ML042990515

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Presentation by Txu on 10/19/04 - Comanche Peak Steam Electric Station, Unit 1 - Steam Generator Replacement Project
ML042990515
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 10/19/2004
From:
TXU Electric
To: Thadani M
NRC/NRR/DLPM/LPD4
Thadani M, NRR/DLPM, 415-1476
References
Download: ML042990515 (27)
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Comanche Peak Steam Electric Station - Unit 1 Steam Generator Replacement Project Anticipated Licensing Actions fA#f hpr 711'0 r fli)iA

  • Introduce key personnel
  • Present SG Replacement Plans for CPSES-1
  • Provide scopes and schedules of anticipated licensing actions

SG Replacement Project Manager

  • Ben Mays
  • 254-897-6816
  • Safety Analysis Manager
  • Whee Choe
  • 214-812-4371 rmaysl @txu.com wchoel @txu.com
  • Engineering and Safety Analysis Point of Contact
  • James Boatwright jboatwright@txu.com
  • Consulting Nuclear Project Manager
  • 214-812-8232
  • Overview of Replacement SG Design Featu res
  • Expected Effects on Analytical Methodologies
  • Expected Changes to Technical Specifications
  • Other Licensing Actions
  • Part of two-unit site with shared control buildings
  • Originally rated at 3411 MWth, now at 3458 MWth with MUR uprate

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  • Similar to ?75 design in use at Shearon Harris and V.C. Summer

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Q TXU ENSA Equipos Nucleare. S.A.

RSG Design: Overview of Design Features Forged elliptical head with integral nozzle (eliminates nozzle weld)

Major nozzles with extra stock (aids installation)

Auxiliary fecdwater nozzle Inspection ports above each TSP (maintenance enhancement)

Four 6 - inch handholes Above tubesheet (maintenance enhancement)

Relocated main feedwater nozzle on upper shell

( Feedring RSG with simplified operation vs. OSG with preheater)

Forged transition cone with cylindrical upstands (eliminates ISI welds)

Forged shell barrels (minimizes ISI welds)

Support ring to match existing supports e

Primary nozzle with safe end extension (aids installation)

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0 TXU ENSA RSG Design: Overview of Design Features

  • Peerless single tier secondary separators (enhancement for reduced moisture carryover)
  • High capacity primary separators (enhancement for reduced moisture carryover)
  • Elevated feedring with Alloy 690 spray nozzles (mitigates stratification and water hammer; traps loose parts)
  • Enhanced materials throughout (high strength pressure boundary, Alloy 690 used, erosion resistant material in high velocity regions)

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  • Tubesheet secondary side tubelane free of obstructions (maintenance enhancement)

PRM Septembcr 2004 at ENSA Page 26 M::

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RSG Design: Overview of Design Features

, Enhanced tube bundle with thermally treated Alloy 690 tubing 5532 tubes with 0.75" OD and on ? pitch Increased heat transfer area (76000 sq ft)

Provides for reduced T-hot operation Provides margin for potential power uprate

  • Field proven minimum gap AVB system
  • Stainless steel broached tube support plates
  • Increased secondary side circulation ratio (mitigates sludge deposition on tubes, tube

~dryout, tube degradation mechanisms)

I* Enhanced tube to tubesheet joint B

@ Elevated feedring with top discharge nozzles

  • Nozzle holes sized to trap loose parts Hole diameter less than tube to tube clearance j I TOPDISCHARGE 4 i__PY i

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  • Relative to D-4 SG, the ?76 has:
  • 76,000 ft2 heat transfer area (vs. 48,000 ft2)
  • Essentially the same exterior envelope
  • 5532 U-tubes (vs. 4578)
  • 3/4" tube OD (same)
  • 1.03" triangular pitch (vs. 1.0625" square pitch)
  • Top of tube bundle 8 ft higher
  • Relative to D-4 SG, the ?76 has:
  • 5330 ft3Shell-side volume (vs. 5954 ft3)
  • Increased Tube Side Volume
  • Approximately 1300 ft3 additional RCS volume
  • 13% increase
  • Circulation Ratio of 4 (vs. ~2.4)
  • Slightly larger secondary fluid mass
  • 251" narrow range water leve

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  • Generically, design for a Tavg range of 589.20F -

574.2°F, but:

  • Limit Steam Pressure to 1000 psia
  • Initially, set full power Tavg - 5850F @ 3458 MWth
  • Raise Tavg toward 589.20F as SG heat transfer capability decreases (due to fouling or tube plugging)
  • Design to a much tighter Tavg range (e.g., +/-1OF) on cycle-specific basis

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Chapter 15 Analytical Methods:

  • Approved by NRC
  • (Core Operating Limits Report)

Primary Affected Transients and Accidents:

" FLB, LOAC, LOFW, MSLB

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  • SG Model Changes:
  • Approved CPSES SG model is coarse; includes explicit preheater representation; recirculation is not modeled
  • Chose to adopt feed ring SG model developed by

-.Westinghouse

  • Uses RETRAN-02
  • Benchmarked against plant data
  • Methodoloogy reviewed and approved by NRC
  • Feedline Break
  • Due to elevated feed ring, initial transient similar to steamline break
  • Detailed model with circulation requires use of dP model to simulate steam generator water level trip functions
  • vs. mass, as described in the CPSES topical

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  • Loss of non-emergency power to the station auxiliaries (Loss of AC power)
  • Different SG model - no methodology changes
  • Different SG model - no methodology changes
  • Main Steamline Break
  • Update existing simplified SG model with new dimensions; use existing methodology
  • SG tube rupture
  • No methodology effects
  • New SG model
  • New SG noding consistent with non-LOCA model
  • Small modification to reactor vessel upper plenum model
  • RXE-91-001-A, "Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", October 1993.
  • To be supplemented to address more detailed SG model, SG Water Level indication, and Feedwater Line Break response

e ERX-2000-002-P, "Revised Large Break Loss of Coolant Accident Analysis Methodology", March 2000.

  • RXE-95-001-P-A, "Small Break Loss of Coolant Accident Analysis Methodology," September 1996.
  • ERX-2001-005-P, "ZIRLOTM Cladding and Boron Coating Models for TXU Electrics Loss of Coolant Accident Analysis Methodologies", October 2001.
  • All to be supplemented (with a single supplement) to AdHimnS P

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TS Table 3.3.1-1 and TS Table 3.3.2-1 and associated Bases Tables:

  • SG Water Level - low-low and high-high

- Main Steamline Pressure - low

  • Allowable Values in the TS Tables
  • Nominal Trip Setpoints in the TS Bases Tables
  • Remove those allowances established for the Unit 1 SGs that are not applicable to the Unit 2 SGs
  • No new requirements anticipated specifically for the ?76 SGs

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  • Core Operating Limits Report (COLR)

TS 5.6.5

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  • General update of radiological dose consequences methodologies to be consistent with RG 1.195
  • Pending results of Engineering Analysis and ensuinglOCFR50.59 Evaluation
  • General reviews of methodologies used throughout the RSG project
  • Spring 2007 Install replacement SGs
  • February 2007
  • Spring 2006 a Winter 2006
  • Fall 2005 NRC approval of RSG-related licensing actions Submit any License Amendments identified through 10CFR50.59 Evaluations

-NRC Approval of Topical Report Supplements Submit Proposed TS changes

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  • Questions?
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