 1 49 MWe

- Unit 2 37 MWe

  • Design and operating margin will be protected to assure continued safe and reliable plant operation

- Modifications

- Analyses Project Milestones A v* PTXU Power

  • August 2007 - LAR submittal to NRC (Units 1 & 2)

" Fall 2008 Outage - Unit I uprate implementation

- Fall 2009 Outage - Unit 2 uprate implementation NRC approval of proposed Uprate LAR requested to support the Fail 2008 Unit I outage 4

5/22/2007 Methodology Transition Project Overview 4Vt TXU Power

-All adopted Westinghouse methodologies have been previously approved by the NRC on a generic basis for application at plants such as Comanche Peak Required'Tech Spec Changes - enabling eto TXU changes

  • Tech Spec 5.6.5b, "Core Operating Limits"

-List of Methodologies used to establish Core Operating Limits expanded to include standard Westinghouse Methodologies

" WCAP-1 1397-P-A, "Revised Thermal Design Procedure," April 1989.

" WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986.

- Applicable to Comanche Peak's N-1 6-based OT/OP system

" WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999.

  • WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System," August 1994.

5

5/22/2007 NSSS Analyses - continued AVhTXU Power

" Component Evaluations

  • System Evaluations
  • Safety analyses include:

- LOCA M&E / containment

- SLB M&E I containment

- Spent fuel pool criticality

- Non-LOCA analyses

- LB BELOCA w/ASTRUM (1)

- SBLOCA (1)

(1)Addressed in Transition to Westinghouse Methodologies NSSS Uprate Modifications

  • TXU S Power Nuclear Steam Supply System (NSSS)

NSSS Control System changes

- Steam Dump Control System

- Rod Control System

- SG Level Control System

- Pressurizer Water Level Control System 6

5/22/2007 Required Tech Spec Changes - conforming e& TXU changes Power

,BEACON-TSM

" Replace the phrase "moveable incore detectors" to "core power distribution measurement information"

" Replace the phrase 'flux map" to "power distribution measurements"

  • Affects:

- TS.3.1.7, "Rod Position Indication"

- TS 3.2.1, "Heat Flux Hot Channel Factor"

- TS 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor"

- TS 3.2.4, "Quadrant Power Tilt Ratio"

- TS 3.3.1, "Reactor Trip System (RTS) Instrumentation."

Required Tech Spec Changes - cycle-specific 41 TXU Power applications

-Tech Spec changes identified as cycle-specific analyses are completed

-Cycle-specific analyses are performed to bound operation at current Rated Thermal Power as well as planned uprated power

  • Current Rated Thermal Power = 3458 MWth
  • Planned Rated Thermal Power = 3612 MWth
  • Permission to operate at uprated power is NOT part of this project 7

5/22/2007 Power Ascension Testing 4 TXU Power

- Plant transient testing under evaluation

- NSSS & BOP systems - monitoring during uprate power ascension

- Flow-induced vibration monitoring of the following systems

- Main Steam, Feedwater (outside of containment)

- Condensate I Heater Drains

- Extraction Steam

" Post-Modification Testing, including

- Heater Drain pump I system

- Isophase bus duct cooling

  • Turbine Thermal Performance Testing Submittal Format & Content 4TXU Power
  • RS-001 EPU standard used to facilitate NRC review
  • Recent NRC RAIs addressed
  • Current licensing basis summarized

5/22/2007 Schedules TXU Power Mid-April 2008 First application of Westinghouse methodologies to Unit 2 Cycle 11 NRC Approval Requested 2/15/08 Supporting Milestones:

April 2007 Submitted Enabling & Conforming Tech Spec changes July 2007 Submit SBLOCA & ASTRUM Evaluation Models September 2007 Submit cycle-specific Tech Spec changes required to support methodology transition RTS & ESFAS Allowable Values affected functions only Pressurizer. Safety Valve set pressure and as-found tolerance General Discussion 4ATXUPower Any Comments or Questions?

9

5/22/2007 Summary Aft TXU Power

°CPSES SPU will result in -4.5% increase in RTP

-Dedicated, experienced project team

-Similar approach to other recent Westinghouse 4 loop SPU projects

-Design and operating margin will be protected to assure continued safe and reliable plant operation

  • RS-001 EPU standard used to facilitate NRC review Summary A TXU Power Project Milestones

-August 2007 - LAR submittal to NRC (Units 1 & 2)

-Fall 2008 Outage - Unit I uprate implementation

-Fall 2009 Outage - Unit 2 uprate implementation NRC approval of proposed UprateLAR requested to support the Fall 2008 Unit I outage Questions?

10

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