ML030920378

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Unit 2 - Core Operating Limits Report (Colr), for Cycle 13 Operation
ML030920378
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 04/01/2003
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF2C13
Download: ML030920378 (33)
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Text

Tennessee Valley Authority, Post Cffice 80x 2OOC Gecax~ AlaDama 35609.2009 April 1, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of 1 Docket No. 50-260 Tennessee Valley Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 - CORE OPERATING LIMITS REPORT (COLR) , FOR CYCLE 13 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is Revision 0 of the Unit 2 Cycle 13, Core Operating Limits Report (COLR).

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

Sincerely, Mana_qcjr__af-kic nsing

,.--and Industry ffairs

,.=

Enclosure EC: See page t

U.S. Nuclear Regulatory Commission Page 2 April 1, 2003 Enclosure cc (Enclosure):

Mr. Stephen J. Cahill, 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),

FOR CYCLE 13 OPERATION (SEE ATTACHED)

TVA Nuclear Fuel QA Document I

TVA-COLR-BF2 C 13 Core Operating Limits Report Revision 0, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 13 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date: 2 63 Verified By: Y  ? Date: 2 b/o 3 Alan L. Bruce, Nuclear Engineer I BWR Fuel Engineering Approved By: Date: z/zc/a?

&- James F. Lemons, Manager BWR Fuel Engineering Reviewed By: Date: 2b 7/03

-52%&r Browns Ferry ieactor Engineering Reviewed By: Date: @f@ 3 Revision 0 (2/26/2003) Initial Issue Pages Affected: All

TVA Nuclear Fuel TVA-COLR-BFZC L 3 Core Operating Limits Report Revision 0, Page 2 Revision Log Revision Q& Descrbtion Affected Panes 0 212612003 Initial Release for New Cycle All

TVA Nuclear Fuel TVA-COLR-BFX L 3 Core Operating Limits Report Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 13 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). One exception to this is an issue with the assumed uncertainty for the GEXL14 CPR correlation. The NRC has identified that the correlation lacked top-peaked axial power shape data in its formulation and in the calculation of the overall correlation uncertainty. As a long term corrective action, Global Nuclear Fuels has agreed to perform more GE14 testing to resolve this descrepancy and use the resulting data to generate an appropriate GEXL14 uncertainty. As an interim action, an increased GEXL 14 uncertainty that incorporates a significant penalty has been calculated and applied to the MCPR Safety Limit (SLMCPR) for this cycle.

Results from the reload analyses for Browns Ferry Unit 2, Cycle 13 are documented in Reference 3.

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 (APRhQ 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. l-l)
f. Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

TVA Nuclear Fuel TVA-COLR-BFZC13 Core Operating Limits Report Revision 0, 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 l-l 1. The APLHGR limits for the GE1 1, GE13, and GE14 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.

Bundle Tvpe 1: ..,EDB N&:-

GE1 l-P9HUB366-12G4.0 2133

I?iQwTi2. GE1 l-P9HUB367-14GZ 2135

.:.: I&L we - 3 I GE13-P9HTB384-12G4.0 1 2218 1 Flgwe4. I GE13-P9DTB391-13GZ 1 2430 faxre10 I GE14-PlODNAl3416-16GZ I 2600 I we 11 I GE14-PlODNAB200-3GZ 1 2603 1 These APLHGR limits are adjusted for off-rated power and flow conditions using the ARTS factors, h4APFAC(P) and MAPFAC(F). The reduced power factor, MAPFAC(P), is given in Figure 12 (reference 11). Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 13 (reference 5). 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 l-l 1 are applicable for both Turbine Bypass In-Service (IBIS) and Out-Of-Service (TBOOS). The off-rated power corrections [MAPFAC(P)] in Figure 12 contain separate limits to be applied below Pbypass (30% rated power) for TBIS or TBOOS. The off-rated flow corrections [MAPFAC(F)] in Figure 13 bound both TBIS and TBOOS operation.

