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| number = ML18038A985
| number = ML18038A985
| issue date = 10/06/1994
| issue date = 10/06/1994
| title = Browns Ferry Nuclear Plant,Unit 2,Cycle 8,Core Operating Limits Rept.
| title = Cycle 8,Core Operating Limits Rept.
| author name = BRUCE A L, KEYS T A, RILEY E E
| author name = Bruce A, Keys T, Riley E
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:TVA-COLR-BF2CS Revision 0, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 8 CORE OPERATING LIMITS REPORT (COLR)TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By Alan L.Bruce, Nuclear Engineer BWR Fuel Engineering Verified By: Earl E.Riley, Nu lear Engineer BWR Fuel Engineering Date:~</~~~5'pproved By: T.A.Keys, Man ger BWR Fuel Engineering Reviewed By Reactor Engineering S or Date: tC Reviewed By: ORC Chairman Date: IO b t I J FDR~o2>>9ecoz<PDR, j  
{{#Wiki_filter:TVA-COLR-BF2CS Revision 0, 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 Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Verified By:                                   Date:
Earl E. Riley, Nu lear Engineer BWR Fuel Engineering               ~</~~~5'pproved By:
T. A. Keys, Man ger BWR Fuel Engineering Reviewed By                                     Date: tC Reactor Engineering S       or Reviewed By:                                   Date: IO b                   t I ORC Chairman J
    ~o2>> 9ecoz<
FDR PDR,     j


TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 2 Revisioa I,og Revision Date 0 10/03/94 D~escri tioo Initial Release Affected Pa es All ii H lk TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, 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 and 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.
TVA Nuclear Fuel                               TVA-COLR-BF2C8 Core Operating Limits Report                  Revision 0, Page 2 Revisioa I,og Revision       Date           D~escri  tioo    Affected Pa    es 0       10/03/94         Initial Release         All ii H
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.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) d.AP~Plpw 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 (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.
0 TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 4 3.LHGR LIMIT (TECHNICAL SPECIFICATION 3.5.J)The LHGR limit for unit 2 cycle 8 is fuel type dependent, as shown below:~Fuel T e P8X8R/BP8X8R/QUAD+
GE8X8NB LHGR Limit 13.4 kw/ft 14.4 kw/ft 4.OLMCPR (TECHNICAL SPECIFICATION 3.5.E/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=00 or whichever is greater.Z~=0.90 sec, (Specification 3.3.C.1 scram time limit to 20%insertion from'fully withdrawn)t Z~=0.710+1.65,-, (0.053)N 2 t.l."11,~l Ltn en g 7r Zave n where;n=Number of surveillance rod tests performed to date in cycle (including BOC test).Zi=Scram time to 20%insertion from fully withdrawn of the i th rod 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),
Cl II TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 5 c.For the performance of Surveillance Requirement 4.5.K.2.b,'C shall be determined in accordance with 4.a above.5.APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.I.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)The APRM Rod Block trip setting shall be: SRB<(0.58W+50/o)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 (TECHNICAL SPECIFICATION TABLE 3.2.C)The RBM Upscale trip setting shall be: s (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.
Il 4l l TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 6 7.REFERENCES 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.0,"Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," September 1994.4.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.
6.24A5153AA, Rev.0,"Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.


V'V A~~a'*'s c i~%v e" ea, b e i.v>~TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 7 Table 1 APLHGR Limits for Bundle Type GE98-P8DWB319-9GZ (6E8X8NB)Most Limiting Lattice for Each Exposure Point Average Planar Exposure~GWD/S 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 45.0 51.20 APLICGR Limit kw/ft 11.64 11.68 11.77 11.88 12.01 12.12 12.22 12.32 12.49 12.65 12.77 12.86 12.86 12.62 12.06 11.47 10.41 8.81 5.91 4l TVA Nuclear Fuel'Core Operating Limits Report TVA-CQLR-BF2CS Revision 0, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB)Most Limiting Lattice for Each Exposure Point Average Planar Exposure~GWD/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 45.0 50.27 APLHGR Limit kw/ft 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
lk TVANuclear Fuel                                                     TVA-COLR-BF2C8 Core Operating Limits Report                                        Revision 0, 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 and 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.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)
: d. AP~ Plpw 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(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.


TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)Most Limiting Lattice for Each Exposure Point Average Planar Exposure~GWD/ST 0.0 0.2 1.0 2.0 30 40 5.0 6.0 7.0.8.0 9.0 10.0 12.5t'5.0'0.0 25.0 35.0'45.0 50.5 51.4 APLHGR Limit km/ft 11.45 11.47 11.55 11.70 11.87 12.01 12.13 12.22 12.31 12.41 12.51 12.63 12.64 12.41 11.91 11.35 10.15 8.72 5.93 5.87
0 TVANuclear Fuel                                                            TVA-COLR-BF2C8 Core Operating Limits Report                                               Revision 0, Page 4
: 3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.5.J)
The LHGR limit for unit 2 cycle 8 is fuel type dependent, as shown below:
                      ~Fuel  T    e                      LHGR Limit P8X8R/BP8X8R/QUAD+                          13.4 kw/ft GE8X8NB                            14.4 kw/ft 4 . OLMCPR (TECHNICAL SPECIFICATION 3.5.E/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  =00          or                                      whichever is greater.
Z~  = 0.90 sec,        (Specification 3.3.C.1 scram time limit to 20%
insertion from'fully withdrawn )
t N  2 Z~  = 0.710 +      1.65,,        (0.053) t.l."11,  ~  l    Ltn en g    7r Zave n
where;    n = Number        of surveillance  rod tests performed to date in cycle (including BOC test).
th Zi = Scram time to 20% insertion from fully withdrawn          of the  i rod 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),


TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)Average Planar Exposure~GWD/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 43.5 fj]II l.~i APLHGR Limit kw/ft 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 Cl TVA Nuclear Fuel Core Operating Linuts Report TVA-COLR-BF2CS Revision 0, Page 11 Table 5 APLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)Average Planar Exposure~GWD/S 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/ft 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
Cl II TVA Nuclear Fuel                                                 TVA-COLR-BF2CS Core Operating Limits Report                                    Revision 0, Page 5
: c. For the performance of Surveillance Requirement 4.5.K.2.b,    'C shall be determined in accordance with 4.a above.
: 5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.I.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)
The APRM Rod Block trip setting shall be:
SRB < (0.58W      +  50/o) 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:
s (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 Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+LTAs (PSX8R)Average Planar Exposure~GWD/S 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/ft 11.2 11.3 11.8 12.0 12.0 11.8 11.2 10.8 10.2 9.5 8.8
Il 4l TVANuclear Fuel                                                   TVA-COLR-BF2CS Core Operating Limits Report                                      Revision 0, Page 6
: 7. REFERENCES
: 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. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," September 1994.
: 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. 24A5153AA, Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.


TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)Average Planar Exposure~GWD/ST 0.2 1.0 5.0 10;0 15.0 20.0 25.0 30.0 35.0 40.0 APLHGR Limit kw/ft 11.5 11.6 11.9 12.1 12.1 11.9 11.3 10.7 10.2 9.6
V    'V A      ~ ~ a'*'  s  c i ~    %v e"      b      e  i    .v > ~
TVA Nuclear Fuel                                                 TVA-COLR-BF2C8 Core Operating Limits Report                                     Revision 0, Page 7 Table     1 APLHGR Limits for Bundle Type GE98-P8DWB319-9GZ (6E8X8NB)
Most Limiting Lattice for Each Exposure Point Average Planar Exposure                         APLICGR Limit
                ~GWD/S                                      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


