ML18038B396

Cycle 8,COLR.

ML18038B396
Person / Time
Site:	Browns Ferry
Issue date:	07/27/1995
From:	Bruce A, Keys T, Welch K TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038B394	List: ML18038B392 ML18038B396
References
TVA-COLR-BF2C8, TVA-COLR-BF2C8-R02, TVA-COLR-BF2C8-R2, NUDOCS 9508280353
Download: ML18038B396 (32)

Text

TVA Nuclear Fue TVA-COLR-BF2C8 Core Operating Linnts Report Revision 2, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 8 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date: 7 I'l 95 Kenneth L. Welch, Engineering Specialist BWR Fuel Engineering Verified By: Date: 7 2,I 9K Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Approved By:

T. A. Keys, M ager BWR Fuel Engineering Reviewed By: Date: Z5 Reactor Engineering isor Reviewed By: Date:

ORC Chairman 950828035K 950727 PDR ADOCK 05000260 P PDR

0 0 TVANuclear Fuel TVAKOLR-BF2CS Core Operating Limits Report Revision 2, Page 2 Revision Log R~eviai e Date ~DpiLi nn Affect Pa 0 10/6/94 Initial Release All 3/24/95 Change APRM flow biased rod block 5,6 setpoint; incorporate changes due to Tech Spec Amendment no. 232.

7/27/95 Revision to correct OLMCPR to agree 6, 14, 15 with GE re-analysis of FWCF using corrected value for vessel level instrumentation loop response time.

0 TVA Nuclear Fue TVAKOLR-BF2C8 Core Operating Limits Report Revision 2, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 8 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'nd 2). Results from the reload analyses for Browns Ferry Unit 2, Cycle 8 are documented in. Reference 3.

The cycle 8 loading includes four Westinghouse QUAD+ demonstration assemblies.

The locations of these assemblies 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 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)

d. APRM Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.l.c, Table 3.2'.C, and Specification 3.5.L)

e. RBM Upscale (Flow Bias) Trip Setting and Clipped Value (Technical Specification Table 3.2.C)

2. APLHGR LIMIT(TECHNICALSPECIFICATION 3.5.1)

The APLHGR limit for each type of fuel as a function of exposure is shown in Tables 1-7.'he 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.

ik TVA Nuclear Fue TVAKOLR-BF2CS Core Operating Limits Report Revision 2, Page 4

,3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5 J)

The LHGR limit for unit 2 cycle 8 is fuel type dependent, as shown below:

~Fu ~1T ~ LH R Li P8X8R/BPSXSR/QUAD+ 13.4 kw/ft GESX8NB 14.4 kw/ft 4.,OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K)

a. 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; Z =0.0'r Z Zaw ZB whichever is greater ZA ZB Zi = 0.90 sec (Specification 3.3.C.1 scram time limit to 20%

insertion from fully withdrawn )

i ZB = 0.710 + 1.65 N 2 (0.053) n n

g 'ti Save n

where; n = Number of surveillance rod tests performed to date in cycle (including BOC test).

Zi = Scram time to 20% insertion from fullywithdrawn of the i fod N = Total number of active rods measured in Specification 4.3.C.1 at BOC

b. For the performance of Surveillance Requirement 4.5.K.2.a (prior to initial scram time measurements for the cycle),

7' 1.0

0 TVA Nuclear Fuel TVAKOLR-BF2C8 Core Operating Limits Report Revision 2, Page 5

c. For the performance of Surveillance Requirement 4.5.K.2.b, 'C shall be determined in accordance with 4.a above.

S. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECBNICAL .

SPECIFICATION 2.1.A.l.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)

The APRM Rod Block trip setting shall be:

SRB 6 (0;58W + 57%)

where:

SRB = Rod Block setting in percent of rated thermal power (3293 MWt)

W = Loop recirculation flow rate in percent of rated Note: Under certain conditions, the APRM Rod Block setting must be adjusted by FRP/CMFLPD. See Technical Specification 3.5.L

6. RBM UPSCALE (FLOW BIAS) TRIP SETTING AND CLIPPED VALUE (TECHNICALSPECIFICATION TABLE 3.2.C)

The RBM Upscale trip setting shall be:

5 (0.66W + 43%)

where:

Trip level setting is in percent of rated thermal power (3293 MWt)

W = Loop recirculation. flow rate in percent of rated RBM upscale flow-biased setpoint clipped at 109 percent rated reactor power.

TVA Nuclear Fue TVAKOLR-BF2CS Core Operating Limits Report Revision 2, Page 6

'7. REFF~NCES

1. NEDE-24011-P-A-10, "General Electric Standard Application for Reactor Fuel",

February 1991.

2. NEDE-24011-P-A-10-US, "General Electric Standard Application for Reactor Fuel", March 1991.

3. 24A5153, Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," July 1995.

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 Corporation.

6..24A5153AA, Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.

7. Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No. 232 to Facility Operating License No. DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No. 50-260.