The APLHGR limits in Figures l-l 1 are applicable for both Recirculation Pump Trip (RPT)

In-Service (RPTIS) and Out-Of-Service (RPTOOS). The off-rated power [MAPFAC(P)]

and flow corrections [MAPFAC(F)] in Figures 12 and 13 bound both RPTIS and RPTOOS 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 multipliers to be applied to this cycle is 0.84 for GE1 1, 0.84 for GE1 3, and 0.93 for GE14 (reference 3). It is not necessary to apply both the off-rated MAPFAC and SLO multiplier corrections at the same time.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 5

3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.23)

The LHGR limit is tie1 type dependent. For Unit 2 Cycle 13 there are three (3) fuel types in the core, GE1 1, GE13 and GE14. The limits for these types are given below:

I GE11 I

14.4 kw/R I

GE13 14.4 kwlfi GE14 13.4 kwifl

TVA Nuclear Fuel TVA-COLR-BF2C13 Core Operating Limits Report Revision 0, Page 6

4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2,3.3.4.1, AND 3.7.5)
a. Rated Limits - OLMCPR(lOO): The MCPR Operating Limit for rated power and flow conditions, OLMCPR(lOO), is equal to the fuel type and exposure dependent limits shown in Figures 13 - 17, as defined in the following table:

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 15 and 17 limits at any point in the cycle.

As noted in the footnotes of Figures 14 through 17, an adder of 0.02 is applied for single loop operation.

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

z - TB z = 0.0 or w , whichever is greater where; TA = 1.0% set (analytical Option A scram time limit - based on dropout time for notch position 36) n c zI r=l z 0°C =

n I

TB = p+ 1.65 *IS

based on dropout time for notch position 36)

CT = 0.019 set (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 51 = Scram time (dropout time) from fully withdrawn to notch position 36 for the i rod

TVA Nuclear Fuel TVA-COLR-BFZC L 3 Core Operating Limits Report Revision 0, Page 7

b. Startup Limits: Option A OLMCPR limits (2=1.0) shall be used prior to the determination of T in accordance with SR 3.1.4.1.
c. Off-Rated Limits: For off-rated power and flow conditions, power-adjusted

[MCPR(P)] and flow-adjusted [MCPR(F)] operating limits are determined from Figures 18 and 19, respectively. The MCPR(P) curve above Pbypass (30% rated power) is a multiplier to be applied to the OLMCPR(100) limit. The hlCPR(P) curve below Pbypass and the MCPR(F) curve are OLMCPR values to be used directly. The most limiting power-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition. Figures 18 and 19 have been resealed for the cycle SLMCPR of 1.08 (documented in Reference 12), as specified in Appendix D of Reference 3.

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 RPTOOWTBOOS condition in Figures 14 through 17. Additionally an off-rated MCPR(P) correction from Figure 18 (references 11 & 12) shall be applied for TBOOS when the power is below Pbypass. This portion of Figure 18 has been resealed for the cycle SLMCPR of 1.08 (documented in Reference 12), as specified in Appendix D of Reference 3.

e . Single Loop Operation (SLO) Limits: As noted in section 4.a above, a correction of 0.02 is to be applied to the OLMCPR(100) limits for SLO as described in the footnotes of Figures 14 through 17. The same adder applies to the off-rated MCPR(F) as noted in the footnote to Figure 19 and to the MCPR(P) value below Pbypass from Figure 18.

TV.4 Nuclear Fuel TVA-COLR-BFX 13 Core Operating Limits Report Revision 0, Page 8

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUAL SECTION 53.1 AND TABLE 3.3.4-l)

The APRM Rod Block trip setting shall be:

SRJIJ I (0.66(W-AW) + 61%) Allowable Value sm I (0.66(W-AW) + 59%) Nominal Trip Setpoint (NTSP) where:

SW= 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=O.O 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-BFX 13 Core Operating Limits Report Revision 0, Page 9

6. ROD BLOCK MONITOR (RBM) TIUP 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):

@BM.%rip S&p$nt  : Alloyabk Value Net&al Trip Setpvint :

. ::.,: (AV) (NTSJP): ; .