a w.i'ay~'e'i t~s''~isa':~~~',So~'I alai (''.w~~~~<v TVA Nuclear Fuel Core Operating Limits Report TVA-'COLR-BF2CS Revision 0, Page 14 Figure 1 MCPR Operating Limit for P8X8R/BP8X8R/QUAD+
4l TVA Nuclear Fuel                                             TVA-CQLR-BF2CS
1.33 1.32 1.31 1.30 1.29 1.28 1.27.1.26 1.25 (EOCS-3080) to EOCS BOC8 to (EOCS-3080) 1.24'.23 0.0 0.1 0.2 0;3.0.4 0.5 0.6 Option B 0.7'.8 0.9 1.0 Option A F~l*"" R*" BOC8'o (EOC8-3080 MWD/ST)(EOC8-3080.MWD/ST) to EOC8 0 tion A Tau=1.0 1.26*1.30 0 tion B Tau=0.0 1.25 1.27": Use this value at BOC8 prior to performing scram time testing.  
'Core Operating Limits Report                                 Revision 0, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB)
Most Limiting Lattice for Each Exposure Point Average Planar Exposure                      APLHGR Limit
                  ~GWD/ST                                  kw/ft 0.0                                10.97 0.2                                11.00 1.0                                 11.11 2.0                                 11.31 3.0                                 11.54 4.0                                 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


~'I''hh'''hh~~hw hh'h I'IJA'h h, w 8>>-h',~~h*.~~h h-" hhu~~h~: h'h'h hV'h TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 15 Figure 2 MCPR Operating Limit for GE8X8NB 1.33 1.32 1.31 1.30 (EOC8-3080) to EOC8 1.29 1.28 g 1.27 1.26 ,BOC8 ho (BOC8-3080) 1.25 1.24 I 1.23 0.0 0.1 Oh2 0;3: 0'.4'h5 0.6'.7'.8 0.9 1.'0 Option B.Option A'KR BOC8 to (EOC8-3080 MWD/ST)(EOC8-3080'MWD/ST).
TVA Nuclear Fuel                                                  TVA-COLR-BF2CS Core Operating Limits Report                                        Revision 0, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)
to EOC8 0 tion A Tan=1.0 1.27"'.32~O~iB h=h.ll 1.25 1.29": Use this value at BOC8 prior to performing scram time testing.
Most Limiting Lattice for Each Exposure Point Average Planar Exposure                            APLHGR Limit
0 TVA Nuclear Fuel Core Operating Limits eport TVA-COLR-BF2C8 Revision 0,'Page 16 (Final)'I.4 Fi.gure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections None 1.3 117.0%112.0%107.0%102.5%1.'0 30 40 60 60 70 80 Total Core Flow (%rated)90 100 For 40%<WT<100%, Kf=MAX[1.0, A-0.00441*WT]
                ~GWD/ST                                      km/ft 0.0                                      11.45 0.2                                      11.47 1.0                                      11.55 2.0                                      11.70 30                                      11.87 40                                      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 12.5t                                    12.64
WT<40%, Kf=[A-0.00441+WT]
                          '5.0'0.0 12.41 11.91 25.0                                      11.35 35.0'                                    10.15 45.0                                      8.72 50.5                                      5.93 51.4                                      5.87
+[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.Flow Control Mode Scop Tube Set oint MANUAL MANUAL MANUAL MANUAL AUTOMATIC 102.5%107.0%112.0%117.0'%/A 1.3308 1.'3528 1.3793 1.4035 1.4410 vl~}}
TVANuclear Fuel                                  TVA-COLR-BF2CS Core Operating Limits Report                      Revision 0, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)
Average Planar Exposure          APLHGR Limit
                ~GWD/ST                      kw/ft 0.0                    11.32 0.2                    11.33 1.0                    11.40 2.0              fj]    11.50 3.0          II 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          l.        12.19 12.5              ~i    12.34 15.0                    12.47 20.0                    12.58 25.0                    12.03 35.0                    10.82 43.5                      9.17
 