0 TVA Nuclear Fue TVA-COLR-BF2C8 Core Operating Limits Report Revision 2, Page 7 Table 1 APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8XSNB)

Most Limiting Lattice for Each Exposure Point Average Planar'Exposure APLHGR Limit

{QW~D/ T} kw/ft 0.0 11.64 0.2 11.68 1.0 11.77 2.0 11.88 3.0 12.01 4.0 12.12 5.0 12.22 6.0 12.32 7.0 12.49 8.0 .12.65 9.0 12.77 10.0 12.86 12.5 12.86

-15.0 12.62 20.0 12.06 25.0 11.47 35.0 10.41 45.0 8.81 51.20 5.91

TVA Nuclear Fue TVAKOLR-BF2C8 Core Operating Linuts Report Revision 2, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB)

Most Limiting Lattice for Each. Exposure Point Average Planar Exposure APLHGR Limit

{QWD~/ ~kw f 0.0 10.97 0.2 11.00 1.0 11. 11 2.0 11.31 3.0 11.54 40 11.79 5.0 11.97 6.0 12.10 7.0 12.23 8.0 12.35 9.0 12.46 10.0 12.58 12.5 12.58 15.0 12.35 20.0 11.86 25.0 11.33 35.0 10.12 45.0 8.60 50.27 5.92

0 TVA Nuclear Fue TVA-COLR-BF2C8 Core Operating Limits Report Revision 2, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8XSNB)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLHGR Limit Q(~WD 0.0

~ ~f 11.45 0.2 11.47 1.0 11.55 2.0 11.70 3.0 11.87 4.0 12.01 5.0 12.13 6.0 12.22 7;0 12.31 8.0 12.41 9.'0 12.51 10.0 12.63 12.5 12.64 15.0 12.41 20.0 11.91 25.0 11.35 35.0 10.15 45.0 8.72 50.5 5.93 51.4 5.87

II lb TVA Nuclear Fu TVA-COLR-BF2C8 Core Operating Limits Report Revision 2', Page 10 Table 4 APLHGR Limits for Bundle Type BPSDRB301L (BP8XSR)

Average Planar Exposure APLHGR Limit gxWD/ST} ~kw/f 0.0 11.32 0.2 11.33 1.0 11.40 2.0 11.50 3.0 11.61 4.0 11.73 5.0 11.86 6.0 11.93 7.0 11.98 8.0 12.03 9.0 12.11 10.0 12.19 12.5 12.34 15.0 12.47 20.0 12.58 25.0 12.03 35.0 10.82 43.5 9.17

TVANuclear Fue TVAKOLR-BF2C8 Core Operating Limits Report Revision 2, Page 11 Table 5 APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R)

Average Planar Exposure APLHGR Limit

$ QW~D~ ~kw f 0.0 10.71 0.2 10.75 1.0 10.86 2.0 11.01 3.0 11. 19 4.0 11.35 5.0 11.47 6.0 11.62 7.0 11.78 8.0 11.95 9.0 12.09 10.0 12.20 12.5 12.37 15.0 12.47 20.0 12.37 25.0 11.77 35.0 10.65 42.1 9.36

TVA Nuclear Fu TVAKOLR-BF2C8 Core Operating Limits Report Revision 2, Page 12 Table 6 APLHGR Limits for Bundle Type PSDRB284L and Westinghouse QUAD+ LTAs (PSXSR)

Average Planar Exposure APLHGR'imit

{QW~D/'jQ ~kw f 0.2 11.2 1.0 11.3 5.0 11.8 10.0 12.0 15.0 12.0 20.0 11.8 25.0 11.2 30.0 10.8 35.0 10.2 40.0 9.5 45.0 8.8

0 TVA Nuclear Fu TVA-COLR-BF2Cg Core Operating Limits Report Revision 2 Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (PSX8R)

Average Planar Exposure APLHGR Limit

{QW~D$'IQ ~kw/f 0.2 11.5 1.0 11.6 5.0 11.9 10.0 12.1 15.0 12.1 20.0 11.9 25.0 11.3 30.0 10.7 35.0 10.2 40.0 9.6

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0 II TVA Nuclear Fu TVA-COLR-BF2C8 Core Operating Limits Report Revision 2, Page 15 Figure 2 MCPR Operating Limit for GE8X8NB 1.31 (E~) to EOC8 1,29 gg 1.28 V

1.27 BOC8 to tEOC830BO) 1.26 1.25 1.24 0.0 0.1 0.2 0.3 0.4 0.5'.6 0.7 0.8 0.9 1.0 0~8 OgttanA Ex osure Ran e 0 tion A Tau=1.0 0 tion B Tnu=0.0 BOC8 to (EOC8-3080 MWD/ST) 1.28

• 1.26 (EOC8-3080 MWD/ST) to EOC8 1.32 1.30

• 'Use this value at BOC8 prior to performing scram time testing.

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TVA Nuclear Fuel TVA-COLR<<BF2C8 Core Operating Limits Report Revision 2, Page 16 (Final)

Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections 1.4 Narc I I7.0%

1.3 I 12.0%

I 07.0%

I 02.5 %

1.0 20 30 40 50 60 70 80 90 100 Total Core Flow (% rated)

For 40%,< 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 102.5 % 1.3308 MANUAL 107.0 % 1.3528 MANUAL 112;0 % 1.3793 MANUAL 117.0 % 1.4035 AUTOMATIC N/A 1.4410

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