ML16162A403

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Summary of 821130 Meeting W/Util Re Use of Mark Bz Fuel Assemblies in Future Reload Cores.Viewgraphs Encl
ML16162A403
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 12/01/1982
From: Wagner P
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8212100355
Download: ML16162A403 (54)
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Text

REc RGUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 1, 1982 Dockets Nos. 50-269/270/287 LICENSEE:

Duke Power Company FACILITY: Oconee Nuclear Station Units 1, 2 and 3

SUBJECT:

MINUTES OF MEETING HELD WITH DUKE POWER COMPANY ON NOVEMBER 30, 1982 A meeting was held on November 30, 1982, at Duke Power Company's request, to discuss the use of Mark BZ fuel assemblies in future Oconee Nuclear Station reload cores. Duke requested the meeting to obtain NRC feedback on what types of information would be required to approve the use of Mark BZ fuel assemblies. A list of attendees is enclosed (Enclosure 1); a copy of the slide presentation is also enclosed (Enclosure 2).

B&W personnel presented the design description and performance evaluations which have been performed on the Mark BZ design.

SMUD personnel were also in attendance since usage of the Mark BZ design is scheduled for the Rancho Seco facility earlier than that planned for Oconee.

The Mark BZ fuel assembly is essentially identical to the approved Mark B fuel assembly, except for the intermediate spacer grids.

Both assemblies utilize the 15 x 15, zircaloy clad fuel rods, zircaloy guide tubes, stainless steel end fittings, and six intermediate spacer grids. The spacer grids are Inconel 718 on Mark B assemblies and Zircaloy-4 on Mark BZ assemblies. There are also some design changes to the BZ grids.

The licensees plan to use the Mark BZ assemblies for improved Uranimum utilization to improved economy with lower axial peaking and also ease of fuel handling.

The licensees expressed the following needs from NRC:

1. Agreement on their overall approach,
2. Identification of concerns which need to be addressed,
3. Approval of the Mark BZ design by September 1983 to support manufacture of fuel for Rancho Seco Cycle 7 restart, and
4. Approval of BWC Critical Heat Flux correlation for Mark BZ assemblies.

PDR ADOCK 05000269 P

PDR OFFICEk SURNAMEfr................................

DATE)..................................

NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960

Oconee 1,2,3

-2 Members of the staff indicated that there should be little technical difficulty with our review, however, scheduling the necessary man power may be limiting. A number of subjects which should be included in the licensee's report were discussed and an advance copy was requested for an overview to ensure completeness prior to formal submittal.

Original tit" Philip C. Wagner, Project Manager Operating Reactors Branch #4 Division of Licensing

Enclosures:

1. List of Attendees
2. Slide Presentation ORB#4:DL OFFAMICE............. _...........

DATE NRC FORM 318 (10-80) NRCM 0240 OFF ICIAL RECORD COPY USGPOs 1981-733-960

ORB#4:DL MEETING

SUMMARY

DISTRIBUTION Licensee: Duke Power Company

  • Copies also sent to those people on service (cc) list for subject plant(s).

Docket File NRC PDR L PDR ORB#4 Rdg GLainas JStolz Project Manager-PWagner Licensing Assistant-RIngram OELD Heltemes, AEOD IE SShowe (PWR-) or CThayer (BWR), IE Meeting Summary File-ORB#4 MFraley, ACRS-10 Program Support Branch.

ORAB, Rm. 542 Meeting Participants Fm. NRC:

GSchwenk MDunenfeld RMeyer CBerlinger SMiner LIST OF ATTENDEES NOVEMBER 30, 1982 MEETING DUKE POWER COMPANY Name Organization P. C. Wagner NRC/Project Manager R. L. Gill DPC/Licensing W. D. Reckley DPC/Reactor Safety R. G. Snipes DPC/Fuel Cycle Operations R. J. Walker B&W/Fuel Services E. J. McGuinn B&W/Fuel Engineer L. L. Losh B&W/Fuel Engineering C. F. McPhatter B&W/Fuel Engineering M. R. Oren

.SMUD C. E. Barksdale B&W R. V. DeMars B&W J. B. Andrews B&W R. Powers SMUD G. A. Schwenk NRC/CPB M. Dunenfeld NRC/CPS R: Meyer NRC/CPB Fuels C. H. Berlinger NRC/CPB Zircaloy Intermediate Spacer Grid Design and Licensing Review November 30, 1982 Duke Power Company Sacramento Municipal Utility District Babcock & Wilcox Nuclear Regulatory Commission