LPSP 27% 25%

IPSP 62% 60%

I HPSP 82% 80%

I LTSP - unfiltered 121.7% 120.0%

- filtered 120.7% 119.0% U),(2)

ITSP - unfiltered 116.7% 115.0%

- filtered 115.7% 114.0% U),(2)

HTSP - unfiltered 111.7% 110.0%

- filtered 110.9% 109.2% (1W)

I I I DTSP 90% I 92%

Notes: (1) These setpoints are based upon an Analytical Limit HTSP of 114% (w/o filter) which corresponds to a MCPR operating limit of 131 (using the cycle safety limit of 1.08), as reported in Section 10 of reference 3 [SRLR]. It is important to note that Unit 2 Cycle 13 has had a cycle specific RWE analysis performeti and the table provided in Section 10 of reference 3 supercedes the OLMCPR values provided in references 6,7, and 8.

(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 5 0.5 seconds (reference 7).

The RBM setpoints in Technical Specification Table 3.3.2. l-l are applicable when:

< 1.72 (a), (b), (f), (h) dual loop operation

< 1.75 (4, @I, (CA 00 single loop operation

< 1.41 (g> dual loop operation (*I Notes: (1) The MCPR values shown correspond to a SLMCPR of 1.08 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-BFT13 Core Operating Limits Report Revision 0, Page 10

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

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

SDM 2 0.38% dWk

TVA Nuclear Fuel TVA-COLR-BF2C13 Core Operating Limits Report Revision 0, Page 11

8. REFERENCES
1. NEDE-240 11 -P-A-14, General Electric Standard Application for Reactor Fuel, June 2000.
2. NEDE-24011 -P-A-14-US, General Electric Standard Application for Reactor Fuel (Supplement for United States), June 2000.
3. OOOO-0006-13SS-SRLR Rev. 0, Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 12 Cycle 13, February 2003.
4. 0000-0006-1355~MAPL Rev. 0, Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 12 Cycle 13, February 2003.
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 [ARTSMELLL (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 [ARTSNELLL (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 8001

10. GE Letter JAB-T80 19a, Technical Specification Changes for Implementation of Advanced Methods, dated June 4, 1998. [L32 980608 8001 11 .GE-NE-LI2-00889-00-O 1P Revision 0, GE14 Fuel Design Cycle-Independent Analyses for Browns Ferry Units 2 and 3, dated January 2002. [L32 020208 8001 12Calculational File BFE-1626, Adjust ARTS MCPR(P) and MCPR(F) Curves for SLMCPR Change, dated March 19,2002. [L32 020319 8021 13.GNF Letter CJP:O3-023, Supplemental Information to the Browns Ferry 2 Cycle 13 SRLR, dated February 26,2003. [L32 030226 8021

TVA Nuclear Fuel TVA-COLR-BFZC13 Core Operating Limits Report Revision 0, Page 12 Figure 1 APLHGR Limits for Bundle Type GEll-P!JHUB366-12G4.0 (GE11 EDB# 2133) 15.00 -

14.00 -- ---. -- j ....-.. -...-.-.-.- .-..---.:."-...-.." ""......""".'. '... ..'.'-'-.- -.- -... .- _." --.-j. '....'.-....

5.00 -- .. .-' j.

1.00 -1.. i , .._

o.w.."".".!""""':""""'!""""'!""""~i~"'~

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/slJ Most Limiting lattice for Each Exposure Point These values apply to both Turbine Bypass In-Service and OutUf-Service.

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

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-BFZC 13 Core Operating Limits Report Revision 0, Page 13 Figure 2 APLHGR Limits for Bundle Type GEll-P9HUB367-14GZ (GE1 1 EDB# 2135)

,q 0 -1.. ..,.......,. .,... - .: ..~ ..-

13.00 -- .'........ .""..." ...:.-.. ..... --"'.' ....._'. .'. .....- "'.'..".'-."' _'.' '. .. ..."'.-.. .. .'.'. .....""_- .'---."'.'._-..- .'.'

o.oai."""'-i' """i " ". '/' "'.I"""'.')""'

