ML18037A827
| ML18037A827 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/14/1994 |
| From: | Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18037A825 | List: |
| References | |
| TVA-COLR-BF2C7, TVA-COLR-BF2C7-R02, TVA-COLR-BF2C7-R2, NUDOCS 9404120286 | |
| Download: ML18037A827 (32) | |
Text
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TvA-COLR-BF2C7 Revision 2, Page 1
QA REcoao Browns Ferry Nuclear Plant Vnit2, Cycle 7 CORE OPERATING LIMITSREPORT (COLR)
TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division
.BWR Fuel Engineering Department r
Prepared By:
Earl E. Riley, Nucl Engineer BWR Fuel Engineering Date:
> /9 0'9 Reviewed By:
Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Date:
3
/V Approved By:
T. A. Keys, nager BWR Fuel Engineering Da~e: 3-/V.->
940412028b 940404 PDR ADOCK 050002b0 P,
.PDR
TVANuclear Fuel Core Operating Limits Report t
TVA-COLR-BF2C7 Revision 2, Page 2 ReViSiOn I,Og
~Revi ion 0,
Date 4-5-93
~Descri tion Initial Release Affec ed Pa e
All 5-7-93 Incorporate Changes in MCPR Operating Limits,to Reflect Additional Analyses:as
,summarized in Revision 1 to the SRLR, reference 3.
revised pages 2, 4, 6, 14-16.
deleted page 17.
2 3-10-93 Add new references 7 and 8. Revise OLMCPR limits for (EOC7-'2150) to EOC7 exposure range revised pages 2, 3, 6, 14, and 15.
'TVANuclear Fuel Core Operating Limits Report t
TVA-COLR-BF2C7f Revision 2, Page 3
- 1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 7 is prepared in accordance with the requirements of Browns Ferry Technical Specification 6;9.1.7.
The core operating limits presented here were developed using NRC-approved methods (References 1 and 2).
Results from the reload analyses for Browns.Ferry Unit 2, Cycle 7 are documented in References 3 and 7.
I The cycle 7 loading includes, four. Westinghouse QUAD+,demonstration assemblies loaded in locations adjacent to.the, periphery. These locations satisfy the criteria specified in References 4 and 5. Evaluations performed by Westinghouse (Reference
- 5) show that the results of licensing analyses for the lead P8x8R fuel assembly bound those for the QUAD+ demonstration assemblies.
Cycle specific analyses, confirm this conclusion.
The following cycle-specific core operating limits are included in this. report.
a; Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3.5.1)
- b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.5.J) c.. Minimum Critical Power Ratio Operating Limit(OLMCPR)
(Technical Specification 3.5.K/4.5.K)
- 2. APLHGR LMIT(TECHNICALSPECIFICATION:3.5.1)
'The APLHGR limitfor each type of fuel as a function.of exposure is shown in Tables 1'-7. The APLHGR limits for the GE9B bundles (GE8X8NB) are for the most limiting lattice at each exposure point. The specific values for each lattice, are given in reference 6.
- 3. LHGR LMIT(TECHNICALSPECIFICATION'3.5.J)
The LHGR limitfor unit,2, cycle 7 is fuel type-dependent, as shown below:
~fuel t e
P8X8R/BP8X8R/QUAD+
GE8X8NB LHGR limit 13.4 kw/ft 14.4 kw/ft
0
TVA:Nuclear Fuel, Core Operating Limits Report t
TVA-COLR-BF2C7 Revision 2, Page 4 4..
OLMCPR (TECHNICALSPECIFICATION,3.5.K/4.5.K) whichever is greater The OLMCPR is equal to the fuel type and exposure dependent MCPR limit at rated flow and rated power shown in Figures.1-2 multiplied by the Kf shown in Figure 3, where; Save ZB
= 00 or Z~ = 0.90 sec (Specification 3.3.C. 1 scram time limitto 20%
insertion from fullywithdrawn )
l Sir = 0.710 + 1.65 (0.053)
N n
ng" 7,r.
Save n
where; n = Number ofsurveillance rod tests performed to date in cycle (including BOC test).
