ML071070321
| ML071070321 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/06/2007 |
| From: | Crouch W Tennessee Valley Authority |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| TVA-COLR-BF1C7, Rev 1 | |
| Download: ML071070321 (35) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 6, 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 7 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is the Unit 1 Cycle 7, Revision 1, Core Operating Limits Report. Revision 1 is an update of the Unit 1 Cycle 7, Revision 0, COLR that was issued November 20, 2006, on an interim basis, to support fuel loading.
There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, William D. Crouch Manager of Licensing and Industry Affairs Enclosure cc: See page 2 D03c
U.S. Nuclear Regulatory Commission Page 2 April 6, 2007 Enclosure cc (Enclosure)
Mr. Malcolm T. Widman, 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 Ms. Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
A ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 CORE OPERATING LIMITS REPORT (COLR), REVISION 1 FOR CYCLE 7 OPERATION (SEE ATTACHED)
'TVA Nuclear Fuel QA Document TVA-COLR-BFIC7 Revision I, PageI Core
- t._a,g limit..s Reor_
Browns Ferry Nuclear Plant Unit I Cycle 7 CORE OPERATING LIMITS REPORT (COLR)
TENNESSEE VALLEY AUTHORITY Nuclear Fuel Design BWR Fuel Engineering Department Prepared B Date: 3*13,7 1rye C. Mitchell, Nuclear Engineer BWR Fuel Engineering Verified B Date: _./ o'3*"
Sco yKrpel, Nuclear Engineer BWR Fuel Engineering Approved B Date: 3 12 3 (cr7 Gy C. Stor* , Manag.r
ý.,VRýuelnginyerfl%
6 .-
Reviewed B Y:._ Date: .. / 4>.>, "-"/
... J. M. Keck, Supervisor Browns Ferry Reactor Engineering Approved B: Dale:
PORC Chairman Revision 103/28,12007) Pages Affected: All
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 2 Revision Log Revision Date Description Affected Pages 0 11/20/2006 Initial Release of Interim COLR (to All support Fuel Loading Only) 1 03/28/2007 Initial Release of COLR to support All operation at CLTP (3458 MWth) conditions Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF 1C7 Core Operating Limits Report Revision 1, Page 3
- 1. INTRODUCTION This Core Operating Limits Report (COLR) for Browns Ferry Nuclear Plant Unit 1 Cycle 7 is prepared in accordance with the requirements of Browns Ferry Technical Specification 5.6.5. This revision of the COLR supports operation at a licensed thermal power of 3458 MWt which is 105% of original licensed thermal power (OLTP).
The core operating limits presented here were developed using NRC-approved methods (Reference 1). The only exceptions to this involve the use of more conservative uncertainties to address emergent issues regarding the GE14 CPR correlation. These changes were explicitly described in the Unit 1 Cycle 7 SLMCPR submittal and are included in the reference 9 approval.
Results from the reload analyses for Browns Ferry Nuclear Plant Unit 1 Cycle 7 are documented in reference 2.
The following core operating and Technical Specification 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)
The Unit 1 Cycle 7 core is composed of Global Nuclear Fuel GE-13TM and GE-14TM assemblies. Throughout this document these are referred to as GE13 and GE14 with the trademark implied. Also, the generic reference to GE14 in this document refers to the GE14C fuel type specified in the SRLR (Reference 2).
Browns FerryNuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 4
- 2. APLHGR LIMIT (TECHNICAL SPECIFICATIONS 3.2.1 AND 3.7.5)
The APLHGR limit is determined by adjusting the rated power APLHGR limit for off-rated power, off-rated flow, and SLO conditions. The most limiting of these is then used as follows:
APLHGR limit = MIN (APLHGRp, APLHGRF, APLHGRsLo) where: APLHGRP off-rated power APLHGR limit [APLHGRRATED
- MAPFAC(P)]
APLHGRF off-rated flow APLHGR limit [APLHGRRATED
- MAPFAC(F)]
APLHGRSLO SLO APLHGR limit [APLHGR RATED
- SLOMultiplier]
Rated Power and Flow Limits: APLHGRRATED The APLHGR limits for full power and flow conditions for each type of fuel (i.e. product line) as a function of exposure are shown in Figures 1 and 2 (Reference 2).
Product Line Rated Power APLHGR Limit GEl3 Figure 1 GE14 Figre 2 Off-Rated Flow Corrections: APLHGRF The APLHGR limits are adjusted for off-rated flow conditions using the ARTS multiplier, MAPFAC(F). The APLHGR limits for the GE 13 and GE 14 fuel in the Unit 1 Cycle 7 core do not require reduction for off-rated power operation so these values are set to 1.0.
MAPFAC(F) is not product line dependent.
Product Line MAPFAC(F)
GEl3 & GE14 1.0 Off-Rated Power Corrections: APLHGRP The APLHGR limits are adjusted for off-rated power conditions using the ARTS multiplier, MAPFAC(P). The APLHGR limits for the GE13 and GEl4 fuel in the Unit 1 Cycle 7 core do not require reduction for off-rated power operation so these values are set to 1.0.
MAPFAC(P) is not product line dependent.
Product Line MAPFAC(P)
GEl3 & GEl4 1.0 Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 5 SLO Corrections: APLHGRSLO Single Recirculation Loop Operation (SLO) requires that the rated power APLHGR limit (APLHGRrated) be reduced by applying the following multipliers. The SLO multipliers are provided in reference 2.
Product Line SLO Multiplier GE13 0.87 GE14 0.93 Equipment Out-Of-Service (EOOS) Corrections:
The rated APLHGR limits in Figures 1 and 2 are applicable for operation with all equipment In-Service as well as the following Equipment Out-Of-Service (EOOS) options.
This includes combinations of these EOOS options.
In-Service All equipment In-Service (includes 1 SRVOOS)
RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service FHOOS (or FFTR) Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)
Single Recirculation Loop Operation (SLO) requires the application of the SLO multipliers to the rated APLHGR limits as described previously.