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST)

Umt Limiting Latllce for Each Exposure Point These values apply10 both Turbine Bypass In-Service and OubOfSawice.

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

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

TVA Nuclear Fuel TVA-COLR-BFZC13 Core Operating Limits Report Revision 0, Page 14 Figure 3 APLHGR Limits for Bundle Type GE13-P!IHTB384-12G4.0 (GE13 EDB# 2218) 20.0 30.0 Cycle Exposure (GWOIST)

Most Limiting Lattke for Each wcsure Point These values apply to both Turbine Bypass InService and Out-OfSenke.

These values apply to both Recirculation Pump Trip in&-n&e and OutJDfService.

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 Sectlon 2.

TV.4 Nuclear Fuel lTA-COLR-BF?C 13 Core Operating Limits Report Revision 0, Page 15 Figure 4 APLHGR Limits for Bundle Type GE13-P9DTB391-13GZ (GE13 EDB# 2430) 15.00 -

,4,00-: .._._.._..._..... ~. _..,...................................  :

13.00 .: .,.

UNACCEPTABLE OPERATION 5.00 --

4.M) --... ...._-- -.-.-.. ....-.-.- -...

o.oo-(:..: ...;. k .:

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWCWST)

Most LimiUng Lattiie for Each Exposure Point These values apply to both Turbine Bypass InServIce and Out-OfService.

These values apply to both Recirculation Pump Trlp In-Service and Outaf-Sewice.

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

TVA Nuclear Fuel TVA-COLR-RFX13 Core Operating Limits Report Revision 0, Page 16 Figure 5 APLHGR Limits for Bundle Type GE13-P9DTB412-2G7.0/llG5.0 (GE13 EDB# 2431) 1500 -

o.ooi..~..~..~:-.-..~.--l~..-....~i....~-~.  :.:

0.0 10.0 22.0 30.0 40.0 50.0 Cycle Exposure (GWDMJ Most Limiting Lanke for Each Exposure Point These values apply to both Turbine Bypass InServIce and Out-Of-Service.

These values apply to both Recirculation Pump Trip InService 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-BFZC 13 Core Operating Limits Report Revision 0, Page 17 Figure 6 APLHGR Limits for Bundle Type GEl4-PlODNAB1862 (GE 14 EDB# 2627) 1400 -

4.00 .: j  ; . . . . . i o.oo+..~..~~  : .:......../....,....;;

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposurs (GWDIST)

Mosl Llmlhng Lattice for Each Exposure Pant These values apply to both Turbine Bypass In-Service and OutQf-Sewice.

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

The APLHGR llmits shown are for dual recirculation loop operation. For single loop operatlon, these values should be multiplied by the most limiting of either 0.93 or the MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BF2C13 Core Operating Limits Report Revision 0, Page 18 Figure 7 APLHGR Limits for Bundle Type GE14-PlODNAB417-18GZ (GE14 EDB# 2628) 5.00 --

4.00 .:. ..................................................................................... ...................................... . ..................

0.00~"""'":"""'":""'-":""""':""""':"""

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Gposure (GWWST)

Most Lbmiting Lattice for Each Exposure Point These values apply to both Turbine Bypass In-Service and Out-OfService.

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 0.93 or the MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 19 Figure 8 APLHGR Limits for Bundle Type GE14-PlODNAB367-14GZ (GE14 EDB# 2602) 0.001;:.;.  :..:

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Expasure (GWDIST)

Most Limiting Lattice for Each Exposure Poinl These values apply to both Turbine Bypass In-Service and Out4%9ervke.

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

The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multlplled by the most limiting of either 0.93 or the MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 20 Figure 9 APLHGR Limits for Bundle Type GE14-PlODNAB16GZ (GE14 EDB#2601) 14.00 T 13.00 .:. _..__._.__,. .,.............._.... _.,. .,.. . . . .._ .,. ._... j _.;

2 . 0 0 - - ....