Zi = Scram time to 20% insertion from;fullywithdrawn ofthe i
fod N = Total number ofactive rods measured'in Specification 4.3.C.1 at BOC
TVANuclear Fuel Core Operating Limits Report t
TVA-COL'R-BF2C7 Revision 2, Page 5.
- b. For the performance of Surveillance Requirement 4.5.K.2.a (prior to initial scram time measurements for the. cycle),
'6 = 1.0
- c. For the performance, of Surveillance Requirement 4.5.K.2.b,
'6.shall be determined in accordance with 4.a above.
i5
TVANuclear Fuel Core Operating Limits Report t
TVA-COLR-BF2C7 Revision 2, Page 6
- 5. REFERENCES
- 1. NEDE-24011-P-A-IO,, "General Electric Standard Apphcation for Reactor Fuel",
February 1991.
- 2. NEDE-24011-P-A-10-US, "General Electric Standard Application for, Reactor Fuel", March 1991.
- 3. 23A7190; Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry.
Nuclear Plant Unit 2 Reload 6 Cycle 7," April 1993.
4.. Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No. 125 to Facility Operating License No. DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No. 50-260.
- 5. WCAP-10507 dated March 1984, "QUAD+ Demonstration Assembly Report,"
Westinghouse Electric Corportion.
- 6. 23A7190AA, Rev. 0, "Lattice-Dependent MAPLHGR Report for-Browns Ferry Nuclear Plant Unit 2 Reload 6 Cycle 7", January 1993.
- 7. Letter from G. D. Plotycia (GE) to T. L. Hayslett (TVA), "Transient Reanalyses Results for Browns Ferry, Nuclear Plant Unit 2, Cycle 7", GDP:94-062 dated March 3, 1994. [L38 940307 802]'.
Letter from G. D. Plotycia (GE) to T. L. Hayslett (TVA), "Transient Reanalyses Results - Additional Information", GDP:94-064 dated March 8, 1994. [L38
'940311 803]
TVANuclear Fuel Core Operating Limits Report I
TVA-COLR-BF2C7 Revision 2, Page 7 Table 1
APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (6E8X8NB)
Most LimitingLattice for Each Exposure Point Average Planar Exposure
{QWD~/T 0.0 0.2 1.0'.0 3.0 4'.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 45.0 50.'27 APLHGR Limit
~kw/f 10.97 11.00 11.11 11.31 11.54 11.79 11.97 12.10 12.23 12.35 12.46 12.58 12.58 12.35 11.86 11.33 10.12 8.60 5.92
0
TVANuclear Fuel Core. Operating. Limits Report TVA-COLR-'BF2C7
.Revision 2, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB)
Most Limiting Lattice for Each Exposure Point Average Planar Exposure
~GWD/ST 0.0 0.2 1.0 2.0'.0 4.0 5.0 6.0 7.0 8.0 9.0-10.0 12.5 15.0 20.0 25.0, 35.0 45.0 50.5 51.4 APLHGR Limit kw/ft 11.45 11.47 11.55 11.70 11.87'2.01 12.13 12.22 12.31 12.41 12.51 12.63 12.64 12.41 1-1.91 11.35 10.15 8.72 5.93 5.87
TVANuclear Fuel Core Operating-Limits Report TVA-COLR-BF2C7 Revision 2, Page 9 Table 3 APLHGR Limits for Bundle Type P8DRB301L (BP8X8R)
Average Planar Exposure Q(jwD/ST) 0.0 0.2 1.0 2.0 3.0 40 5.0 6.0 7.0 8.0 9.0
.10.0 12.5 15.0 20.0 25.0 35.0 43;5 APLHGR Limit
~kw/f 11.32 11.33 11.40 11.50 11.61 11.73 11.86 11.93 11.98 12.03 12.11 12.19 12.34 12.47 12.58 12.03 10.82 9.17
IS
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C7 Revision 2, Page 10 Table 4 APLHGR Limits for Bundle Type PSDRB299 (BP8X8R)
Average Planar Exposure
~WD/ST 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0
'25.0 35.0 42'.1 APLHGR Limit
~kw/f 10.71 10.75 10.86 11.01 11.19 11.35 11.47 11.62 11.78 11.95 12.09 12.20 12.37 12.47 12.37 11.77 10.65 9.36
TVA:Nuclear Fuel Core Operating Limit~seport i
'TVA-COLR-BF2C7 Revision 2, Page.11 Table 5 APLHGR Limits for Bundle Type PSDRB284L and Westinghouse QUAD+ LTAs (P8XSR)
Average Planar Exposure
~WD/ST 0.2 1.0 5.0 10;0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGR Limit
~kw/f 11.2 11.3 11
~ 8 12;0 12.0 11,8 11.2 10.8 10.2 9.5 8.8
IS Ik
TVA.Nuclear Fuel Core Operating Limits Report t
TVA-COLR-BF2C7 Revision 2, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284Z (P8X8R)
Average Planar Exposure 0.2 1.0.