Requested NRC Actions

  • Agreement with overall approach
  • Identification of any additional technical information required
  • Approval of BZ design by September 1983
  • Approval of BWC CHF correlation for BZ fuel

.**g Meeting Objectives Present synopsis of development history Present design description and verification of the BZ fuel Present operating performance evaluation of the BZ fuel Demonstrate acceptability of BZ for full batch implementation Concurrence on scope of submittal

  • Agreement on review and implementation schedule

Agenda For Mark BZ Review Meeting Introduction C.F. McPhatter Mark BZ Design Description, and Verification E.J. McGuinn Mark BZ Operating Performance Evaluation L.1. Losh Summary C.F. McPhatter

Introduction Development History Schedule Benefits

Design Phase Program Start Late 1976 Prototype Desigrr Mid 1978 Initial Presentation to NRC Dec. 1978 Licensing Report May 1979 Flow Testing Mid 1979 Life & Wear Test Feb. 1980 Lead Demo Licensing Report Feb. 1980

Verification Phase Lead Demo - Oconee 2 June 1980 Critical Heat Flux Test Dec. 1980 Demo Licensing Report March 1981 Demo Assemblies - Oconee 1 Dec. 1981 First Cycle Post Irradiation Exam Dec. 1981

Implementation Phase.

Mark-BZ Portion of Rancho Apr. 1983 Seco Reload Report NRC Approval of Mark BZ Sept. 1983 Production Zircaloy Grids Dec. 1983 Fabrication Mark BZ Assembly Fabrication Dec. 1983 Rancho Seco Cycle 7 Apr. 1984 Reload Report Fuel Delivery June 1984 Rancho Seco Cycle 7 Startup Sept. 1984

MK-BZ Benefits Improved Uranium Utilization More Economical Lower Axial Peaking Improved Handling Characteristics

MK-BZ Fuel Assembly MK-BZ Design Description

-Standard MK-B fuel assembly design

- MK-BZ spacer grid

- Material properties

-Zircaloy-4 grid design MK-BZ Verification Program

- Key performance factors

- Relaxation (fretting)

- Corrosion

-Structural integrity

- Local flow parameters

- Handling characteristics

- Operating experience

  • ANDARD MK-B FUEL ASSEMBq Upper End k p Fitting End Cap UPPER END GRID Fuel Pellet Spacer a r Grid INSTRUMENT TUBE SPACER SLEEVE Guide Tube ACTIVE CORE REGION Lower End f

/L LOWER END GRID Fitting

MK-B Spacer Grid Design FUEL RODS HARD STOP SOFT STOK REMOVABLE KEY

MK-BZ Spacer Grids MK-BZ Grid Design.- Functionally unchanged from MK-B

- Material properties

-Zircaloy-4 vs. Inconel 718

- Design configuration

- Increased grid height by 33%

- Improved outside strip design

- Lead - in tabs

- Increased internal strip thickness

- Reinforced center grid cell MK-B MK-BZ 0

0 00P7 00

Spacer Grid Material Properties MK-B MK-BZ Inconel-718 Zircaloy-4 Ni - 52%

Zr - 98%

Typical Chemical Cr - 20%

Sn - 1.5%

Composition Fe - 18%

Fe -

.2%

Nb - 3%

Cr -

.1%

Mo - 3%

Ni -

.05%

Cross Section 3.6 Barns

.2 Barns Condition Age Hardened Alpha Annealed Elongation 38% (Annealed) 14%

Elastic Modulus 29x106 psi (70*F) 14x106 psi (70* F) 26x106 psi (650*F) 11x106 psi (6500F)

Yield Stress 163 ksi (70F) 35 ksi (700F) 141 ksi (650*F) 15 ksi (650*F)

Tensile Strength 200 ksi (700*F) 60 ksi (700*F) 195 ksi (650*)

31 ksi (650F)

MK-BZ Fuel Assembly The MK-BZ fuel assembly design achieves improved uranium utilization by replacing the six intermediate spacer grids with grids fabricated from Zircaloy-4 material vs. Inconel 718 for the MK-B