Browns FerryNuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 6
- 3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3)
The LHGR limit is determined by adjusting the rated power LHGR limit for off-rated power and off-rated flow conditions. The most limiting of these is then used, as follows:
LHGR limit = MIN (LHGRp , LHGRF, LHGRsLo )
where: LHGRp off-rated power LHGR limit [LHGRRATED
- LHGRFAC(P)]
LHGRF off-rated flow LHGR limit [LHGRRATED
- LHGRFAC(F)]
LHGRSLO SLO LHGR limit [LHGRRATED
- SLOMultiplier]
Rated Power and Flow Limits: LHGRRATED The LHGR limit is fuel type (i.e. product line) dependent. The limits for each of the product lines are given below:
Product Line Rated Power LHGR Limit GE13 Figure 3 GE14 Figure 4 Figures 3 and 4 provide the U0 2 LHGR limits. Separate limits apply to Gadolinia containing rods that are dependent upon the Gadolinia concentration. The limiting Gadolinia concentration limits for each Unit 1 Cycle 7 bundle design is provided in Reference 3.
Off-Rated Flow Corrections: LHGRF The LHGR limits are adjusted for off-rated flow conditions using the LHGRFAC(F) multiplier which is provided in Reference 4. LHGRFAC(F) is not product line dependent.
LHGRFAC(F) is not dependent upon specific equipment in-service assumptions.
Product Line LHGRFAC(F)
GEl3 & GEl4 Figure 5 Off-Rated Power Corrections: LHGRp The LHGR limits are adjusted for off-rated power conditions using the LHGRFAC(P) multiplier which is provided in Reference 4. The LHGRFAC(P) multiplier is dependent on whether the Turbine-Bypass Valve and Power-Load-Unbalance systems are in-service or out-of-service. LHGRFAC(P) is not product line dependent.
Product Line LHGRFAC(P)
GE13 & GE14 I See EOOS section Browns Ferry Nuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 7 SLO Corrections: LHGRsLo Single Recirculation Loop Operation (SLO) requires that the rated power LHGR limit (LHGRrated) be reduced by applying the following multipliers. The SLO multipliers are provided in reference 2.
Product Line SLO Multiplier GE13 0.87 GE14 0.93 Equipment Out-Of-Service (EOOS) Corrections:
The rated LHGR limits are applicable for operation with all Equipment In-Service (EIS) as well as the following Equipment Out-Of-Service (EOOS) options. This includes combinations of these EOOS options.
In-Service All equipment In-Service (includes 1 SRVOOS)
RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service PLUOOS Power Load Unbalance Out-Of-Service SLO Single Recirculation Loop Operation FHOOS (or FFTR) Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)
The off-rated power corrections [LHGRFAC(P)] in Figures 6 through 9 are dependent upon operation of the Turbine Bypass Valve and Power Load Unbalance systems. For this reason, separate limits are supplied in this figure to be applied for TBVOOS, PLUOOS, or combined TBVOOS/PLUOOS operation. The LHGRFAC(P) limits have no dependency on RPTOOS or FHOOS/FFTR.
EOOS Option
- LHGRFAC(P)
In-Service Figure 6 TBVOOS Figure 7 PLUOOS Figure 8 TBVOOS & PLUOOS Figure 9
- All LHGRFAC(P) limits support RPTOOS, SLO, and FHOOS/FFTR.
The off-rated flow corrections [LHGRFAC(F)] in Figure 5 bound both EIS or EOOS operation.
Browns Ferry Nuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF IC7 Core Operating Limits Report Revision 1, Page 8
- 4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4.1, AND 3.7.5)
The MCPR Operating Limit (OLMCPR) is calculated to be the most limiting of the flow-dependent MCPR (MCPRF) and power-dependent MCPR (MCPRp).
OLMCPR limit = MAX (MCPRF, MCPRp) where: MCPRE core flow-dependent MCPR limit MCPRp power-dependent MCPR limit Flow-Dependent MCPR Limits: MCPRF The MCPRF limits are dependent upon:
" Core Flow (% of Rated)
" Max Core Flow Limit (Rated or Increased Core Flow, ICF)
The MCPRF limits are provided in Figure 10. For Unit 1 Cycle 7 the MCPRF limits are not fuel type (i.e. product line) dependent. These limits are valid for all EOOS combinations.
No adjustment is required to the MCPRF limits for SLO. The MCPRF limits are found in Reference 4.
Power-Dependent MCPR Limits: MCPRp The MCPRP limits are dependent upon the power level in relation to Pbypass (30% rated power), as follows:
P > 30% (above Pbypass): MCPRp = Kp
- OLMCPR(100) (Figures 11-14)
P < 30% (below Pbypass): MCPRp = MCPR(P) (Figures 15-18)
Browns Ferry Nuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF 1C7 Core Operating Limits Report Revision 1, Page 9
- a. Rated Limits - OLMCPR(100): The MCPR Operating Limit for rated power and flow conditions, OLMCPR(100), is equal to the fuel type (i.e. product line) and exposure dependent limits shown in Figures 11 - 14, as defined in the following table:
Product Line Exposure Range OLMCPR(100)
- MOC is 1323 MWD/MTU (1200 MWD/ST) prior to EOR. EOR is defined as the end of full power capability at rated flow with normal feedwater temperature.
It is acceptable to use the more restrictive Figures 12 and 14 limits at any point in the cycle.
As noted in the footnotes of Figures 11 through 14, an adder of 0.02 is applied for single loop operation.
The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below (Reference 10):
T ave - TB
' = 0.0 or , whichever is greater TA TB where; TA = 1.096 sec (analytical Option A scram time limit - based on dropout time for notch position 36) n nTi i=l1 T'ave =
n TB +1.65*a*Li]l
+
where; p. = 0.830 sec (mean scram time used in transient analysis -
based on dropout time for notch position 36) a = 0.019 sec (standard deviation of p.)