5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45,0 APLHGR Limit
~kw/f 11.2 11.2 11.7 12.0 12.0 11.8
- 11. 1 10.4 9.8 9.1 8.5
TVANuclear Fuel Core Operating Limits Report i
TVA-COLR-BF2C7 Revision 2, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)
Average Planar Exposure
~W~D~T 0.2 1.0 5.0 10;0 15.0 20.0 25.0 30.0 35.0 40.0 APLHGR Limit
~kw/f 11.5 11.6 11.9 12.1 12.1 11.9 11.3 10.7 10.2 9.6
il
TVANuclear Fuel
'Core Operating Limit~seport TVA-COLR-BF2C7'evision 2,
Page 14 Figure 1
MCPR Operating Limitfor P8X8R/BP8X8R/QUAD+
1.36 1.35 1.'34 i
J 1.33
- (EOC7-2l 50) to EOC7 1.32
,CC 1.31 V~ 1.30 1.29-1.28 1'.27 BOC7 to (EOC7.2150) 1.26 0.0
'0.1 Option.B 0.2 0.3'.4 0.5 0.6 0.7 0.8 0.9 1.0 Option A
~EE*
BOC7 to (EOC7-'2150) MWD/ST (EOC7-2150) to EOC7 MWD/ST 0 tion A Tan=1.0 1.28
+
1.35
'~pi B T
=II.D 1.27 1.32
- 'Use this value at BOC7 prior to performing scram time testing.
il 0
TVANuclear Fuel Core Operating LimiNReport 1
TVA-COLR-BF2C7 Revision 2, Page 15 Figure 2 MCPR Operating. Limitfor, GE8X8NB 1.36 1.35 1.34 33 (EOC7-2150) to EOCl
~. 1.32 E
gg 1.31 U
1.30 I
It 1.29 1.28 to OC7-1.27 1.26 0.0 0.1
'0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Option'B Option A
~E*
R BOC7 to (EOC7-2150) MWD/ST
'(EOC7-2150) to EOC7 MWD/ST tion A Tau=1.0 1.30
- 1.35 tion B Tan=0.0 1.28
- 'Use this value at BOC7 prior to performing scram time testing.
l5 0
I
TVANuclear Fuel Core Operating Limits eport TVA-COLR-BF2C7 Revision 2, Page 16 (Final) 1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections Nona 1.3 117.0'%112.0
%'07.0 102;6 %
1.020 30 40 50 60 70 80 Total Core Flow (% rated) 90 100 For 40%%uo < WT ( 100%,
Kf = MAX[1.0, A-0.00441~WT]
WT ( 40%,
Kf = [A - 0.00441+WT] + [1.0 + 0.0032+(40- WT')]
WT ) 100%,
Kf =
1.0 where
WT =
Percent of Rated Core Flow, and A = constant which depends on the Flow Control Mode and the Scoop Tube Setpoint as noted'below.
MANUAL MANUAL MANUAL MANUAL AUTOMATIC 102.5 %
107.0
'%%uo 112.0 %
'117.0 %
N/A 1.3308 1.3528 1.3793 1.4035 1.4410.
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