ML20044G210

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Rev 1 to TVA-COLR-BF2C7, Browns Ferry Nuclear Plant Unit 2, Cycle 7 Colr.
ML20044G210
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/07/1993
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18036B302 List:
References
TVA-COLR-BF2C7, TVA-COLR-BF2C7-R01, TVA-COLR-BF2C7-R1, NUDOCS 9306020184
Download: ML20044G210 (16)
v • d • e


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', TVA-COLR-BF2C7 i Revision 1, Page1

. i Browns Ferry Nuclear Plant Unit 2, Cycle 7 t l

CORE OPERATING LIMITS RFPORT  :

(COLR)

TENNESSEE VALLEY AUTHORITY ,

Nuclear Fuel Division BWR Fuel Engineering Department  ;

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Prepared By: d Date: E- 7 -U Earl E. Riley, Nucledr Engineer  ;

BWR Fuel Engineering  ;

Reviewed By: 6 Date: f/7/73

' I Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Approved By: Date: 8 73 T. A. Keys,[ Manager i BWR Fuel Engineering 9306020184 930522 PDR ADOCKOSOOgO P j a

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- TVA N=!=r Fr! TVA-COLR-BF2C7 Core Operating Limits Report Revision 1, Page 2 Revision Log Revision Date Description Affected Pages -

0 4-5-93 Initial Release All 1 5-7-93 Incorporate Changes in MCPR Operating revised pages Limits to Reficct Additional Analyses as 2, 4, 6, 14-16.

summarized in Revision I to the SRL'R, deleted page reference 3. 17.

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. TVA Nuc! car Fuct TVA-COLR-BF2C7 Core Operating Limits Report ~ Revision 1 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 Reference 3.

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 asserably 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.I)
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. APLIIGR LIMIT (TECHNICAL SPECIFICATION 3.5.I)

The APLHGR limit for 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 LIMIT (TECHNICAL SPECIFICATION 3.5.J)

The LHGR limit for unit 2 cycle 7 is fuel type dependent , as shown below:

fuel type LHGR limii P8X8R/BP8X8R/ QUAD + 13.4 kw/ft GE8X8NB 14.4 kw/ft w .-

TVA Nuclear Fuel TVA-COLR-BF2C7 Core Operating Limits Report Revision 1. Page 4

4. OLMCPR (TECIINICAL SPECIFICATION 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 Kr shown in Figure 3, where;

%- Ta T = 0.0 or T= 3 .whichever is greater.

D - Ta T4 =

0.90 sec (Specification 3.3. C. I scram time limit to 20%

insertion frcm fully withdrawn )

_ _1 2

N Ta = 0. 710 + 1. 65 -

(0.053) n D

hvc =

n J

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

T = Scram time to 20% insertion from fully withdrawn of the i  ;

rod

.l N = Total number of active rods measured in Specification 4.3.C.1 -

at BOC 1 i

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[

, ., m . . . _ _ . . , _ . . - _. _._ _ - . - . . - . _ .

'. TVA Nuclear Fuct TVA-COLR-BF2C7

, Core Operating Limits Report Revision 1. Page 5 ,

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b. For the performance of Surveillance Requirement 4.5.K.2.a (prior to initial'  !

scram time measurements for the cycle), 5 t

a T = 1.0 i 1

)

c. For the performance of Suneillance Requirement 4.5.K.2.b, T shall be  !

i determined in accordance with 4.a above. -!

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_ _ . . _ _ .-_ . . . _ _ . _ . _ _ . __ . _ . . . _ _ . __ m _ .

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. i TVA Nuclear Feel TVA-COLR-BF2C7.

Core Operating Limits Report Revision 1, Page 6 i

5. REFERENCES  !
l. NEDE-24011-P-A-10, " General Electric Standard Application for Reactor Fuel",

February 1991.  ;

2. NEDE-240ll-P-A-10-US, " General Electric Standard Application for Reactor ,

Fuel", March 1991.