N = Total number of active rods measured in Technical Specification Surveillance Requirement SR 3.1.4.1 n = Number of surveillance rod tests performed to date in cycle Ti = Scram time (dropout time) from fully withdrawn to notch position 36 for the it rod Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 10
- b. Startup Limits: Option A OLMCPR limits (T = 1.0) shall be used prior to the determination of TF in accordance with SR 3.1.4.1.
- c. Off-Rated Limits: For off-rated power conditions, power-adjusted [MCPR(P)]
operating limits are determined from Figures 15 through 18 depending on the equipment out-of-service conditions. The MCPR(P) curve above Pbypass (30% rated power) is a multiplier to be applied to the OLMCPR(100) limit. The MCPR(P) curve below Pbypass are OLMCPR values to be used directly.
In-Service All equipment In-Service (includes 1 SRVOOS)
- RPTOOS EOC-Recirculation Pump Trip Out-Of-Service TBVOOS Turbine Bypass Valve(s) Out-Of-Service RPTOOS+TBVOOS Combined RPTOOS and TBVOOS PLUOOS Power Load Unbalance Out-Of-Service PLUOOS+RPTOOS Combined PLUOOS and RPTOOS PLUOOS+TBVOOS Combined PLUOOS and TBVOOS PLUOOS+TBVOOS+RPTOOS Combined PLUOOS, RPTOOS, and TBVOOS SLO Single Recirculation Loop Operation (see below)
- Feedwater Heaters Out-Of-Service (or Final Feedwater Temperature Reduction)
- All limits include l-SRVOOS and FHOOS/FFTR.
- e. Single-Loop Operation: The MCPRp limits for SLO are to be increased by 0.02 (Reference 2).
Browns Ferry NuclearPlant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 11
- 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 (Reference 6):
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)
W= 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%).
Browns Ferry NuclearPlant Unit I Cycle 7
I-TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 12
- 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. 6 & 7):
RBM Trip Setpoint Allowable Value Nominal Trip Setpoint
LPSP 27% 25%
IPSP 62% 60%
HPSP 82% 80%
LTSP - unfiltered 124.7% 123.0% (1),(2)
- filtered 123.5% 121.8%
ITSP - unfiltered 119.7% 118.0% (1),(2)
- filtered 118.7% 117.0%
HTSP - unfiltered 114.7% 113.0% (1),(2)
- filtered 113.7% 112.0%
DTSP 90% 92%
Notes: (1) These setpoints are based upon an Analytical Limit HTSP of 117% (w/o filter) which corresponds to a MCPR operating limit of 1.38(GE13/GE14), as reported in section 11 of Reference 2. Unit 1 Cycle 7 has had a cycle specific CRWE analysis performed and the table provided in section I1 page 38 of Reference 2 supercedes the OLMCPR values of references 6 and 8.
(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 6.b). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (Reference 6.a).
The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:
THERMAL POWER Applicable Notes from
(% Rated) MCPR ") Table 3.3.2.1-1
> 27% and < 90% < 1.70 (a), (b), (f), (h) dual loop operation
< 1.74 (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 1.09 for dual recirculation loop operation and 1.11 for single loop operation. (Reference 2, Appendix C).
(2) Greater than 90% rated power is not attainable in single loop operation.
Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 13
- 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 (Reference 5).
SDM > 0.38% dk/k Browns Ferry Nuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 14
- 8. REFERENCES
- 1. Global Nuclear Fuel Analytical Methodology
References:
a) NEDE-24011-P-A-15, "General Electric Standard Application for Reactor Fuel",
September 2005.
b) NEDE-24011-P-A-15-US, "General Electric Standard Application for Reactor Fuel (Supplement for United States)", September 2005.
- 2. 0000-0044-1520-SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry 1 Reload 6 Cycle 7", dated January 2007. [L32 070129 800]
- 3. 0000-0043-8325-FBIR Rev. 0, "Fuel Bundle Information Report for Browns Ferry 1 Reload 6 Cycle 7", dated May 2006. [L32 060512 800]
- 4. GE-NE-0000-0060-4817-RO, "Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Reload 6 / Cycle 7 Off-Rated Limits Validation at a Rated Thermal Power of 3458 MWt", dated January 2007. [L32 070129 803]
- 5. Browns Ferry Unit 1 Custom (pre-ITS) Technical Specification Section 4.3.A.1, "Reactivity margin core loading".
- 6. PRNM Setpoint Calculation:
a) FilteredSetpoints - 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.
b) Unfiltered Setpoints - 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.
- 7. GE Letter LB#: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.
- 8. 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.
- 9. NRC letter to Karl W. Singer, "Browns Ferry Nuclear Plant, Unit 1 - Issuance of Amendment Regarding Cycle-Specific Safety Limit Minimum Critical Power Ratio (TAC No. MD1721) (TS-455)", dated February 6, 2007.
Browns Ferry NuclearPlant Unit I Cycle 7
STVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 15 Fi.gure1 APLIGR Lhnits for iall GE 13Fuel
.......... *(2 13)
A' AZ
'3
=
-J A.
4 0.00 10.00 20.00 30.00 40.00::ý ::5G.0 60.00 70.00 Average Plnani Expos uie (FGWD oITU i Average:Planar Aver..ag:e LHGR....... :Planar (GWDiMTU: : GWD:;ST) (kwift:
0.00 0.00132 21 74 --- -- -- 19.72134 30.00 27.22:: A :1:2.29::::
... . ... ...... ~~~~~~. . ....... . . . . ... . .. . . .. . .. . .. . .. ..... . . . . . . . .
7000.........3:.0.8.9
- These rated power'valu~es apply to all equipmenit in-se~rvice andif out-f-service coniditions except
.for Single
- . . . , . . Loop . . . .. Operiatien
. . . . . . . ....($0L1). .SICadjustmients .. . .. arre:performed . . . . as . described
...... . ... hi Sectioln*.
