ML023240187

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Core Operating Limits Report (Colr), Revision 2, for Cycle 12 Operation
ML023240187
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/08/2002
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023240187 (27)
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 November 8, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket No. 50-260 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 - CORE OPERATING LIMITS REPORT (COLR), REVISION 2, FOR CYCLE 12 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is Revision 2 to the Unit 2 Cycle 12 Core Operating Limits Report (COLR). The COLR was revised to support continued operation following a mid-cycle replacement of leaking fuel assemblies.

There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.

ti0 P-nted omrecycled paper

U.S. Nuclear Regulatory Commission Page 2 November 8, 2002 Enclosure cc (Enclosure):

Mr. Paul E. Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Kahatan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 2 CORE OPERATING LIMITS REPORT (COLR), REVISION 2 FOR CYCLE 12 OPERATION (SEE ATTACHED)

TVA"Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 1 L32 021024 800 Browns Ferry Nuclear Plant QA RECORD Unit 2, Cycle 12 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date: lo-2 3-oh.

Earl E. Riley, Engineering Specialist BWR Fuel Engineering Verified By: Date: 1(/2 3/o 2.

Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Approved By: Date: /" 3 --r2.

Lýa-mes F. Lemons, Manager BWR Fuel Engineering Reviewed By: Date: /0-"2'-OZ

^4 Keck, Supervisor Browns Ferry Reactor Engineering Reviewed By: Date: /o- -

Revision 2 (10/24/2002) Modifications for MOC Outage Pages Affected: 1-7, 11, 17-24

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 2 Revision Log Revision Date Description Affected Pages 0 3/14/2001 Initial Release for New Cycle All 1 4/20/2001 Revise Table under Figure 9 to 1, 2, and 20 correct typographical error BF PER 01-004088-000 2 10/24/2002 Add GEl 1 Data for October 2002 1 thru 7, 11, Mid-Cycle Outage Core Loading and 17 thru 24 Alterations. OLMCPR limits for GE 11 fuel is not provided for the MOC12 exposure point since the plant has already exceeded the allowable cycle exposure prior to loading the GEl I reinserts.

"TVANuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 12 is prepared in accordance with the requirements of Browns Ferry Technical Specification 5.6.5. 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 12 are documented in References 3 and 12.

The following core operating limits are included in this report:

a. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)
b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3)
c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5)

d. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)
e. Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)
f. Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

TVA Nuclear Fuel TVA-COLR-BF2CI2 Core Operating Limits Report Revision 2, Page 4

2. APLHGR LIMIT (TECHNICAL SPECIFICATIONS 3.2.1 AND 3.7.5)

The APLHGR limits for full power and flow conditions for each type of fuel as a function of exposure are shown in Figures 1-7. The APLHGR limits for the GEl1 and GE13 assemblies are for the most limiting lattice (excluding natural uranium) at each exposure point. The specific values for each lattice are given in Reference 4 (GE13) or Reference 11 (GEl1). The applicability of the Reference 11 GEl1 MAPLHGR values for Cycle 12 is addressed in Reference 12.

These APLHGR limits are adjusted for off-rated power and flow conditions using the ARTS factors, MAPFAC(P) and MAPFAC(F). The reduced power factor, MAPFAC(P),

is given in Figure 8. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 9. Both factors are multipliers used to reduce the standard APLHGR limit. The most limiting power-adjusted or flow-adjusted value is taken as the APLHGR operating limit for the off-rated condition.

The APLHGR limits in Figures 1-7 are applicable for both Turbine Bypass In-Service and Out-Of-Service. The off-rated power and flow corrections in Figures 8 and 9 bound both Turbine Bypass In-Service and Out-Of-Service operation. No corrections are required to the APLHGR limits for TBOOS for either rated or off-rated operation.

The APLHGR limits in Figures 1-7 are applicable for both Recirculation Pump Trip (RPT) In-Service and Out-Of-Service. The off-rated power and flow corrections in Figures 8 and 9 bound both RPT In-Service and Out-Of-Service operation. No corrections are required to the APLHGR limits for RPTOOS for either rated or off-rated operation.

