ML032340703

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Slides of Meeting Between NRC, Framatome and Crystal River on Mark-B-HTP Design
ML032340703
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/03/2002
From: Martin L
Progress Energy Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML032340703 (18)
v • d • e


Text

L. A. Martin October 3, 2002

,Nuclear IGeneration Group eot Progress Energy

Attendees I Progress Energy P Sherry Bernhoft Superintendent, Systems Engineering P Sid Powell Supervisor, Licensing and Regulatory Programs P Michael Donovan Supervisor, Reactor Systems i Leo Martin Supervisor, PWR Fuel Engineering

  • Framatome-ANP P Jerry Holm Manager, Product Licensing P Richard Harne Team Leader, Thermal Hydraulic Technology O Progress Energy 2

Purpose

  • Present need for Mark-B-HTP (High Thermal Performance) Design
  • Describe Design
  • Identify NRC Support Necessary
  • Communicate Requested Schedule

@? Progress Energy d, % 3

Background/History

. Leaking Fuel at CR3 P CR3 has experienced recurring fuel failures each cycle throughout its 25 year operating history P Actions to date have not been adequate to address long-standing fuel performance problems

  • Root Cause Investigation Performed P Inadequate stabilization of the fuel rod by the grid to prevent fuel rod vibration
  • Corrective Action to Prevent Reoccurrence P Implement HTP spacer design at earliest opportunity sJ

@Progress Energy 4

Background/History (Continued)

U~~~~~~~~~~~~~~~~~~~~~~~~~~~~-----

If Timeline P Mark-B10 to Mark-B12 transition planned (early Summer 2002) for Cycle 14 implementation (Fall 2003)

  • Mark-B12 utilized at Davis Besse and TMI-1 P Chief Nuclear Officer challenge to address CR3 failures (Summer 2002) i Aggressive schedule set for Mark-B-HTP introduction for Cycle 14
  • Plan developed (late Summer 2002)

+ Parts being fabricated

  • Flow testing (Spring 2003)

P Additional NRC reviews are required a21 Progress Energy dQ-0% 5

Mlark-B-HTP Design Description e Mark-B-HTP is based on Mark-B1 2 with:

P Seven zircaloy HTP grids

  • 8 full length line contacts versus 6 stops (2 soft + 4 hard)
  • Slanted flow channels improve mixing P One inconel HMP (High Mechanical Performance) grid
  • At bottom of assembly

+ Straight flow channels P A FUELGUARD lower end fitting

  • Reduced flow turbulence
  • No "line of sight" design prevents debris entry
  • Debris resistance comparable to fine mesh TRAPPER dqG K2 Progress Energy 6

Fuel Design Comparison I Parameter Mark-B10 (Cycle 13) Mark-B-HTP (Cycle 14)

Cladding, end cap, guide All Zirc-4 M5 cladding and guide tube and instrument tube tubes material Zirc-4 end caps and instrument tubes Plenum Volume (in3) _

Clad ID 0.377" 0.380" Pellet OD 0.3700" 0.3735" Cladding Thickness 0.0265" 0.0250" Pellet Density %Theo 95 96 Active Fuel Length 140.7" 143.0" Bundle U Weight (KgU) 466 490 a Progress Energy do % 7

Fuel Design Comparison (Continued)

I, I.Vb.Wa....... .. l~~~~~~~~~~-

I Parameter Mark-B10 (Cycle 13) Mark-B-HTP (Cycle 14)

Bottom grid Inconel HMP (Inconel HTP)

Intermediate grids (6) Mark-BZ Zircaloy HTP Zircaloy Top grid Inconel HTP Zircaloy Fuel assembly structure Floating grids Welded grids Debris resistance Long lower end plug FUELGUARD

& Progress

~ Energy HAG 8

HTP /HMP Industry Experience I HTP grid experience P Over 3,483 HTP assemblies; zero grid fretting failures

  • H. B. Robinson: 8 cycles 15x1 5 HTP (409 assemblies)
  • Shearon Harris: 6 cycles 17x1 7 HTP (353 assemblies)