Browns Ferry Nuclear Plant Unit 1 Cycle 7
4.
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 16 ALXPLHGR Limit~s for Al GEI4 Fuel.
(CR,14) 14.00:
11300: 4 jUNACCEPTABLE . O PE.RIATION[V 12.
11.0 I0
.10.0Q
- 9.0 o0:::::: ::: :: : ..:: . i i i ?:::)i'~ ~ii~i i ? ? ! : ..... ...
... . ........ : .. .?i i 8.0 r6 7:.
30 - -------
5.0030.................................... -..--. ..-..
Jo
.4.0 .... _.. ....
JO ' :.." .. "" " " '. . '
- 3.0
. . .. ~.. . .. . . .. . =. . . . . . . . ...
j:.O
- ::.?II'I
.1 '.).*::..*.::........... .**?j ..
- .*.j.-t :-.
0.00 10.00 20.00:: 30.00 40.00 50.00 60.00 70.00 Average Ptanai Expos-ure (GWDMII.TU)
Average Planiar Average Plmar ... !LHGR Exposuire ExPosue : imit IGWDS.i'MTV) IGWDS (kwift:
0.00 ... 0.. ....
0 ............
12..
21.09 .1913 18 63.50 57.61 8::ý.00 70.00 63.50 .800 Th..eserated power valuies apply to all eup nti-rvcado-fsric oditionts ex-ept for Single:Loo~p Ope~ration (SLO). SLOdutet r efre a ecie nScin2 Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 17 LHGR Limits for aill:GE.-U3Ftwul (CR13)
"J1, 15.00 ..........
.ý --- 7 ----------
14.00:. .7....... ....... .........
I ...........
13.00d .......... ONACCIEPTABLEE.:OPERATON 12.00:. ............. ...... ...... .............
ttt7 11.00 A
9.00 ....................... ....... .................
I i...,JACCEP!TAB LE::OP.ERATIONJ. .........
7.00: -. . . .. . . S... . . . ;. . . . .
7-7-!...........
0; 4~
=
-J 5.00 3.:00:
2.00 i . .- i i >
.i> T > .. ! i - ! 7 - II I .1-.-..-i I III ?- > I . . ' - !.7.1-i .7->.-.-
1.00.
0.00:::84 ..o.
10.00 20.00 30.:00:: * :: :::::.40.00 o50.00 68000' :: 70.00
... Pellet Exp~osure:(GWVD.MTU)
Pellet .. Pellet:::: ::U.02 LHGR.
Expouf e Expoure LHG'R LihW (G#WDI"MTU): (GWD)ISTI: IkW~ft 0 .00: ()000:::: 14.4
ý:300022212 70 00 635.60 .790 These raited power valules3 ppyoaleumnti-seivce and out-of-servce conditions except frSingle Loop Operation:(SLO). SLO adjustmfents are perforrued ais describedrin'Sectionl 3.
These ar h ausfor thellU0 fuel rods. Referenefce 3 contains limitiing:Gadolinia LHGR limits for1 each Unit 1Cycle 7 bunidle with Gadolinia continingt rods.
Browns Ferry NuclearPlant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF 1C7 Core Operating Limits Report Revision 1, Page 18
. . ... .. .... .. :Fig r
.. . . . . .. . . i,. . .....
LHGR9 ,imits ~fo.r ~il GE-14 Fui*.
(GF,14) 15.00 14.00 13.00
.4 . . . .. . .. .....
12.00 11 .00 10.00 ACCEPTABLE OPERATIONTO g.9..001 S... . ....
.00
-l7.00 ii~
iiiiii***
- !*! i*!!! i i iiii i i i.
i i***
...........*i~
. I ... .. ... . ... ... . ..:... . :.. .. .... . .. .. ...
ii~ii< .I
........**i < < .. . . . . . ..... .
Z 6.00 ...
..--i -
iiiiiii.
i":':::'::'::':' :'::÷:**:**:'::':i':'::'::*:**:*::* 'i~ii~i~~i÷?~i~ii~ii~i~~i~ii~i~~i~'i*:ii > >>:*
5.00 S@~ii~iiiiiiiii~ii PTABL EOPERATION i~ ii~iiiiiiii~iiO ........
4.00 -:
.............. fA CCE .......
!:*i~~iiiii~~i~~i!?1:*!?
....... iii~ii~~iiK ; :: S:;;; :?
3.00 2.00 1 .00 0.00 0.00 10.00 20.00 30.00 40.00 50.00... ++.....50.00 70.00 Pellet Expostire (r.VD..TU)
Pellet Pellet U02LHGRe Exposine EXpsuie LHGRI Limiti
- GWD.
- DMTU)
(GWD'fST) tkwtftV 0.00 0.001340::::::: : :::: 13.4 14.05 14:.40:
63.50 57.61 80 70.00 63.50 5.00 These rated: poWe, values apply to all equipment in-service Arnd out-of-service conditionls except:
for ýSindfle L.ýoop Opertion (SLO).:510 adutm tsaeeroedsdsrieinScin.
Thesear~e the values for the U02 fuelrods. Reerence 3 containsIiiitingjGado!inia LHGRimits ixe Unit I Cycle 7 bundle with G*adolinia conlainin *r:ods.
Browns Ferry Nuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BFIC7 Core Operating Limits Report Revision 1, Page 19
.. ....Figu e*.5 Flow Dependent LHGR Factor- :*LHGRAC(F)!
(GE13/GE14) 1.00 0.90 0.80 ix a;l:
0.70 0,.60::.
30 40 .50: 60 708 0100 Core Flow %Rtd Max:Core Flow 102.5% Rate.d Coe
- Fo*w LHGRFAC(F).