- Basic fuel assembly design unchanged

- Fuel handling equipment interfaces unchanged

-Control rod interfaces unchanged

-Spacer grids are functionally unchanged

MK-BZ Verification Program Structural Evaluation Fretting wear (relaxation)

Life & wear test Grid corrosion Life & wear test Structural integrity LOCA & seismic evaluation Grid crush test Handling characteristics F.A. handling test Operating Experience Oconee - 2 Lead BZ demo assembly Oconee - 1 Four BZ demo assemblies

MK-BZ Life & Wear Test Test environment simulates reactor conditions Full size prototype fuel assembly

- Zircaloy grid

- Relaxed cells

-Loose rods (oversized cells)

- Std. upper and lower end grid 2

2 2

P2 12 2

2 P2 A

21 2

2 3

1 3

3 3

3 S Oversize cells at 2or 6 grid locations

BZ Life & Wear Test Synopsis Inspections at 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> 1000 hours 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />

- Fuel rod/grid interface Zircaloy grids Standard cells---1296 sites Oversized cells--1876 sites Inconel end grids Normal cells.---1056 sites Total 4228 sites Results

- No significant wear (.001 inch)

- No indication of progressive wear

- No evidence of high amplitude fuel rod vibration

==

Conclusion:==

- Spacer grid relaxation does not adversely effect the MK-BZ fuel assembly performance

MK-BZ Fuel Assembly MK-BZ Zircaloy - 4 Spacer Grid

-Corrosion resistance factors

- Oxidation during manufacturing

-Surface contamination

- Evaluation

-Autoclave testing (development)

- Life and wear test Results

- MK-BZ Zircaloy - 4 grid did not exhibit any significant corrosion in a reactor environment

MK-BZ Fuel Assembly The structural. integrity of the MK-BZ fuel assembly design was verified for seismic and LOCA events:

- Standard methods as described in topical report BAW-10133

- Generic analysis applicable to all operating skirt support plants

-Both all BZ and mixed core configurations investigated

MK-BZ Fuel Assembly Structural Evaluation Grid Impact Acceptance Margin Loading Criterion Case OBE Elastic (Operational Load 50%

basis earthquake)

Limit LOCA +

Coolable Seismic (SSE)

Geometry 75%

MK-BZ Fuel Assembly The shipping analysis verified the structural integrity of the MK-BZ spacer grids

- Evaluation of spacer grid for clamping load

- Crush test of zircaloy spacer grid

- Margin= 150%

Handling Test Configurations BZ BZ BZ BZ Simulated conditions:

Fuel assembly bow Handling bridge misalignment (4 inch)

The MK-BZ grids refused to 'Hang Up' under any of the simulated conditions

MK-BZ Fuel Assembly Operating Experience Oconee - 2 Lead BZ Assembly June 1980 to Dec. 1981 14000 MWd/MtU, 400 EFPD PIE completed Discharged PIE (Post Irradiation Examination) Results Visual No evidence of fretting, or corrosion Grids structurally sound Minor abnormality on one grid Grid position Top 5 intermediate grids moved to limits of constraints Grid width growth As expected ~.003" Fuel rod bow Same or better than MK-B

50 45 Fuel Rod Bow 40 35

_0 W4-B.Nd o W-BZ ai 30

-B 25 20 15 10 20 30 40 BURNLP (GWd/mtU)

MK-BZ Fuel Assembly Operating Experience Oconee - 1 0

Four BZ assemblies Startup Dec. 1981 Three cycles PIE. after each cycle

- Five extended Startup mid-1983 burnup assemblies (1)

- one cycle (4) - three cycles PIE after each cycle

MK-BZ Assembly

-Achieved a fuel assembly design with high structural integrity, good corrosion resistance, and improved handling characteristics Design has been verified through an extensive test program and incore demonstrations MK-BZ fuel assembly design is acceptable for full batch implementation

MK-BZ Fuel Assembly Thermal Hydraulic Evaluation

  • Minor change to core/fuel assembly o Evaluation supported by testing and analysis
  • Implementation will have minor impact on operation

MK-BZ Thermal Hydraulic Analysis

  • Hydraulic effects
  • Flow distribution
  • Core A P
  • increased zirc
  • Impact on operating limits

MK-BZ Flow Testing Full bundle prototype Operating temperature & pressure Measure component AP's Grid loss coefficient increase 10%

Core AP increase LDV testing -subchannel loss coefficients

UNatE suppcer PeArs

_*_I ofaicAlo tw"ak votacrTVr l4fttL P~?mIAI momes.