1.00 .: .._..._.. . ..! i -..

o.ooi:::::

0.0 10 0 20.0 30.0 40.0 50.0 Cycle Exporura (GWDIST)

Most Llmitirg Lattice for Each Exposure Point 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-OfSetvice.

The APLHGR limits shown are for dual recirculation loop operatlon. For single loop operation, these values should be multiplied by the most limiting of either 0.93 or the MAPFAC correctIon, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BFC 13 Core Operating Limits Report Revision 0, Page 21 Figure 10 APLHGR Limits for Bundle Type GE14-PlODNAB416-16GZ (GE14 EDB#2600) 14.00 -

4.00 .:  ;. I . I 0.001..1,.. I . ..f.,.,.. /.-....i.

0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST)

Mast Limiting Lattice for Each Exposure Pant These values apply to both Turbine Bypass InServIce and Out-OfService.

These values apply to both Recirculation Pump Trlp InServlce and Out4f-Sewice.

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 0.93 or the MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 27 Figure 11 APLHGR Limits for Bundle Type GE14-PlODNAB200-3GZ (GE14 EDB#2603) 14.00 -

Jr.00 .:.. ..-

ACCEPTABLE OPERATION 4.00 -: _..__.._,_,_._._.....,.... ~.. .,.. i .i 2.00 .: .,._ . . .I

,JJo .: ..- ..-. . . . . . <.. / -.

0.001~~~~~~11 ~~~I~~~~~.~I.~~~~~~:C 0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposurs (GWDIST) 4q.O . . . .! . . . . 8.23 These values apply to both Turbine Bypass In-Service and Out-OfSewice.

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

The APLHGk limits shown are for dual reclrculatlon loop operation. For single loop operation, these values should be multlplied by the most llmltlng of &her 0.93 or the MAPFAC correction, as described in Section 2.

TV-4 Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 23 Figure 12 Power Dependent MAPLHGR Factor - MAPFAC(P) 0.9 ._..

0.6 .-

F .

5 .

i 0.7 .-

4 Tws: 5 50% cue Flcm I .

\

0.6 . ., ..,.... .;

5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 65 90 95 100 Power (x Rated)

Below Pbypass (30% Rated Power) the Value is dependent Upon whether the Turbine Bypass System is InServIce (TBIS) or Out-OfSeruice (TBOOS)

MAPLHGR(P) = MAPFAC(P) x MAPLHGRrtd MAPLHGRstd = Standard MAPLHGR Limits Below Core hlonltorina Power Threshold (25% Rated Power)

For 25% z- P  : NO THERMAL LIMITS MONITORING REQUIRED NO LlMlTS SPECIFIED Below Pbvoass with Turbine Bvoass Svstem In-Service fTBlS)

F o r 2 5 % (P < 3 0 % : MAPFAC(P) = 0.600 + O.O05(P-30%) For 5 50% CORE FLOW

MAPFAC(P) = 0.460 + 0.905(P-30%) F o r > 50% COREFLOW Below Pbvoass with Turbine Bvoass Svstem Out-OfService ITBOOS)

For 25% ( P

  • 30% : MAPFAC(P) = 0.577 + 0.0124(P-30%) For 5 50% CORE FLOW
MAPFAC(P) = 0.446 + 06092(P-30%) F o r > 50% COREFLOW AbovePbvpass For 30% s P  : MAPFAC(P) = 1.0 + O.O05224(P-100%)

These Curves Bound both the Recirculation Pump Trip In-Service (RPTIS) and Out-OfSewice (RPTOOS)

TVA Nuclear Fuel TVA-COLR-BFC 13 Core Operating Limits Report Revision 0, Page 24 Figure 13 Flow Dependent MAPLHGR Factor - MAPFAC(F) 1 0.9 0.8 A

s 2 0.7  :

3 0.6 0.5 ,i 0.4 -I-30 40 50 60 70 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 1100 + Bf)

Af and Bf are Constants Given Below:

102.5 0.6784 0.4861 107.0 0.6768 0.4574 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).

