ML030980683

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Core Operating Limits Report, for Cycle 13 Operation
ML030980683
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
Download: ML030980683 (33)
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Text

N Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 1, 2003 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. 50-260 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, Manager of nsing ndIndustry ffairs Enclosure Se pag P-ted cn aycled paps

-7 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 3561.1-6970 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)

\\

I TVA Nuclear Fuel Core Operating Limits Report QA Document TVA-COLR-BF2C13 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:

Verified By:

Approved By:

Reviewed By:

Reviewed By:

Earl E. Riley, Engine6ing Specialist BWR Fuel Engineering an L. Bruce, Nuclear Engineer BWR Fuel Engineering

-7ff-Date:

2.*2c-03 Date:

2L/

3 Date:

Date: 2/2 $3 Date: ____

_/ 3 C-,vr-James F. Lemons, Manager BWR Fuel Engineering iJ.

M. Keck, Supervisor Browns Ferry Reactor Engineering

//

PORC Chairman Revision 0 (2/26/2003)

Initial Issue Pages Affected: All

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 2 Revision Log Revision Date Description Affected Pages 0

2/26/2003 Initial Release for New Cycle All

Or t l I n

TVA Nuclear Fuel TVA-COLR-BF2C13 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 I 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 GEXL14 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 (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-BF2C13 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 1-11. The APLHGR limits for the GEl l, 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.

I "o................

Fi ire l GEl 1-P9HUB366-12G4.0 2133 Fl GE 1-P9HUB367-14GZ 2135 E

re 3 GE13-P9HTB384-12G4.0 2218 gure4 GE13-P9DTB391-13GZ 2430 Figre 5 IGE13-P9DTB412-2G7.0/ 1 G5.

2431 Figue6 GE14-PIODNAB416-18GZ 2627 F re.

GE14-PlODNAB417-18GZ 2628 F

e X GE14-PlODNAB367-14GZ 2602 Fi rge GE14-PlODNAB416-16GZ 2601 H re 10 GE14-PlODNAB416-16GZ 2600 gu re.1 GE14-PIODNAB200-3GZ 2603 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 12 (reference 11). Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 13 (reference 5). Both factors arc 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 1-11 are applicable for both Turbine Bypass In-Service (TBIS) 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 1-11 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 GE1I, 0.84 for GE13, 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 Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 5

3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3)

The LHGR limit is fuel 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:

G:.

1

... {

0 g GEI I 14.4 kw/ft GE13 14.4 kw/ft GE14 13.4 kw/ft

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(100): The MCPR Operating Limit for rated power and flow conditions, OLMCPR(100), is equal to the fuel type and exposure dependent limits shown in Figures 14 - 17, as defined in the following table:

i '

T 1

r GE11 & GE13 BOC to EOR-2200 MWD/ST i5

{GE11&GE13 BOC toEOC GE14 BOC to EOR-2200 MWDIST GE14 BOC to EOC 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(1 00) value is dependent upon the scram time testing results, as described below (ref. 10):

tave TB T = 0.0 or whichever is greater TA

'B where; TA

= 1.096 sec (analytical Option A scram time limit - based on dropout time for notch position 36) n Tave

=

i=l n SB

=

+ 1.65

  • ca * [-]

n where; 1t = 0.830 sec (mean scram time used in transient analysis -

based on dropout time for notch position 36) cr = 0.019 sec (standard deviation of tt)

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 xl = Scram time (dropout time) from fully withdrawn to notch position 36 for the i"' rod

TVA Nuclear Fuel TVA-COLR-BF2C13 Core Operating Limits Report Revision 0, Page 7

b. Startup Limits: Option A OLMCPR limits (T=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 MCPR(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 rescaled 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 RPTOOS/TBOOS 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 rescaled 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.

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, 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%)

SRB < (0.66(W-AW) + 59%)

Allowable Value Nominal Trip Setpoint (NTSP) where:

SPjB =

AW=

AW =

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

Loop recirculation flow rate in percent of rated 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 13%).

I TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, 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 Tip Stpoit Alowable Value NmnlTrpSton

.........vvv=..s.