SB RR TIO4 G;AP:

Y, FI R

2 FIUR 2.1 1E'eT ESRMN OAIN

Fluid Velocity Profile 1.40 1.20 Inc 1.00

.60

.40 1

2 3

4 5

6 Pin#

  • e MK-BZ Critical Heat Flux Testing
  • ARC heat transfer facility 10 MW 12 ft/5x5 test section Acoustic temperature
  • Three MK-BZ tests Unit Guide tube Intersection
  • Correlation with BWC
  • Design limit

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MARK RZ DATA WITH RWC 12 acM

+C.

+

L&J 0.4000 CALCULATEDl CHF, 105 BTUAH-FT 2

Mark BZ Data With The BWC Correlation No. Of Bundle(s)

Type Points Mean Std. Dev.

B16

  • Matrix 70

.985

.083 B15 Guide Tube 44

.971

.072 B17 Intersection 97

.976

.057 All 211

.978

.070

DESIGN LIMIT ANALYSIS Determine Protection Criteria There w ill be 95 percent confidence that 95 percent of those pins ca culated to be at the DNBR design limit will not experience CHF.

Compute the Correlation Statistics Compute the mean measured to predicted CHF (M/P) and the associated standard deviation (a).

Calculate the DNBR Dfeign Limit Using one sided tolerance lihit theory, DNBR(L)

=

M/P K

Ko where K is a' function of the confidence level, the population protected, and the number of data points.

BWC Correlation Limit For MK-BZ Mean M/P

.978 Std. Dev. a

.070 Points, n 211 K (95/95) 1.83 Design Minimum DNBR

-1.18-

MK-BZ Fuel Assembly Lift Based on. flow testing Maximum at lower temperature Holddown requirement Increase -

50 lb.

MK-BZ Core DNB Analysis BWC correlation 1.18 correlation design Minimum DNBR Steady state DNBR Transient (limiting) DNBR RPS limits - minimal impact

MK-BZ Fuel Assembly RPS Limits DNB - Insignificant Impact

  • Improvement in

- Four pump coastdown DNB

- Flux/flow setpoint

  • Decrease in

- P/T limits (~ 2 0F)

  • Change in allowable peaking

-1.6% to +3.5%

RPS LIMITS 2400 K - 13 Z 2300 P-T TRIP eNVELoPE 2200 2U 2000 1900 590 600 610 620 630

.640 OUTLET TEMPEATURE, OF

MK-BZ ECCS Evaluation Increased core AP Increased Zirc in core H2 production Impact on operating limits

K-BZ Fuel Assembly ECCS Evaluation Core AP

  • Increase of only 3%

(17.8 psi to 18.4 psi)

  • Insignificant impact

MK-BZ Fuel Assembly

  • Eccs Evaluation Metal/water reaction
  • Additional Zirc
  • Grid at fuel rod temperature MK-B MK-BZ Limit Local 6.2%

12.4%

17%

Whole core

.58%

.65%

1%

MK-BZ Fuel Assembly ECCS Evaluation MK-BZ/BWC Impact

  • No impact @ 2 ft, 4 ft
  • Increase in Tclad @ 6 ft & above
  • Reduction in LOCA limit

@.6 ft elevation only 18 kw/ft - 17 kw/ft

  • Available margin

@8ftand 10ft T(clad) increase of 10OF

  • LOCA limits maintained 8 ft - 17 kw/ft 10 ft - 16 kw/ft

MK-BZ Fuel Assembly Operating Limits Reduction in 6 ft LOCA limit 18 kw/ft - 17 kw/ft insignificant impact on rod insertion limits

MK-BZ Fuel Assembly Thermal Hydraulic Evaluation

-Conclusion Implementation will have minor impact on operation

Summary Improved Uranium Utilization More economical Lower axial peaking Handling characteristics are improved Mechanical design is acceptable Thermal hydraulic design is acceptable Impact on safety and operating limits is small

Conclusions Zirc grid is a small change to a proven fuel design All safety issues have been addressed The information presented today supports full batch implementation

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