TV.4 Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 25 Figure 14 MCPR Operating Limit for All GE11 & GE13 Bundles For Cycle Exposures up to EOR-2200 MWWST (sea note 3) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 Option A Option I3 Tau ( 7 )

i:::ljliiiitii;ii;i::;;-i~;,i:~~~r

. . . .., .,. . .\: : : ~::.:::~:~::::?:::~::;~r~::::::::::: :. ..

.
: .,,;y;~: j i::lll.i..::;li~:i:,::~:~,~~::.;:: :::::y;:::jl:::::; :

BOC13 to (EOR-2200 MWDST) na 1.33 1.31 BOC13 to (EOR-2200 MWD/ST) Turbine Bypass (TBOOS) 1.36 1.31 BOC13 to (EOR-2200 MW D/ST) Recirculation Pump Trip (RPTOOS) 1.36 1.31 BOC13 to (EOR-2200 MWD/ST) TBOOS and RPTOOS 1.39 1.34 Notes

1. Use this value prior to performing scram time testing per SR 3.1.4.1.
2. The values shown are for dual recirculation loop operation (1.06 SLMCPR). Increase any value shown by 0.02 for Single Loop Operation (SLO:SLMCPR=l .lO).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with namal Feedwater Heating.

TVA Nuclear Fuel -WA-COLR-BFZC13 Core Operating Limits Report Revision 0, Page 26 Figure 15 MCPR Operating Limit for All GE11 & GE13 Bundles Optional for All Cycie Exposures - Required after EOR-2200 MWDLST is reached (see note 3) 1.46 1.45 1.44 1.43 _-.. ..;

1.42 B

T 1.41 z

y 1.40 t 1.39

=

5 1.36 B 1.37

=

1.36 E 1.35 Y

1.34 .;

1.33 j.

,:-  : Turbine Byp 1.32 i.

1.31 f

1.30 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 option B Option A Tau (2)

BOC13 to EOC13 na 1.33 1.31 BOC13 to EOC13 Turbine Bypass (TBOOS) 1.38 1.35 BOC13 to EOC13 Recirculation Pump Trip (RPTOOS) 1.40 1.32 BOC13 to EOC13 TBOOS and RPTOOS 1.45 1.37 Notes

1. Use this value prior to performing scram time testing per SR 3.1.4.1.
2. The values shown are for dual recirculation loop operation (1.08 SLMCPR). Increase any value shown by 0.02for Single Loop Operation (SLO:SLMCPR=l.lO).
3. EOR refers to the end of Full Power Capabilityt Rated Flow with normal Feedwater Heating.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 27 Figure 16 MCPR Operating Limit for All GE14 Bundles For Cycle Exposures up to EOR-2200 MWDLST (see note 3)

_e 0 0.1 0 2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 Option B Option A Tau (T)

BOC13 to (EOR-2200 MWDIST) na 1.38 1.35 BOG13 to (EOR-2200 MWDIST) Turbine Bypass (TBOOS) 1.42 1.39 EtOC13 to (EOR-2200 MWDIST) Recirculation Pump Trip (RPTOOS) 1.47 1.36 BOG13 to (EOR-2200 MWDIST) TBOOS and RPTOOS 1.51 1.40 Notes

1. Use this value prior to performing scram time testing per SR 3.1.4.1.
2. The values shown are for dual recirculation loop operation (1.08 SLMCPR). Increase any value shown by 0.02 for Single Loop Operation (SLO:SLMCPR=l.lO).
3. EOR refers to the end of Full Power Capabilityat Rated Flow mth normal Feedwaler Heating.

TVA Nuclear Fuel -I-VA-COLR-BFX 13 Core Operating Limits Report Revision 0, Page 78 Figure 17 MCPR Operating Limit for AU GE14 Bundles Optional for All Cycle Exposures - Required after EOR-2200 MWDKT is reached (see note 3)

.. "" L .. ".'...  ;-. ._ I -; .- ".