For Single Recirculation Loop Operation (SLO), the most limiting of either the SLO multiplier or the off-rated MAPFAC correction is used to reduce the exposure dependent APLHGR limit. The SLO multiplier to be applied to this cycle is 0.84 (references 3 and 12). It is not necessary to apply both the off-rated MAPFAC and SLO multiplier corrections at the same time.

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2. Page 5

3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3)

The LHGR limit is fuel type dependent. For Unit 2 Cycle 12 there are two fuel types in the core. The limits for these types are shown below:

Fuel Type LHGR Limit GEl 1 14.4 kw/ft GE13 14.4 kw/ft

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Lirmts Report Revision 2, Page 6

4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4.1, AND 3.7.5)
a. Rated Limits - OLMCPR(100): The MCPR Operating Limit for rated power and flow conditions, OLMCPR(100), is equal to the fuel type and exposure dependent limit shown in Figures 10 and 11. Both figures apply to GE13 fuel type. Figure 11 also applies to the GEl 1 fuel type.

Figure 10 applies to exposure up to 2000 MWD/ST prior to EOR (end of full power capability at rated flow with normal feedwater temperature) after which Figure 11 shall be used. It is acceptable to use the more restrictive Figure 11 limits at any point in the cycle.

As noted in Figures 10 and 11, an adder of 0.03 is applied for single loop operation.

The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below (ref. 10):

"T17e - TB T = 0.0 or , whichever is greater T A- TB where; TA = 1.096 sec (analytical Option A scram time limit - based on dropout time for notch position 36) n Z Ti taV~- i=1 n

"C,= g++/-1.65" a* [NI]

where; p. = 0.830 sec (mean scram time used in transient analysis based on dropout time for notch position 36) a= 0.019 see (standard deviation of p)

N = Total number of active rods measured in Technical Specification Surveillance Requirement SR3.1.4.1 n = Number of surveillance rod tests performed to date in cycle

",r= Scram time (dropout time) from fully withdrawn to notch position 36 for the it ' rod

b. Startup Limits: Option A OLMCPR limits (1 = 1.0) shall be used prior to the determination of T in accordance with SR 3.1.4.1.

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2. Page 7

c. Off-Rated Limits: For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits are determined from Figures 12 and 13, respectively. The most limiting power-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition.
d. Equipment Out-Of-Service OLMCPR Limits: Rated power OLMCPR(100) limits are provided for Recirculation Pump Trip out-of-service (RPTOOS),

Turbine Bypass out-of-service (TBOOS), and the combined RPTOOS/TBOOS condition in Figures 10 and 11 (reference 5). Additionally an off-rated MCPR(P) correction from Figure 12 (reference 5) shall be applied for TBOOS when the power is below Pbypass.

e. Single Loop Operation (SLO) Limits: As noted in section 4.a above, a correction of 0.03 is to be applied to the OLMCPR(100) limits for SLO as described in the footnote of Figures 10 and 11. The same adder applies to the off rated MCPR(F) limit as noted in the footnote to Figure 13 and to the OLMCPR value below Pbypass from Figure 12.

I-.A Nuclear Fuel TVA-COLR-BF2CI2 Core Operating Limits Report Revision 2, Page 8

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUAL SECTION 5.3.1 AND TABLE 3.3.4-1)

The APRM Rod Block trip setting shall be:

SRB < (0.66(W-AW) + 61%) Allowable Value SRB < (0.66(W-AW) + 59%) Nominal Trip Setpoint (NTSP) where:

SRB= Rod Block setting in percent of rated thermal power (3458 MWt)

Loop recirculation flow rate in percent of rated AW= Difference between two-loop and single-loop effective recirculation flow at the same core flow (AW=0.0 for two-loop operation)

The APRM Rod Block trip setting is clamped at a maximum allowable value of 115 %

(corresponding to a NTSP of 113%).