Cl TVA Nuclear Fuel                                TVA-COLR-BF2CS Core Operating Linuts Report                      Revision 0, Page 11 Table 5 APLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)
Average Planar Exposure          APLHGR Limit
                ~GWD/S                      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 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 Fuel                                  TVA-COLR-BF2CS Core Operating Limits Report                      Revision 0, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+ LTAs (PSX8R)
Average Planar Exposure            APLHGR Limit
                ~GWD/S                      kw/ft 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
 
TVA Nuclear Fuel                                TVA-COLR-BF2CS Core Operating Limits Report                    Revision 0, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)
Average Planar Exposure          APLHGR Limit
                ~GWD/ST                    kw/ft 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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1.33 1.32 1.31 1.30 1.29 (EOCS-3080) to EOCS 1.28 1.27      .
1.26 BOC8 to (EOCS-3080) 1.25 1.24'.23 0.0    0.1  0.2    0;3    .0.4      0.5      0.6    0.7'.8            0.9        1.0 Option  B                                                                  Option A F~l*    "  " R*"                    0  tion A Tau=1.0                0      tion B Tau=0.0 BOC8'o (EOC8-3080 MWD/ST)                                  1.26
* 1.25 (EOC8-3080.MWD/ST) to EOC8                                1.30                                    1.27 Use this value at BOC8 prior to performing scram time testing.
 
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                                    ,BOC8   ho (BOC8-3080) 1.26 1.25 1.24                                             I 1.23 0.0     0.1     Oh2         0;3: 0'.4'h5         0.6'.7'.8                 0.9       1.'0 Option B                                                                         .Option A'KR 0  tion A Tan=1.0                    ~O~iB h =h.ll BOC8 to (EOC8-3080 MWD/ST)                                   1.27
                                                                                      "'.32 1.25 (EOC8-3080'MWD/ST). to EOC8                                                                         1.29 Use this value at BOC8 prior to performing scram time testing.
 
0 TVANuclear Fuel                                                       TVA-COLR-BF2C8 Core Operating Limits eport                                          Revision 0, 'Page 16 (Final)
Fi.gure 3 GEXL-Plus                   Kf   Curve OLMCPR Flow Corrections
    'I .4 None 117.0 %
1.3      112.0 %
107.0 %
102.5 %
1.'0 30       40         60           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.
Flow Control Mode       Scop Tube Set oint MANUAL                   102.5 %               1.3308 MANUAL                  107.0 %               1.'3528 MANUAL                  112.0 %               1.3793 MANUAL                  117.0'%/A 1.4035 AUTOMATIC                                        1.4410
 
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Latest revision as of 14:55, 3 February 2020

Cycle 8,Core Operating Limits Rept.
ML18038A985
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/06/1994
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038A984 List:
References
TVA-COLR-BF2C8, TVA-COLR-BF2C8-R, TVA-COLR-BF2C8-R00, NUDOCS 9411070211
Download: ML18038A985 (32)
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Text

TVA-COLR-BF2CS Revision 0, 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 Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Verified By: Date:

Earl E. Riley, Nu lear Engineer BWR Fuel Engineering ~</~~~5'pproved By:

T. A. Keys, Man ger BWR Fuel Engineering Reviewed By Date: tC Reactor Engineering S or Reviewed By: Date: IO b t I ORC Chairman J

~o2>> 9ecoz<

FDR PDR, j

TVA Nuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 2 Revisioa I,og Revision Date D~escri tioo Affected Pa es 0 10/03/94 Initial Release All ii H

lk TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, 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 and 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.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)

d. AP~ Plpw 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(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.

0 TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 4

3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.5.J)

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

~Fuel T e LHGR Limit P8X8R/BP8X8R/QUAD+ 13.4 kw/ft GE8X8NB 14.4 kw/ft 4 . OLMCPR (TECHNICAL SPECIFICATION 3.5.E/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 =00 or whichever is greater.