3. 23A7190, Rev.1, " Supplemental Reload Licensing Report for Browns Ferry i Nuclear Plant Unit 2 Reload 6 Cycle 7," April 1993. t
4. Safety Evaluation by the office of Nuclear Reactor Regulation Supporting  ;

Amendment No.125 to Facility Operating License No. DPR-52, Tennessee i 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. O, " Lattice-Dependent MAPLHGR Report for u. owns Ferry
Nuclear Plant Unit 2 Reload 6 Cycle 7", January 1993.  ;

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4  :

1

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. TVA Nuclear fuel TVA-COLR-BF2C7 --  !

Core Operating Limits Report Revision 1, Page 7  :

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Table 1 i APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ

' (GE8X8NB) f b

Most Limiting Lattice for Each Exposure Point  !

Average Planar Exposure APLH_GR Limit -

(GWD/ST) kw/ft l 0.0 10.97 i 0.2 11.00  ;

1.0 11.11 2.0 11.31 3.0 11.54 .;

4.0 11.79 i 5.0 I1.97 i 6.0 12.10  ;

, 7.0 12.23 8.0 12.35 9.0 12.46 l 10.0 12.58 12.5 12.58 l 15.0 12.35 l 20.0 11.86  !

25.0 11.33 i 35.0 10.12 45.0 8.60 ,

50.27 5.92-  !

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,- - r -, w e . n - -. _ _ _ _ _ ________J_______________l..

I l TVA Nuc! car Fuct TVA-COLR-BF2C7 i Core Operating Limits Rqmrt Revision 1. Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ -

(GE8X8NB) i Most Limiting Lattice -

for Each Exposure Point .

Average Planar Exposure . APLHGR Limit (GWD/ST) kw/ft 0.0 11.45 i 0.2 11.47 1.0 11.55 ,

2.0 11.70 3.0 11.87 4.0 12.01 i 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- 1 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 l

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- TVA Nuclear Fuel ' TVA-COLR-BF2C7 Core Operating Limits Report Revision I, Page 9 3

1 Table 3 i i

APLHGR Limits for Bundle Type P8DRB301L i (BP8X8R)

I l

i l.

Average Planar Exposure APLHGR Limit (GWD/ST) kw/ft  :

0.0 11.32  !

0.2 11.33  !

1.0 11.40 l 2.0 11.50 l 3.0 11.61 .

4.0 11.73 l 5.0 11.86  !

6.0 .I1.93- 1!

7.0 11.98 l 8.0 12.03 .!

9.0 12.11 10.0- 12.19-

]

12.5 12.34  !

15.0 12.47 I 20.0 12.58  !

25.0 -12.03 i 35.0 _

10.82 l 43.5 9.17 ~.

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TVA Nuclear Fuct TVA-COLR-BF2C7 '

Core Operating Limits Report Revision 1, Page 10 Table 4-APLHGR Limits for Bundle Type P8DRB299 (BP8X8R)

Average Planar Exposure APLHGR Limit l (GWD/ST) kw/ft }

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 l 6.0 11.62 j 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 i 42.1 9.36  !

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TVA Nuclear Fuct TVA-COLR-BF2C7 Core Operating Linnts Regnt Revision I, Page 11 1

Table 5  ;

APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD + LTAs'  !

(P8X8R) 'I t

6 l

. 1 Average Planar Exposure APLHGR Limit i (GWD/ST) kw/ft '!

0.2 11.2 -

1.0 11.3 i 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 l 2

40.0 9.5 e 45.0 8.8 t

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TVA Nuclear Fuel TVA-COLR-BF2C7 Core Operating Limits Repuit Revision 1, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284Z (P8X8R)

Average Planar Exposure APLHGR Limit (GWD/ST) kw/ft 0.2 11.2

,. I.0 11.2 5.0 11.7 10.0 12.0 15.0 12.0 20.0 11.8 25.0 11.1 30.0 10.4' 35.0 9.8 40.0 9.1 45.0 8.5 i

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'. TVA Nu;1 car Fuel TVA-COLR-BF2C7 '

Core Operating Limits Report Revision 1. Page 13  !

i Table 7 s APLHGR Limits for Bundle Type P8DRB265H l (P8X8R) [,

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. Average Planar Exposure APLHGR Limit ,

(GWD/ST) kw/ft 0.2-l 11.5 _l 1.0 11.6 i 5.0 11.9 >

t 10.0 12.1  !