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 9

6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS AND OPERABILITY (TECHNICAL SPECIFICATION TABLE 3.3.2.1-1)

The RBM trip setpoints and applicable power ranges shall be as follows (refs. 7-9):

RBM Trip Setpoint Allowable Value Nominal Trip Setpoint (AV) (NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 118.7% 117.0%

(1),(2)

- filtered 117.7% 116.0%

ITSP - unfiltered 113.7% 112.0% (1),(2)

- filtered 112.9% 111.2%

HTSP - unfiltered 108.7% 107.0% (1),(2)

-filtered 107.9% 106.2%

DTSP 90% 92%

Notes: (1) These setpoints are based upon a MCPR operating limit of 1.25 using a safety limit of 1.07, as reported in references 6, 7, and 8. These setpoints bound the cycle specific minimum Option B MCPR operating limit of 1.29.

(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 7).

The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:

THERMAL POWER Applicable Notes from

(% Rated) MCPR 0) Table 3.3.2.1-1

> 27% and < 90% < 1.70 (a), (b), (f), (h) dual loop operation

< 1.75 (a), (b), (f), (h) single loop operation

> 90% < 1.40 (g) dual loop operation (2)

Notes: (1) The MCPR values shown correspond to a SLMCPR of 1.07 for dual recirculation loop operation and 1.10 for single loop operation.

(2) Greater than 90% rated power is not attainable in single loop operation.

TVA -Nuclear Fuel TVA-COLR-BF2C12 Core Operating Limits Report Revision 2, Page 10

7. SHUTDOWN MARGIN (SDM) LIMIT (TECHNICAL SPECIFICATION 3.1.1)

The core shall be subcritical with the following margin with the strongest OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted.

SDM > 0.38% dk/k

TVA Nuclear Fuel TVA-COLR-BF2C12 Core Operating Limits Report Revision 2, Page 11

8. REFERENCES
1. NEDE-2401 1-P-A-14, "General Electric Standard Application for Reactor Fuel", June 2000.
2. NEDE-2401 1-P-A-14-US, "General Electric Standard Application for Reactor Fuel (Supplement for United States)", June 2000.
3. J 11-03718-10-SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 11 Cycle 12", January 2001.
4. J 11-03718-10-MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 11 Cycle 12", January 2001.
5. NEDC-32774P Supplement 1 Revision 0, "Browns Ferry Nuclear Plant Units 1, 2, and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Combination Mode Out-Of Service", dated February 2001.
6. NEDC-32433P, "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.
7. EDE-28-0990 Rev. 3 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated October 1997.
8. EDE-28-0990 Rev. 2 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL (NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated October 1997.
9. GE Letter LB#: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.

[L32 970912 800]

10.GE Letter JAB-T8019a, "Technical Specification Changes for Implementation of Advanced Methods", dated June 4, 1998. [L32 980608 800]

11. J 11-03447MAPL Rev. 1, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 10 Cycle 11", March 1999.
12. 0000-0009-2842 Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Unit 2 Cycle 12C", October 2002.

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 12 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 1500 1400 1300 UNACCEPTA3LE OPERAT1O 1200 J 1100 1000

""E 800

- ,ACCEPTABLE OPEATI x 700

. 6 O0 0

5 00 400 3000 200 100 I 0 00 00 100 200 300 400 500 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Umilt Exposure Umit Exposure Umit (GWDIST) (kwlft) (GWD/SI) (kwtft) (GWDIST) (kw/ft) 00 1 10.09 7.0 11.71 25.0 10.75 02 1 10.15 8.0 11.95 30.0 10.43 1.0 10.31 90 12.16 35.0 1006 2.0 10.52 10.0 12.28 40.0 1 972 3.0 10.75 12.5 12.16 45.0 9.38 4.0 ti 10.99 15.0 11.88 500 - 9.03 50 11.25 17.5 11.56 550 866 60 11.48 20.0 1124 55.98 858 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 13 Figure 2 APLHGR Limits for Bundle Type GE13-P9DTB406-13GZ (GE13) 1500 1400 1300 1200 1100 1000 9 00 E 8 00

.J C,, 700 C-.