Equations 30 0.69 LHGRFAC (F)MIN(1.0, [A(F) t W(C)/1 00+6(F)])
75.3 1 00 A(F) 06784 0:
102.5 1.00 B(F)=ýý0.4861 Max :Core Flow 107%: Rated coeflow Core.......LHGRFAC(F)
(%rated) .________
30:
107~i 0.66 1.00oiii~!!!:::::::::
- :LHGRFAC(F) =MiN(1 .0, [A(F) tW(C)/1 00+8(F)])
A(F) =-:0.67583 60.31.00:
B(F) = 0.4574 These off-iated flow corrections :apply to all equipment in-service:mad out-of-service conditions.
The 102.5*%maximumn flow fline is used for operation up to 100% rated flo:w.
The 107%I:7ý-
- axitmum
- : : : ::: : ::: :is
- : :::: : ::flow:linie ::used
.:.: : : ::operiation:
- :: :::for :.
- . ..: up
- .::.. : : : ::::rated
- ::: : :::o5 flow (I: : ::: : : :::: : ::: :: ::::.: : : : : ::
Browns Ferry Nuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 20
- ,. h, h. ,h, ,/, , * / * .. . . ....... . . h .. . . . . . .i ..* . . * , , . . . . .. . . . . .
Power Dependeint LI-I:R Mulliplr: LHRFACI*P)
Equipment .I-Sel~ice or RPTOOS (G
- E14. . . ..
1.100
=~iiii~
'-0700
-I* ::iii 25 30 35 40 45 50 655 60 66: 70 75 80 .8: 9 :95
- 6100 paiwer %fwated~
Equipicment: . .iii.i.:..:.
r ..In-Service or:.:i.~ RPTOOS.
core Power 1LGF~P : ::::
LU~n
- : : : : ::: : : : : : : :: : : ::3: : ::: : ::.. : : : :: : : :: : : : :: : : ::.: : : : : : ::.: :
5: :: ::: ::::: : : : : : : : : ::
0 0: : :: :: ::* : :' :::1 100:1:00 ::For 30 0% <= P <:50 0% LHGRFAC(P) = 0 688 +3 68E-03(P-.50):
- 50::: 0:739: For5O.:0%:P<100.0%: LHGIRFAC(PY O1.0006+5.224E-03(P-100.00 EquatioM:
For 25.0% <= P < 30.0%: LHGRFAC(P) 0.460 + 6,33E.03(P-30.0):
For 25.0% <=P <30 0% LHGRFAC(P) &.538 +1IOOE-03(P-30.0)
Browns Ferry Nuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 21 Fi ur 74:....
PoWer Depeiiiidet LUOGR Mutiplioer - LIIGRFACTIP
....... an R TOOS
.. GE..4
,41' iiSi
-J~i 25:3 36 3570
- 35 :: 45:5 55 50 55 ,. 75 80 85 90 95 100
.Power.......d...
TBVOOS:an d:RPTOOS Core t. rate Power S,(%: ratW4i ::,I LHGRFAC P): Eq~uations:
100 1000 F..1r3O0% <P:<50:0% LHGRFAC(P) = 0 688 + 3 68E-03(P-50.0) 50 : 0739 For50,0% a P: 100.0%: LHGRFAC(P) = 1.000 +5.224E-03(P-100.0) 50 , 7 0:688 30 : 06.14
.CoeFlow 50 rated. ..
.30 A ::::0:37:!:::::::: For:25.0% a=:P < 30.0%: LHGRFAC(P) 0.371 +1.13E-02(P-30.0)
Core Flow.: 56%= rated=4:==
- ::: 30 :::::I: :m: :ý4::::::: : : :: : F2S%:::Eqilai0
- P:-<30:0%::::: LHGRFAC(P) = 0549 +1 53E-02(P-30.0)
'. / ' / / / / / ./ . ,. .. ....... ,... ,....
, -. . -* -* * . / . , . . . . ..... . . .,..
,I . . ., . . . . .,. .
Browns Ferry NuclearPlant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BFl C7 Core Operating Limits Report Revision 1, Page 22 Figure 8 Power Dependent LIIGR Muhtiplier - LHGRFACI.P)
PLUQOS and RIPTOOS (GEl 3GE 14) 040 03500
- i ~0 300:
50 60 66 Pawmet (% FPAted)
PLU: OS:andR:PTOOS For:30.%:<= P < 60 0%: LHGRFAC(P) = 0 725 + 3 68E-03(P-60.0)::
For 60.0% <ý P <70.0%: LHGRFAC(P) = 0643 + 1.18E-,02(P-703
.For:70.0%,<-' P < 100,0%: LHGRFAC(P) =1 000 + 5 224E-03P-100.0).
- Eqqations........:
LHGRFAC(P) 0.460 + 6.33E.03(P-30.f3)
For 2*.0% <= P <30 0% LHGRFAC(P) &50.38 + 1 OOE-03(P-30.0)
Browns Ferry Nuclear Plant Unit I Cycle 7
- . t
- i I.
TVA Nuclear Fuel TVA-COLR-BF IC7 Core Operating Limits Report Revision 1, Page 23 Power D.pei.deiLHplT* i..PLmidP.er' LIGRFACP)
TB'VOOS. PLITOOS. Amd RTOO.S:
3...14 ......
4
'A-
-J 25::30 : 35::: 40 4: SI) 55 60: 55 75 80 .85 90 95::: 100*
p6i me i t%Alte TBVOOSPI*UOOS, aind RPTOOS
- :::Loe P r LH* RFACtPi : E aulikmis:
100 000 For M00% <= P <60,0% LHGRFAC(P) = 0 72Y+ 3 68E-03(P-60 0)
For 600.10% 5" P.<70.0%: LHGRFAC(P) = 0.843 + 1.18E-02(P+70.0)
For 700 < 100% LHGRFAC(P) = 1:000 + 6 224E-0mp*i-o1o0)
IP For 25,0% t=P,<30.0%: LHGRFAC(P) = 0.371 + 1.13E-02(P-30.0) ton*.......