15.0 12.1 20.0 11.9 >

25.0 11.3 {

30.0 10.7 -l 35.0 10.2  !

40.0 9.6 I I

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TVA Nuclear Fuel TVA-COLR-BF2C7

  • Core Operating Limits Report Revision 1. Page 14 Figure 1 MCPR Operating Limit for P8X8R/BP8X8R/ QUAD + l 1.35 . .

1.34 ----- - - - - - - ---

---l - ------- ---- - --

1.33 - - - -- -- - - -

---h ----

1.32 -- - - - - -

  • E1.31

-- -- 4 ---- .  ;

3 -

cc 1.30 - I ('" ' * '*' " l-- --- -- - - - -

C1. _ .

O

. 2 1.29 -

1 1,gg -. .. ..... , . .. . .. . * .........'. '

t l BOC7 to (IM)C7-2150) l 1.27 -- -

.-- 2----

[

1.26 4 . .

.  : i 1.25"""""""'""""""""'""""""""'""""'""""'"'"""'""""  !

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 i Option 11 Option A T  !

i

.i Exnosure Rance Option A (Tan =1.0) Ontion B (Tan =0.0)

BOC7 to (EOC7-2150) MWD /ST 128

  • 1.27  ;

(EOC7-2150) to EOC7 MWD /ST 1.32 1.29 i i

\

. Use this value at BOC7 prior to performing scram time testing. i 4-F f

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TVA Nuclear Fact TVA-COLR-BF2C7 Core Op-frating Limits Report Revision 1, Page 15 Figure 2 MCPR Operating Limit for GE8X8NB 1.35 1.34 --

1.33 - - - -- ----

1.32 . .I m>c - 21so) io roc 7 I; . . .

j 1.31 - - - - -

3 -

1.30 --

2 1.29 --

l noc7 to (noc7-21so) l:

/ -

1.27 - - - -- - - -

1.2G r '

' ~~

1.2 5 "=" ' " " " " ' " ^'""''"'"'"'""""'"""'"'"'"""

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 0;) tion H Optio; A Exposure Range Option A (Tan =1.(0 Option B (Tan =0 01 BOC7 to (EOC7-2150) MWD /ST 1.30

  • 1.28 (EOC7-2150) to EOC7 MWD /ST 1.34 1.31
  • Use this value at BOr7 prior to performing scram time testing.

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< TVA Nuclear Fuct TVA-COLR-BF2C7 Core Opemting Limits Report Revision 1.- Page 16 (Final)  !

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Figure a GEXL-Plus Kf Curve ~  :

OLMCPR Flow Corrections 1.4 i None '

117.0 %

1.3 -

112.0 %

4 107.0 %

102.5 %

Q 1.2 -

~1.1 -

1.0 ' ' '

20 30 40 50 60 70 80 90 100 -!

Total Core Flow (% rated) i For 40% < %7i 100%, Kf = MAX [ 1.0, A - 0.00441*%T ]

%Ti 40%, Kf = [ A - 0.00441*WT ] * [1.0 + 0.0032*( 40 - WT )] .j WT > 100 % , Kf = 1.0 j where : %T = Percent of Rated Core Flo.v. and A = constant which depends on the Flow Control Mode and the Scoop  !

Tube Setpoint as noted below.

now Con . - Scoon Tube Serpoint A l MANUAL 102.5 % 1.3308 l

MANUAL 107.0 % 1.3528 MANUAL 112.0 % 1.3793 MANUAL 117.0 % 1.4035 )

i' AUTOMATIC N/A 1.4410 l

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