600 500 400 300 2 00 1 00 0 00 00 100 200 300 400 500 Cycle Exposune (GWDIST)

Most Limiting Lattce for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Umit Exposure Umit Exposure Umit (GWD/ST) (kwtft) (GWD/ST) (kw/ft) (GWDIST) (kwlft) 0.0 1 10.66 7.0 11.75 250 11.33 0.2 I 1069 8.0 11.87 30.0 1076 1.0 1 10.76 9.0 11.99 350 10.29 20 10.89 10.0 12.12 400 9.85 30 11.06 125 12.16 450 9.45 4.0 i 11.24 150 12.14 500 903 50 11.45 175 12.03 550 866 6.0 11.61 20.0 11.78 59.01 8.38 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described In Section 2.

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 14 Figure 3 APLHGR Limits for Bundle Type GE13-P9DTB401-14GZ (GE13) 1500 1400 1300 120ooUNACCEPTABLE OPERATIOC 1200 1100 1000

- 800

-j ACCEPTABLE OPERATIOCj 1 700

a. 600 I 5 00 400 300 200 100 000 00 100 200 300 400 500 Cycle Exposure (GWDtST)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Umit Exposure Umit Exposure Umit (GWDIST) (kw/R)- (GWDI/ST) (kw/ft) (GWDIST) (kwlft) 0.0 1 10.49 7.0 11.44 250 11.10 0.2 10.52 80 1 11.59 30.0 10.55 10 10.59 90 11.72 350 10 15 2.0 1074 10.0 11.85 400 9.80 3.0 10.90 12.5 11.84 450 947 40 11.02 150 11.84 50.0 901 50 11 15 17.5 1183 550 856 "60 11-29 200 11.71 58.59 8.23 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described in Section 2.

"TVANuclear Fuel "TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 15 Figure 4 APLHGR Limits for Bundle Type GE13-P9DTB391-13GZ (GE13) 1500 1400 1300 CUNACCEPTABLE OPERATIo 1200 1100 1000 9 00 800 E

7 00 CCEPTrABLE OPERATIO C,

a-

-C 6 00 500 4 00 3 00 2 00 100 0 00 00 100 200 30 0 40 0 50 0 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Umit Exposure Umit Exposure Umit (GWDIST) Jkfj (GWD/ST) (kwfft) (GWDIST) (kwtft) 00 10.75 7.0 11.45 250 10.79 0.2 10.80 8.0 11.55 300 1024 1.0 10.87 90 11.66 350 985 2.0 10.96 100 11.77 40.0 949 3.0 11.06 12.5 11.71 450 9.15 40 11.15 15.0 11.63 500 878 50 i 11.25 17.5 11.55 550 845 60 1135 20.0 11.39 57.82 8.27 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculatlon Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described in Section 2.

TVA-Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 16 Figure 5 APLHGR Limits for Bundle Type GE13-P9DTB412-2G7.0/11G5.0 (GE13) 1500 1400 1300 1200 - UNACCEPTABLE OPERATIOI I 1100 1000 900 800.

"E

-* (ACCEPTABLE OPERATIO

", 700

- S' 60 40.

5 00 4 00 300 i I 100o I I 0 00 00 100 200 300 400 500 Cycle Exposure (GWDIST)

Most Lmrtng Lattce for Each Exposure Pcxnt Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Umlt. Exposure Umit Exposure Umit (GWD/ST) (kw/wft) * (GWD/ST) (kw/ft) (GWDIST) (kwtft) 0.0 10.38 7.0 11.58 250 11.12 0.2 10.45 8.0 11.73 30.0 1 1078 1.0 10.57 9.0 11.86 35.0 1046 2.0 10.72 10.0 12.00 40.0 10.01 3.0 10.88 12.5 12.03 45.0 949 4.0 I 11.05 15.0 11.96 500 9 04 5.0 1122 175 11.80 550 866 60 1 11.40 200 11.59 57.99 8 45 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described in Section 2.

TVA.Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 17 Figure 6 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE 11) 15 14 13 12 NACCEPTABLE OPERATION 11 10

-J7 7 ACCEPTABLE OPERATION

" 6 5

4 3

2 I

0 00 100 20.0 300 400 500 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point Average Planar LHUR Average Planar LHGR Average Planar LHUR Exposure Umit Exposure Umit Exposure Umit (GWDIST) (kwlft) (GWDIST) (kw/ft) (GWDIST) (kwtft) 0.0 9.55 7.0 11.39 25.0 10.51

.2 1 9.62 .... . ... -7 300 -...*_T 9.84 1.0 980 9.0 1181 35.