For 250%:<=P < 30 0%~: LHGRFAC(P) =0.549 + 1 53E-02(P-M0.)
Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 24
- Flow! Depeniden~t:*! MCPR: :Lhmit :-i MClP R(F~i i iiiiii iiiiii (021i* i3/0214) iiiiiiiiiiiiiiiiiiiii 1.55 1 45 S1 40
- .MAX FLOW F107%
MAX FLOW F . .. .
- 1 .30 1 25 30 40 50 60 70 80 90 100 Care Flow (%,Rated')
Max*Core Flow 102.5,%: Rated
- Core Flow MCRF S ra... .ted) _. . . . . . . : U ju~::E iatioins:::iiiiiiiii!
MCPR(F) MAXL7I.30,. [A(F)-(C)/I,00 +0.(F)])
A(F) 7-0.:582 B(F). 1.686 I
- Maxx Core Flow 107%::Rated 4orerated)%j Flow r___d)_____ MPRF 1.535: MCPR(F) -=MAX(1I.30, [A(F)*WV(C)/100+0 (F)])
- 71:.9
. B(F)= 1.729 These 6off-ated flow corrections apply to: all: equipmnen t in-servce and oiut-of-service coniditions.
ýThe10M2*.5%maximu flow:lineis used for operation up, to 100% rated flow.
The.107%; maximum flow line is11sed5forSioeration up to 105%:rated::flow:(ICF):.
i i iii i iii i i~i i iii i iii i~i ii iii i iiii i iii i iii i iii iiii i iii.
i iiiiiii~ i.ii..i.i.
ii.i. i~i iiii ii~i iii i iii i ii!..
i.~~ii Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF IC7 Core Operating Limits Report Revision 1, Page 25
............ Figure IiM MCPR Operuthig Ulnit for All 0E131Bundles BOG' to, MOG EOR-1,32-3 MX)MU[e . oe 1 .46 1..45 1 .44
- 1. 43.,i-
.1!!ii* ! . RPTOOS ....o.*... . . .
APTOOS."*i'.i. . . . i . i i i i i'i i PIJIODS, 9 TOIVOOS i i i . ..ii
. .. . ...: ' .: . ,v.
.1 .42 1 .44 .......
..... ... .. .. .. .. .. .. . .. .. ..'.7.7 >...- .. .. ......... : . ...
_ _ _ _ice:_.._......
- . 1.40i~0
....................... . . .~... . ..............== .==
..==.==
... == == ====
<139::
1.
.1 >
37.-..:>
- 0.1 0.6 0.7 .:0.8 0.9s 0.333 0.428 Option A Option B
. ...... . T u (r)
Notes
- 1. Use týis8valueprior to performing scram time testingper:SR 3.1.4.1.:
- 2. The values shown are for dual recirc*ua.tnl*o peration (1.09 SLMCPR). Irncease any value shown by 0102foriSingleSgLo~op:Operation (SLO:SLMCPR1.=i1:1)i...... i.......
- 3. EOR refiers t1otheend of Full Power Capability :at:Rated Flow withi normal Feedwater Heating.
4 All limits sUpp0ort !:SRYVOOSanid lFHbOOS/FFTlRlR. ...........
Browns FerryNuclear Plant Unit I Cycle 7
.4 . --
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 26 Figure 1-2 AMCPR Operathin.Limit for A-UAGE13 Bundles BOG to vO ...see no1e "31
.1.54
.. ' . .. +. .:. .'b . . . . +. :
. .+. +. '.'. . . . . . .: .';.........................
- .' ;-;i -;-; ; ; ; -;+;
- ,; ; ; ; ; ; ;.; :': ;... ..-
1 .53 1 .52 1 .48
~114 1.47 ....... I..... 0....... -*.-"-..
~
-:: . .T.B ~ .:... O --PL0.S i.:.;::;; a V- O-O S .:i: :* : ": "*: : ' -;;:''"""' "-; '""' --
.61.46 ;; ;,* :**; [";: : :; : :: [ '; i' ' -: :i -: : ;- ; ; ;:.:'Y :' ': : : -; - : ; '; ;' : :0: 0: -;0 :-17'-IP'T :: : :: :: : :: :: : :: :: : :: :: :
g1 .45: ...: -... - - -: , , : *; -~z
..; -:*:;:. - - -: : : : - - - -L + . . .: : : : : : : : - - - .: : : : - ..............
- -.... - : : -: : .: : i : . i ===
.!.+ = = == === == = = == = ==
nww.
1.44 A 1 .42ý 1.4 1 .41
.1.40 1.39 1.38 1 .37 0.1 0.7 0.8
- 0:.9:
0 0.2 ::::: : 0.3 04 0.5 0.6 Option B Option A Tau (r) 4UIIjI I IIti III-,-eI YrU " 4:..43 .
.. :Rbteirclation PumpbTrip (RPTOOS) :1.:50 :::: ii : :::::1.:39:
Turbine:::::::::ypass::::::(:TBVOOS :::)~
1.i~43:::::: ::::::1.:40:
to:EOC Power:Load: Unbalance :(PLUOOS)::::: 1:~i0 n :: : :1:3R:P 1 39 4ý50:::ý::ý
- 1:54 : :::: 1t::43::
)C:to EOC Combined RPTOOS:and TBVOOS::::: 1 43 K-ii~~ :to EOC Combined: RPTOOS, PLUOOS,ý and:TBVOOS 4ý54:::
1i: 4
ý:
I::::: i143:1 43 t6t:ý:ý Notes
- 1. Use this Value prior to. perform*i n*g. sctram time testin~g per SR 3141 2:The values shown are for dul recirciaulation loopi:(operiation (1.09:SLMCPR). Increas e any: value shown by0.022 for Single iLoop operation (SLO:SLMCPR.1,i).
- 3. These IHmits may be appl*dlat. any exposure: point: inthe cycle.