P Used in KWU 16x16 and 18x18, CE 14x14 and 15x15, W 17x1 7 and 15x1 5 fuel designs P Peak Exposure Achieved: 56 GWd/MTU e HMP (or Inconel HTP) grid experience e Used in 503 assemblies; zero grid fretting failures P Used in CE 14x14 (276 assemblies), CE 15x15 (171 assemblies), W 17x1 7 leads (24 assemblies), and KWU 16X1 6 and 18X1 8 leads (32 assemblies)

Volt Progress Energy 9

FUELGUARD Industry Experience I FUELGUARD experience P 3,409 PWR and 1,818 BWR assemblies P H. B. Robinson: 6 cycles FUELGUARD (313 assemblies) e Shearon Harris: 6 cycles FUELGUARD (353 assemblies)

P Brunswick: 4 leads in second cycle P Zero PWR debris failures (industry wide)

P 2 BWR debris failures (industry wide)

. Debris entry from top of bundle suspected P Peak Exposure Achieved: 56 GWd/MTU 0 Progress Energy 10

NRC Reviews Required I Assemblies,"

Change to Technical Specification 4.2.1, "Fuel and M5 Exemption Request P Schedule

  • Submit LAR 276 October 25, 2002 (LAR 276 also contains changes to T.S. 4.2.2, "Control Rods," unrelated to Mark-B112 implementation)
  • Request Approval August 2003
  • Technical Specification changes required to implement Mark-B-HTP P SL 2.1.1.2 - LYNXT based HTP DNB correlation limit P Figure 2.1.1-1 RCS DNB safety limit (potential)

P Schedule

  • Submit December 2002
  • Update (if required) May 2003
  • Request Approval August 2003

&421s Progress Energy g~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 11

NRC Reviews Required (Continued)

I Revision to EMF-92-153, "HTP: Departure From Nucleate Boiling Correlation For High Thermal Performance Fuel"

  • Incorporate results of LYNXT evaluation of HTP CHF database
  • Schedule
  • Submit December 2002
  • Request Approval August 2003 Progress Energy M.% 12

NRC Reviews Req u ired (Continued)

I .Revision to BAW-1 0179, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses" P Reference revised EMF-92-1 53 P Reference BAW-1 0164, R4, "RELAP5/MOD2-B&W, An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analyses"

  • Approved 04/02 for use in BWNT LOCA EM (BAW-1 0192) o Schedule
  • Submit December 2002
  • Request Approval August 2003 a Progress Energy 13

Summary I Mark-B-HTP design addresses root cause of fuel failures

  • Design features have proven in-reactor experience
  • Implementation requires NRC review and approval of several minor revisions to LTRs and Technical Specifications
  • Schedule provides adequate time for required reviews Progress Energy 14

Backups I

W$ Progress Energy d.qy 15

115x15 Fuel Design Comparison HZ B. Robinson / Crystal River -3 i

Parameter Robinson Crystal River-3 Fuel Rod Diameter, in 0.424 0.430 Fuel Rod Pitch, in 0.563 0.568 Grid Envelope, in 8.436 (HTP) 8.536 Axial Grid Span, in 20.55 21.09 (typical) dq.% IA Progress Energy 16

Technical Specification 4.2.1 Change and M5 Exemption Request I Changes Assemblies" to Technical Specification 4.2.1, Fuel o Adopt NUREG-1 430, Rev. 2, "Standard Technical Specifications - Babcock and Wilcox Plants" wording P Add M5 cladding material

Changes to BAWV l 01 79 (additional detail)

I Reference LYNXT based HTP correlation topical report

  • Reference BAW-1 0164, R4; RELAP5/MOD2-B&W; Approved 04/02 for use in LOCA EM
  • Clarify that BAW-1 0192 (BWNT LOCA EM topical report) will be used with BAW-1 0164 R4
  • Clarify that the LOCA EM will use the appropriate DNB correlation for the HTP spacer as required by the Approved EM (Notification as required by 10CFR 50.46)
  • Incorporate previously approved changes Progress Energy 18
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