ML032340703
| ML032340703 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/03/2002 |
| From: | Martin L Progress Energy Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032340703 (18) | |
Text
L. A. Martin October 3, 2002
, Nuclear I Generation 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 d, %
@? Progress Energy 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 1 4
- Plan developed (late Summer 2002)
+ Parts being fabricated
- Flow testing (Spring 2003)
P Additional NRC reviews are required dQ-0 a21 Progress Energy 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 do %
a Progress Energy 7
Fuel Design Comparison (Continued)
I, I.V b.W a.......
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 HAG
~ Progress Energy 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 1 7x1 7 and 1 5x1 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 1 7x1 7 leads (24 assemblies), and KWU 1 6X1 6 and 1 8X1 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 Change to Technical Specification 4.2.1, "Fuel Assemblies," 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 M. %
Progress Energy 12
NRC Reviews Req u i red (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
d.qy
W$ Progress Energy 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 to Technical Specification 4.2.1, Fuel Assemblies" o Adopt NUREG-1 430, Rev. 2, "Standard Technical Specifications - Babcock and Wilcox Plants" wording P Add M5 cladding material Exemption Request to allow use of M5 Cladding i
10 CFR 50.46, "Acceptance criteria for emergency core cooling systems of light-water nuclear power reactors" o 10 CFR 50.44, "Standards for combustible gas control system in light-water-cooled power reactors" f
o 10 CFR 50, Appendix K, "ECCS Evaluation Models" yG eProgress Energy 17
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 1 OCFR 50.46)
Incorporate previously approved changes Progress Energy 18