LPSP 27%

25%

IPSP 62%

60%

HPSP 82%

80%

LTSP - unfiltered 121.7%

120.0%

- filtered 120.7%

119.0%

ITSP - unfiltered 116.7%

115.0%

- filtered 115.7%

114.0%

HTSP - unfiltered 111.7%

110.0%

- filtered 110.9%

109.2%

DTSP 90%

92%

(1),(2)

(1),(2)

(1),(2)

Notes: (1)

These setpoints are based upon an Analytical Limit HTSP of 114% (w/o filter) which corresponds to a MCPR operating limit of 1.31 (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 performed 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 < 0.5 seconds (reference 7).

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

-HERMAL PO E pie e

Notes fromn"

.......i i

..." :S

Ra-te)

MPR~ 1 T.."'able 3.3.2..1:

> 27% and < 90%

< 1.72 (a), (b), (f), (h)

< 1.75 (a), (b), (f), (h)

> 90%

< 1.41 (g) dual loop operation single loop operation dual loop operation (2)

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 Core Operating Limits Report TVA-COLR-BF2C13 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 OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted.

SDM > 0.38% dklk

TVA Nuclear Fuel TVA-COLR-BF2C 13 Core Operating Limits Report Revision 0, Page 11

8. REFERENCES
1. NEDE-24011-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. 0000-0006-1355-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 [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]

1 L.GE-NE-L12-00889-00-OlP Revision 0, "GE14 Fuel Design Cycle-Independent Analyses for Browns Ferry Units 2 and 3", dated January 2002. [L32 020208 800]

12.Calculational File BFE-1626, "Adjust ARTS MCPR(P) and MCPR(F) Curves for SLMCPR Change", dated March 19, 2002. [L32 020319 802]

13.GNF Letter CJP:03-023, "Supplemental Information to the Browns Ferry 2 Cycle 13 SRLR", dated February 26, 2003. [L32 030226 802]

I.

II TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 12 1,

Figure 1 APLHGR Limits for Bundle Type GEI1-P9HUB366-12G4.0 (GE1I EDB# 2133) 15.

141 13.1 121 11 10 E 8

3i a:

7 a

K-6 545 4

3 2

0 00-UACCEPTABLE OPERATION i

00 '1,.X oo.

.....................X 00.

00 oo t....................

00

........... +....

00-ACCEPTABLE OPERA~TIONl 00

_~...... 4.'.'

00 -

................................ +.. '.........

00 00 00 100 20 0 30.0 Cycle Exposure (GWDIST) 40.0 50 0 Most Umiting Lattice for Each Exposure Point 0.2 42 I I 0

I 4

3.0 9.

0.2 9.42i 8.0

11.43 30..

?.0 9.64.

1.0 9.60 9.0 11.57 35.0 9.00 2.0 9.84 100 11.71 400 8.37

~.

c....

3.0 1011 12.5 11.68 450 7.75 4.0 10.36 15.0 11.48 50.0 7.11 5.0 10.62 17.5 11.25 55.0 6.45 6.0 10.88 200

.0.97 5617 6.29 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 Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 13 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11 EDB# 2135)

I 0.

1500 14 00-13 00-12 00-11 00-1000 900w 800-7.00 -

600 500 400-300-200-1 00 0 00 0

UNACCEPTABLE OPERATION 4.

ACETABL OERATION).