4, All limits:support.I :SRVOOS an d: FHOOS/FFTRR:.: :i%
Browns Ferry NuclearPlant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF 1C7 Core Operating Limits Report Revision 1, Page 27 Figure 1* .
MCPR Oper-ating Limift for All GEN- Btuidles BOC to MOC' iEOR -1323 lNVDlVWMTU! [seenoe]
1::I.58 1.57 1.56
- ! .* -:-:.--.:-:-:B* O$ -*:-:-:-:-: : : * ...': .. :.. ......... . .......................' .: ,"
1 .54 " ' "" -..........
...... .. ... .7 ' '.
................. ' ... ... .7 -7, . . *. .. ....
- W 1 .53
. ........... ........... . .' . " -" .-. ... . . 7 .. . . .. . .
0 1.52 C . " ". ' .: ...'.'.'.'. '..
1 .51 1.50
- 1.49 O S.. ........i........ ....
1 .48 1*1.47 & TSV 0 ... .... . .
j4 1.46 C1.45
?: , ?!?* ? !J-! ?! . *; J* ? * - ? * - 1 2-? 2-':. " ? ? ? ? ? ? : : .- '.. ....... - -.-.. .. ::
... .... -......: - ` g .. . . . -
- 1.4 1.42ý 1.ý41 1 .40 1.38 1.38
- 0:.4
.0.... ...
... ..!i
- !O . .. . . . . . . . .:0.64
.... 0.7:
ii: .~ii:::!0.!:
- !.!.i~ ..: :Option A:
option B Ta (:t:
Notes
- 1. Use this value prior to performing: scrami time: testing per SR 3.1.4.1 .
- 2. The values shown are: fori dual:r:ecircuiation: lo op: ope rati'on i(1.0IO9 SLMCPR). Increase any value shown by 0.02 for Single LoopOperation (SLO:SLMCPRW11. 11)
- 3. EOR:refers :to :the endl of Full Power Csapability at ted Flo* with: normal Feedwater Heating.
4.: Alllimits: isuppqort 1:!:: SRV.OOSa :lnd :FHOOS/FFTRR :............ ....... .......
Browns Ferry Nuclear Plant Unit 1 Cycle 7
- ,-,.; ,::..; I,` ,;*'
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 28 S . . . . . . . . , , ,. ., ... .. . .. .,.... . . . . .. -. . .. . I..... . . . .. . . . ./ . . * *.. . . , , , , * * . . . . . . . . , . . .
MCPR OperatingLimit.for AU0GE14 lBiufles BOC to EQO1 [see note 3]
1 .67 1 66
.'" * . .* ..... ... ... * * *` *................* ... . ....... ' " , "' ' " " " '" " "
1.64 1.63
.1 62
- 1.:6 . . ..--
ii:*;F --:*:* *;*:'
APTOOS,
- ~~ ~ '* -:. : &
PLUQOS, ~ . TOVOOS: ~ ~
. . . i. . "-
~
~
,-1 .64
- 1:-53::
o1 .52 1 64 ...... RPTOOS or ruooT 0:1.63 1 452
. 1 1:4:::
3:
1 .62
.40~i
- 1 1.41 1 46 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 Option A Option B ..... ..... :iii~~iii**
...... .... ~~ii~::ii .6:iii~~~ii
- ii~~~iii~ . ..... ~~~~ii :~iiii~~*
.... Tau (-)
Notes............. .... ..
1:Useethis value: prior to performingi scram timet*esting per: SR 3.1.4.1:
- 2. The valUes ishown are for dual recic ulati0h loop oýperationi :(.o.09 SLMCPR).i ncrease ia:ny value shown:
by 0.02 fo Sinige Loop.Operation (SLO:SLMCPR#1.11).
- 3. These, limits may be applied at any exposre.point. *nthe cycle.
4.: All limits: suppoirt SRVOOSand FHOOS/FFTRR. ::
Browns FerryNuclear Plant Unit I Cycle 7
4 ..
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 29 Fig r 15.....
Power Depelident M{CTR Ep - :K MCPR(P)
.EquipmentIm-Sei.ee.or RPTOOS
.(GEl3/GE 14)
.suuu - ---- __
2.700 ------....
- 2. ----0. . . .,80 ... ...-- -- ------ ...... ....
220 . ... .
~ o...F.ow .....
21..
z 2 Z 19300
.0.. ...... ......
- 1. 00..
1 .600 i
!'i11!]!]!]'i
!i!!!!!!!!!!
1 500 1 400 1 300
- !iiiiii'ii*'q -- --- .~~~iii
..iiiii 1 200 1 100 1 000 45 85 90. 95 100 25:. 30 35 40 50 55 150:
wer ii~ ~ii °:~ ~iiir75 ii~~80 i 65: ::::70
~~s*
E qui... m.. t - S ................
!Equipmentiln-Servici:6eirRPP'OOS
__________- at and above Pypass (30% Power)
For 30.0% <= P < 50.0%: Kp(P) = 1.384 + :.38E-03(5O0l-P)
For 50.0% - P < 60.0%: Kp (P) = 1.150 +0.67 E-G3(0.0- P)
For 60.0% <= P < 100.0%: Kp(P)-= 1.000 +o3.75E-03(100.0-P) rePow" :::ri:MCPR(p)
EgiUtio*i-: below PiYpass (30% Power) o Fl: : rated::::
ý:. '0% Four25.0% :<: P:: 30.0%:;: MCPR(P):# 2.64 + 3.67,E.-02(300&P):
c~ure Flow.: 50!-',aed Fur 25.0% < 7P : 3P300%;:: M:CPR(P):2 +1.OOE-02(30.0-P):
- 5 Browns Ferry NuclearPlant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 30 Figure 16 Power Dependent MCPR - Kp / MCPR(P)
TBVOOS and RPTOOS (GE13/GE14) 4.200 ............ -------------------
4.000 -------------- :.............