=1.45 ... .. IL-:.:--. _ 2. .- _ .-. . . . .Y -T i ._ ..i

, ,a . "d.7; :i ..,.. ~.. '..".'.:'

1.43  ;.." j

..; Turbine &pass and Rbclrculatlon PUW Trip InServIce 1.42 ' ~

1.41 i 1 . 4 0 .i .' i 1.39 1.36 """"':""""':""".":"""".:.....""I".."".:'.""'..i~.~~~~~~~~~~~~~~~~~~~~-

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 Option B Option A Tau (T) b jlj i.iil.ii::liiiliii~~~~~~~~~,~:~~:~ j

. ,,i..:,., ,. ,.,A.,.. ,A.

. . . ..I.... .i. . . . . . . ..A. . . . . .,....), .,

BOCl3 to EOCI 3 na 1.42 1.39 BOC13 to EOC13 Turbine Bypass (TBOOS) 1.47 1.44 BOC13 lo EOC13 Recirculation Pump Trip (RPTOOS) 1.59 1.42 BOC13 to EOC13 TBOOS and RPTOOS 1.64 1.47 Notes

1. Use this value prior to performing scram time testing per SR 3.1.4.1.
2. The values shown are for dual recirculation loop operation (1.08 SLMCPR). Increase any value shown by 0.02 for Single Loop Operation (SLO:SLMCPR=l.lO).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with normal Feedwater Heahng.

TVA Nuclear Fuel TVA-COLR-BFZC 13 Core Operating Limits Report Revision 0, Page 29 Figure 18 Power Dependent MCPRCP) Limits 4.2 0 10 20 30 40 so 60 70 60 90 100 110 power (x Rated)

Below Pbypass (30% Rated Power) the Value Is dependent Upon whether the Turbine Bypass System is In-Service (TBIS) or Out-Df-Setvice (TBGGS)

OPERATING LIMIT MCPR(P) = Kp OLMCPR(lO0)

Below Core Monitorfna Power Threshold (25% Rated Power)

For P < 25%  : NO THERMAL LIMITS MONiTORiNG REQUIRED NO LiMiTS SPECIFIED

&slow Pbwass with Turbine Bvoass Svstem In-Service (TBIS\

For 25% ( P c 30% : MCPR(P) = 2.09 + 0.022(30%4) F o r ( 5O%COREFLOW

MCPR(P) = 2.31 + 0.034(30%-P) For r 50% CORE FLOW

&low Pbvoass with D For 25% 5 P < 30% : MCPR(P) = 2.55 + 0.072(309&P) For ( 50% CORE FLOW

hlCPR(P) = 3.35 + 0.102(30%4) For > 50% CORE FLOW Above Pbvoasiq For 30% (P<45%  : Kp = 1.28 +0.01340(45%-P)

For 45% (Pe80%  : Kp = 1 .15 + 0.00887(60%P)

For 60% ( P  : Kp = 1.00 + 080375(100%P)

These Curves Bound both the Recirculation Pump Trip InServIce (RPTiS) and Out-Of-Service (RPTOOS)

Note: The OLMCPR below Pbypass is based upon the dual recircuiatlon loop SLMCPR of 1.08.

Add 0.02 to the OLMCPR in Slngie Loop Operation [SLMCPR(forSLO) = 1.101.

TVA Nuclear Fuel TVA-COLR-BFC 13 Core Operating Limits Report Revision 0, Page 30 (Final)

Figure 19 Flow Dependent MCPR Operating Limit - MCPRW 30 40 so w 70 So 90 100 Core Flow (V. Rdd)

For W C 2 30%  : MCPR(F) = MAX(l.21, AfWdlOO + Bf)

WC = % Rated Core Flow Af and Bf are Constants Given Below:

These values bound both Turbine Bypass In-Service and Out-GfServlce.

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 operatlon up to 105% rated flow (ICF).

This flgure is based upon the dual reclrculatlon loop operation SLMCPR of 1.06.

Add 0.02 to these values for Single Loop Operatlon [SLMCPR(for SLO) = 1.10).

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