2.0 1005 10.0 11.95 40.0 -.65

,0 10.32 - --25 1 - 4 5--45:0- 79-..

4.0 10.58 15 0 11T722 50.0 - 7-:26 50 10.84 17.5 11.489-5-..0 675

.......... 60-.. 1t- 200 1.20 -56.7 . . 642 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described In Section 2.

T-IA.Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 18 Figure 7 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE 11) 15 14 13 12 11 10 9

A8 E

7 C,

z-J

0. 6

'C 5

4 3

2 1

0 L 00 100 200 300 400 500 Cycle Exposure (GWDIST)

Most Lmrtmng Lattice for Each Exposure Point Average Planar LHOR Average Planar L.HUR Average Planar LHIGR Exposure Umit Exposure Umit Exposure Umit (GWDIST) (kw/ft) (GWDIST) (kwI/t) (GWD/ST) (kwlft) 0.0 9.18 7.0 1 25 0 10.51

---...0:2 -.

27 -0 -- :7- 30-0" .. 9.84 1.0 945 9.0 11.81 30 9T9 2.0 9.72 10.0 I1.5 400

-0 10 000-5 ---- I:92- 4S 0 7-91 4.0 10.30 15.0 1 11.72 S00 7.26-5.0 10 62 17.5 11.48 50 6-59

-6 0 O.

2- aTO-S t-120 56 17 6-42 These values apply to both Turbine Bypass In-Service and Out-Of-Service.

These values apply to both Recirculation Pump Trip In-Service and Out-Of-Service.

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limiting of either 0.84 or the MAPFAC correction, as described in Section 2.

"ITVA Nuclear Fuel T'VA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 19 Figure 8 Power Dependent MAPLHGR Factor - MAPFAC(P) 1.2 1

08 S06 04 0.2 0

0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits For 25% > P NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED For 25% < P < 30% : MAPFAC(P) = 0.60 + 0.005(P-30%) For < 50% CORE FLOW

MAPFAC(P) = 0.46 + 0.005(P-30%) For > 50% CORE FLOW For 30% < P  : MAPFAC(P) = 1.0 + 0.005224(P-100%)

These values bound both Turbine Bypass In-Service and Out-Of-Service These values bound both Recirculation Pump Trip In-Service and Out-Of-Service

TVA-COLR-BF2C 12 TVA Nuclear Fuel Revision 2, Page 20 Core Operating Limits Report Figure 9 I

Flow Dependent MAPLHGR Factor - MAPFAC(F) 1 MAX FLOW - 1025%

09 08 IL 07 MAX FLOW 107%

06 05 04 30 40 50 60 70 80 90 100 Core Flow (% Rated)

FOR Wc (% Rated Core Flow) >= 30%

MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM( 1.0, Af*Wc I100 + Bf)

Af and Bf are Constants Given Below:

Maximum Cor Flow Af Bf

(%Rated) 102.5 06784 04861 107.0 06758 04574 These values bound both Turbine Bypass In-Service and Out-Of-Service.

These values bound both Recirculation Pump Trip In-Service and Out-Of-Service.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

The 107% maximum flow line is used for operation up to 105% rated flow (ICF).

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operattig Limits Report Revision 2, Page 21 Figure 10 MCPR Operating Limit for All GE13 Bundles For Cycle Exposures up to EOR.2000 MWD/ST (see note 3)

U a.

_E

-I a,.

U 0 01 02 03 04 05 06 07 08 09 Option B Option A Tau (t:)

Exposure Range Out-Of-Service Option A (1) Option B Tau=1.0 Tau=O.0 BOC12 to (EOR-2000 MWD/ST) na 1.31 1.29 BOC12 to (EOR-2000 MWD/ST) Turbine Bypass (TBOOS) 1 35 1.30 BOC12 to (EOR-2000 MWD/ST) Recirculation Pump Tnp (RPTOOS) 1 35 1 30 BOC12 to (EOR-2000 MWD/ST) I TBOOS and RPTOOS 1.39 1.34 Notes 1 Use this value pnorto performing scram time testing per SR 3 1.4 1.