3.800 ------- --- ------------ ------------------------- ------------ ....................
3.600 ---------- ---------- ......... -----------
50% Core Flow
l ...........
3.400 --------------- --------.............. ..... ----------- ...... -- ---- .............
3.200 ------------ ............ ------------ ---------
3.000 2.8Wo
- 2600-2 400 ------------
150%C.ý Flow I--------------
2.200 ------------............ .............................
2.000 ............ ..---------........ ------------ ------------- ------------------
1.800 ---------------------------------------............-----------------------------------------
-1 1.600 ........... . .... ..................... .............
1.400 ------------- ........... I----
1.200 ---------------------------- ------------ ----------- ------------ .............
1.000 L 25 30 35 40 445 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)
TBVOOS and/or RPTOOS Equations: at and above Pypass (30% Power)
For 30.0% <= P < 50.0%: Kp(P) = 1.384 + 8.38E-03(50.0-P)
For 50.0% <= P < 60.0%: Kp(P) = 1.150 + 8.67E-03(60.0-P)
For 60.0% < P < 100.0%: Kp(P) = 1.000 + 3.75E-03(100.0-P)
Power (% I Core rated) MCPR(P)
CRP Equations: below Pypass (30% Power)
Core Flow > 50% rated 30 3.55 For 25.0% < P < 30.0%: MCPR(P) = 3.55 + 1.47E-01(30.0-P) 25 4.29 Core Flow < 50% rated 30 I 2.63 For 25.0% < P < 30.0%: MCPR(P) = 2.63 + 8.67E-02(30.0-P) 25 1 3.06 Browns FerryNuclear Plant Unit I Cycle 7
TVA Nuclear Fuel TVA-COLR-BF 1C7 Core Operating Limits Report Revision 1, Page 31 Figure 17 Power Dependent MCPR - Kp / MCPR(P)
PLUOOS and RPTOOS (GE13/GE14) 3.000
............ - ............ ............I---------------I------------ --------- ............. ..........
2.900 2.800
..............i......!.
-T.. i.-.-.-. .--. -......
2.700 ------------- ------------- ------------ ------------ --------------------------- ............ ------------ ------- I-----------
2.600 2.500
L............
2.400 ------------------------- ------------ ............ ------------------------- -------------------------- ------------ ----------
- i------- .... ------- --------------------------- ------------ ------------ --------------------------............
2.300 2.200 ------------ .......... ....... ....... ......I-------- -------- ............4------------ ------------ ----------
50% Core Flo.
. 2.100 --------------- --- ........ ....... ----------------- -------------- ------------ ........... - -- - - - - - - - - - ---- - - -- - - - - - - ---- - - - - -- - - -
U 2.000 ............ ------ ------- ......... ------------- ------------ ............ .............. ..........
1.900 1.700 ------------ ........................... ............. ------------------------- -- -------------- ------------ ------------ -----------
1.600 ............ -------------------------- ----------- --------------------------:-------------I------------- ------------ ----------
1.500 ----------- - --------------------------- ............ ------------ ------------I-------------- ---- --------------------- -----------
1.400 ------------ ........... ------------ ...... ........ - ----------- - ------ -------------- ---- --------------------- ----------
1.300 ---------------------- ..... ............ ----------- ------------ ------------------------- --------------
1.200 -------------------------- -------- ..... ...... -------------------
1.100 . ........... ............ ............................ ... ....... ............4....... ......-------- ---
1.000 25 30 35 40 45 75 80 85 90 95 100 50 55 60 65 70 Power (% Rated)
PLUOOS andlor RPTOOS Equations: at and above Pypass (30% Power)
For 30.0% < P < 60.0%: Kp(P) = 1.300 + 8.38E-03(60.0-P)
For 60.0% <= P < 70.0%: Kp(P) = 1.150 + 1.50E-02(70.0-P)
For 70.0% < P < 100.0%: Kp(P) = 1.000 + 5.OOE-03(1 00.0-P)
Core Power (% MCRP Equations: below Pypass (30% Power) rated) I Core Flow > 50% rated 30 F 2.64 For 25.0% < P < 30.0%: MCPR(P) = 2.64 + 3.67E-02(30.0-P) 25 2.82 Core Flow <50%rated 30 t 2.1 For 25.0% <= P < 30.0%: MCPR(P) = 2.15 + 1.OOE-02(30.0-P) 25 22 Browns FerryNuclear Plant Unit 1 Cycle 7
TVA Nuclear Fuel TVA-COLR-BF1C7 Core Operating Limits Report Revision 1, Page 32 (Final)
Power DepeUdent A .CPR
- Kp MCPR( O : ::::
PLITOOS. TBVOOS. ind RiPTOOS (GEl 31GB14) 4,200 000 ..
- 3800 3,600 3 400 3 200 3 000
~'2.800 S2.600ý S2.400 2.200 2.000 1800 1.600, 1.400 I 200 1 000 60 65 70
~ ate d)
Poe PLUOOS,.TBVOQS,.atnd RP.TOOS:::... *.*.
- : we: .iEuatienlf:.:
.. :at and above6Pypass (30% Power) 100: : 1:000 For:..
O: <=P:<60 Oh Kp(1) 1300 :+8.3BE-0 (603 P) 70 :1.150 For:60 70 0%P<700KP(P)150.0E0(.0P
.. ::300.F.r.70..:::-:P::
-/&2 .... ... 100
..55 Kp() .........15 I:OE.Io2(7000-P)0 15000 COre: Power ~CRR below Pylpess (30% Power)
C::(ore: Flow. >50W rate&d 30 3.55 For:25.0% <: P <30.0%. MCPR(P) =: 355 +1 .47E-O1 (30.0-P) 25 4.29 Core Flowe50% rated
-30`, j 2.63 For 25.0% <= P < 30.0%: MCPR(P) = 263 :+8.67E-02(30.0-P)
Browns FerryNuclear Plant Unit 1 Cycle 7