  • ----------------------------+-'-'-----------'----.

~~~~~~~~~~~~~~~............ jilACPAL PRTO

..i 0

100 200 300 Cycle Exposure (GWDIST) 40.0 500 Most Umiting Lattice for Each Exposure Point 0.2 9.08 7.0 11.08 1

25.0 8.0 11.43 1

30.0 E

9.64 I

1.0

  • .6 0

2.0 9.52 10.0 11.71 40.0 8.37 3.0 i

9.80 12.5.

11.68 45.0 i

7.75 4010.09 15011.48 50.0 5.0

.10 40 1

17.5 j11.25 1

55.0 6.45 61 0. 95 60 10.73 1

20.

10.97 56.17 6.29 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 Core Operating Limits Report

,I I

TVA-COLR-BF2CI3 Revision 0, Page 14 Iv I ?

Figure 3 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13 EDB# 2218) z 0.

1500 1400.-

1300.

UNACCEPTABLE OPERATION 1200 100 9 oo ------

8 00 -

....... j 7 °°.

i**-

1 ACCEPTABLE OPERATION l...................1 2.00 4500 --

3400 -

2.00 -.

1.00 000 0.

I 00 100 200 300 Cycle Exposure (GWD/ST) 400 50 0 Most Umiting Lattice for Each Exposure Point u.u I u.uZ 0.2 10.15 1.0 10.31 8.0 11.95 9.0 12.16 30.0 10 43 10

.0 6.3.

35.0 110.06 2.0 10.52 10.0 12.28 40.0 9.72 3.0

...0....i.75 1.25 12.16 45.0 9.38 4.0 10.99 15.0 11.88 50.0 9.03 5.0 11.25 17.5 11.56 55.0 8.66 6.0 11.48 20.0 11.24 55.98 l

8.58 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 Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 15 i,, It Figure 4 APLHGR Limits for Bundle Type GE13-P9DTB391-13GZ (GE13 EDB# 2430)

E

-A a-1500 1400.-

13 0 0 12 l -.UNACCEPTABLE OPERATION I12 o.

10.00 T 9200 -

7.00 ACCEPTABLE OPERATION 7.00 6.00 -

2. 0 0 ---------.-----------------------------

1.00 000 I

I 00 100 20.0 30 0 Cycle Exposure (GWD/ST) 40 0 so 0 Most Llmring Lattice for Each Exposure Point 0.2 10.80 1.0 10.87 2.0 10.96 10.0 11.77 40.0 1 9.49 3.0 11.06 12.5 11.71.45.0 9.15 4.0 11.15 15.0 1.63 50.0 8.78

1.

17.5 11.55 55.0 8.45 6.0 11.35 20.0 11.39 57.82 A

8.27 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 recirculatlon 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 Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 16 i Ia Figure 5 APLHGR Limits for Bundle Type GE13-P9DTB412-2G7.0/11G5.0 (GE13 EDB# 2431) 1500 -

14.00 - - -

13.0 0

- t 12.00 UNACCEPTABLE OPERATION 1100

,in o

! g oo

& 800 -

E w 7.00-

-Ji 6 00 500 400 -

300 -

2 00 -

1 00 000

~~...

.................i lls

.~~~

t..-..-.----..-.-.....,-..-.--..-.---..-.............

PACCEPTABLE OPERATION..............

k

+..

0.0 100 200 300 Cycle Exposure (GWDIST) 40.0 500 Most Umiting Lattice for Each Exposure Point u.u

.AbOO_

00 0.2 10.45 0

1..

7.

1.0 10.57 I A j I *..JL.

8.0 11.73 9.0 11.86 2.0 10.72 1.0 12.00

.. o 5T

_o os~

3010.88 12512.03 4.0 i

11.05 15.0 11.96 5.0 11.22 17.5 11.80 6.0 11.40 20.0 11.59 S

  • ..L IOOAOA A

O A-10.678 wwo..ooAi1.46' 10.01

..... 4~....

9.49 9.04 8.66 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.

i TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 17 Figure 6 APLHGR Limits for Bundle Type GE14-PlODNAB416-18GZ (GE14 EDB# 2627) 1400 1300-1200-11 00-10.00 900-8 800I 7.00.

4 600

-J 500.

4 00 300 200 1 00

......................... ;.UNACCEPTABLE OPERATION A..

fUNACCEPTABLE ee'.

i (1ACCEPTABLE OPERATION)s I.

O...

i..

nn.........

,l I.

I

.I 0 0 100 200 300 Cycle Exposure (GWD/ST) 40 0 50 0 Most Limiting Lattce for Each Exposure Point hA ~ ~~~~~

-~AIW

~ A

-AA A AW A ~

-A A

WA -

WPAWA AWAV AA"_.._ibWWAWA AWAM 3.0 9.77 2.0 10.85 40.0 9.09 4.0 9.93 13.0 10.86 45.0 8.56 5.0 10.09 14.0 50.0 1

8.01

......66

-10i5......

'J.

7.0 10.25 15.0 10.93 7.0 10.41 17.0 i

10.93 57.53

4.93 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 0.93 or the MAPFAC correction, as described In Section 2.

I 

,, I i

.1

"

1., -

, -, ' 1, I,

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 18 1

1, I

Figure 7 APLHGR Limits for Bundle Type GE14-PlODNAB417-18GZ (GE14 EDB# 2628) 14 00 1300 1200 11 00 1000 900 8.00 7.00 600

~~~~...