2. The values shown are for dual recirculation loop operation (1 07 SLMCPR). Increase any value shown by 0 03 for Single Loop Operation (SLO SLMCPR=1 10)
3. EOR refers to the end of Full Power Capability at Rated Flow with normal Feedwater Heabng

TVA.Nuclear Fuel TVA-COLR-BF2C 12 Revision 2, Page 22 Core Operating Limits Report Figure 11 MCPR Operating Limit for All GEl1 and GE13 Bundles Optional for All Cycle Exposures -Required after EOR-2000 MWD/ST is reached (see note 3) 144 1 43 1 42 1 41 0 14 a 1 39 138 1 37 136 1 35 I .... - RTBOOS 134 0,. 1 0 3 0 5 0' 07 08 09° CJ 133 1 32 1 31 13 129 1 28 I I ~~Turbine Bypass and Recirculation Pump Trip tn-Srvc 0 0 1 27 Option B Optbon A Tau (r)

Exposure Range Out-Of-Service Option A (1) Option B Tau-l.0 Tau=O.0 BOC12 to EOC12 na 1.31 1.29 BOC12 to EOCI2 Turbine Bypass (TBOOS) 1.35 1.32 BOC12 to EOC12 Recirculation Pump Trip (RPTOOS) 1.40 1.32 BOC12 to EOC12 TBOOS and RPTOOS 1.43 1.35 Notes 1 Use this value pnor to performing scram time testing per SR 3.1.4 1.

2 The values shown are for dual recirculation loop operation (1.07 SLMCPR) Increase any value shown by 0 03 for Single Loop Operation (SLO.SLMCPR=1.10).

3 EOR refers to the end of Full Power Capability at Rated Flow with normal Feedwater Heating

TVA Nuclear Fuel TVA-COLR-BF2C 12 Revision 2, Page 23 Core Operating Limits Report Figure 12 I

Power Dependent MCPR(P) Limits 32 28 26 24 22 CL 0 2

18 16 14 12 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

OPERATING LIMIT MCPR(P) = Kp

For P < 26% NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED For 25% < P < Pbypass  : (Pbypass a 30%)

Kp - [Kbyp + 0.02(30%-P)]/OLMCPR(100)

Turbine Bypass and RPT In-Service, or RPT Out-Of-Service (RPTOOS)

Kbyp = 1.92 For < 50% CORE FLOW Kbyp = 2.15 For > 50% CORE FLOW Turbine Bypass Out-Of-ServIce (TBOOS)

Kbyp z 1.96 For < 50% CORE FLOW Kbyp a 2.93 For > 50% CORE FLOW For 30% < P<45%  : Kp = 1.28 + 0.01340(45%-P)

For 45% < P<60%  : Kp = 1.15 + 0.00867(60%-P)

For 60% < P  : Kp = 1.00 + 0.00375(100%-P)

Note: The OLMCPR below Pbypass is based upon the dual recirculation loop SLMCPR of 1.07. Add 0.03 to the OLMCPR in Single Loop Operation (SLO - SLMCPR=1.10).

TVA Nuclear Fuel TVA-COLR-BF2C 12 Core Operating Limits Report Revision 2, Page 24 (Final)

Figure 13 Flow Dependent MCPR Operating Limit - MCPR(F) 15 15 14 CL C.)

13 12 11 30 40 50 60 70 80 90 100 Core Flow (% Rated)

For Wc > 30%  : MCPR(F)= MAX(1.20, Af*WcIl00 + Bf)

Wc = % Rated Core Flow At and Bf are Constants Given Below:

Maximum

  • co* Flow Af Bf 102.5 -0571 1655 1070 -0586 1697 These values bound both Turbine Bypass In-Service and Out.Of-Service.

These values bound both Recirculation Pump Trip In-Service and Out-Of-Service The 102.5% maximum flow line is used for operation up to 100% rated flow.

The 107% maximum flow line is used for operation up to 105% rated flow (ICF).

This figure is based upon the dual recirculation loop operation SLMCPR of 1.07.

Add 0.03 to these values for Single Loop Operation (SLO - SLMCPR=I.10).

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