Z~ = 0.90 sec, (Specification 3.3.C.1 scram time limit to 20%

insertion from'fully withdrawn )

t N 2 Z~ = 0.710 + 1.65,, (0.053) t.l."11, ~ l Ltn en g 7r Zave n

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

th Zi = Scram time to 20% insertion from fully withdrawn of the i rod 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),

Cl II TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 5

c. For the performance of Surveillance Requirement 4.5.K.2.b, 'C shall be determined in accordance with 4.a above.
5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.I.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)

The APRM Rod Block trip setting shall be:

SRB < (0.58W + 50/o) 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:

s (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.

Il 4l TVANuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 6

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

V 'V A ~ ~ a'*' s c i ~ %v e" b e i .v > ~

TVA Nuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 7 Table 1 APLHGR Limits for Bundle Type GE98-P8DWB319-9GZ (6E8X8NB)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLICGR Limit

~GWD/S 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

4l TVA Nuclear Fuel TVA-CQLR-BF2CS

'Core Operating Limits Report Revision 0, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB)

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

~GWD/ST kw/ft 0.0 10.97 0.2 11.00 1.0 11.11 2.0 11.31 3.0 11.54 4.0 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

TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)

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

~GWD/ST km/ft 0.0 11.45 0.2 11.47 1.0 11.55 2.0 11.70 30 11.87 40 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 12.5t 12.64

'5.0'0.0 12.41 11.91 25.0 11.35 35.0' 10.15 45.0 8.72 50.5 5.93 51.4 5.87

TVANuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 11.32 0.2 11.33 1.0 11.40 2.0 fj] 11.50 3.0 II 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 l. 12.19 12.5 ~i 12.34 15.0 12.47 20.0 12.58 25.0 12.03 35.0 10.82 43.5 9.17

Cl TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Linuts Report Revision 0, Page 11 Table 5 APLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)

Average Planar Exposure APLHGR Limit

~GWD/S 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 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 Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+ LTAs (PSX8R)

Average Planar Exposure APLHGR Limit

~GWD/S kw/ft 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

TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 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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. w ~~~ ~ < v TVA Nuclear Fuel TVA-'COLR-BF2CS Core Operating Limits Report Revision 0, Page 14 Figure 1 MCPR Operating Limit for P8X8R/BP8X8R/QUAD+

1.33 1.32 1.31 1.30 1.29 (EOCS-3080) to EOCS 1.28 1.27 .

1.26 BOC8 to (EOCS-3080) 1.25 1.24'.23 0.0 0.1 0.2 0;3 .0.4 0.5 0.6 0.7'.8 0.9 1.0 Option B Option A F~l* " " R*" 0 tion A Tau=1.0 0 tion B Tau=0.0 BOC8'o (EOC8-3080 MWD/ST) 1.26

  • 1.25 (EOC8-3080.MWD/ST) to EOC8 1.30 1.27 Use this value at BOC8 prior to performing scram time testing.

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,BOC8 ho (BOC8-3080) 1.26 1.25 1.24 I 1.23 0.0 0.1 Oh2 0;3: 0'.4'h5 0.6'.7'.8 0.9 1.'0 Option B .Option A'KR 0 tion A Tan=1.0 ~O~iB h =h.ll BOC8 to (EOC8-3080 MWD/ST) 1.27

"'.32 1.25 (EOC8-3080'MWD/ST). to EOC8 1.29 Use this value at BOC8 prior to performing scram time testing.

0 TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits eport Revision 0, 'Page 16 (Final)

Fi.gure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections

'I .4 None 117.0 %

1.3 112.0 %

107.0 %

102.5 %

1.'0 30 40 60 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.

Flow Control Mode Scop Tube Set oint MANUAL 102.5 % 1.3308 MANUAL 107.0 % 1.'3528 MANUAL 112.0 % 1.3793 MANUAL 117.0'%/A 1.4035 AUTOMATIC 1.4410

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