(4UACCEPTABLE OPERATION

]

~~~~~~~.

((4..........

ct

_i

-J 0.

Cr

\\

b UU 4 00 -

3 00 -

2 00 1.00 000 00 100 200 300 Cycle Exposure (GWDIST) 40 0 500 Most Limiting Lattice for Each Exposure Point 2.0 9.63 i 1.0 11.00 35.0 9.62 3.0 9.80 12.0 11.02 40.0 9.12 4.0 9.99 13.0 11.02 45.0 8.58 5.0 10:19 14.0 11.02 50.0 8.02

..6.0 10.41 15.0 11.03 55.0 6.35 7.0 10.64 17.0 11.02 57.82 4.92 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 0.93 or the MAPFAC correction, as described In Section 2.

4

.~I i j-2 TVA Nuclear Fuel Core Operating Limidts Report TVA-COLR-BF2C 13 Revision 0, Page 19 Flgure 8 APLIIGR Limits for Bundle Type GE14-P1ODNAB367-14GZ (GE14 EDB# 2602) 14 00 13 00 12 00 -

11 00 -

10 00 -

9 00 8 00, 700 6.00

...... UNACCEPTABLE OPERATION......

V-0.

CD ACCEPTABLE OPERATION 15.uu 4 00-33 0 0

+....

nAn 0 0 10 0 20 0 30 0 Cycle Exposure (GWDIST) 40 0 50.0 Most Limiting Lattice for Each Exposure Point 1.0 2.0 9.96 10.09 1 0.0 11.29 11.0 11A45 3.0 10.24 12.011 540 01

.7 4.O0 i

10.40 13.0 11.53 45.0 i823

.14.

.010.71 1 5.

0....... 11i.43 55.0 6

70 f

10.85 17.0 1 2656.76 4.79 These values appiy 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 0.93 or the MAPFAC correction, as described In Section 2.

I TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 20 I

Figure 9 APLHGR Limits for Bundle Type GE14-PlODNAB416-16GZ (GE14 EDB#2601) 1400 1300-1200-11 00-10.00 900-8a00 E 7.00 C3 I

6 00 C.

'Cr

~~.

.................,, V.',

...... {....... UNACCEPTABLE OPERATION l O.+

--(ACCEPTABLE OPERA1

RON, 400.

300 -

2 00.

1.00 1.00 0.0 nn i'i' 0 0 100 20.0 30 0 Cycle Exposure (GWD/ST) 400 500 Most Limiting Lattice for Each Exposure Point 30 9.83 12.0 11.03 40.0 I

9.13 4.0 10.02 13.0 11.02 45.0 1

8.59 5.0 10.21

.11.02 50.0 8.03 6.0 10.43 15.0 11.03 55.0 6.38 7.0 10.62 7.0 11.02 57.90 4.92 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 0.93 or the MAPFAC correction, as described In Section 2.

I TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 21 0.I Figure 10 APLHGR Limits for Bundle Type GE14-P1ODNAB416-16GZ (GE14 EDB#2600) 14.00 1300-12.00 -

11.00-1000 900-1 800-7.00-C, 600 I

6 00 -

6 5Soo 400 -

3 00.

200 -

1 00 -

000 -

UNACCEPTABLE OPERATION

................,.,8

.... \\ ACCEPTABLE OPERATION 0.0 100 20 0 30.0 Cycle Exposure (GWDIST) 400 500 Most Limiting Lattice for Each Exposure Point 2.-0 1

11 -0 10.85 35.0 3

9.63 1

01 120 10.85 1

40.0 9.10 4.0 10.00 13.0 10.86 45.0 i

8.57 6.0 15.0 10.91 55.0 1 6.24 7.0

- 10.42 170 10.94 57.60 4.93 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 0.93 or the MAPFAC correction, as described In Section 2.

e_;

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 22 I

'I 1

  • I Figure 11 APLHGR Limits for Bundle Type GE14-PIODNAB200-3GZ (GE14 EDB#2603) 1400 1300-12.00-11.00-10.00-900-S 8 00 800 E 7.00-I 6 00 A.

f C

.................. *....... -+ -- UNACCEPTABLE OPERATION f i

3U~~fl T o..

..+.

ACCEPTABLE OPERATION 400 4

300 2 00................. A..

.A...

. ?...

1.00..

0.00' j.,

.j.j.i, 0 0 10.0 20.0 30 0 Cycle Exposure (GWDIST) 40.0 50 0 Most Limiting Latbce for Each Exposure Point 3.0 10.13 12.0 9.97 40.0 I

8.23 4.0 10.34 13.0 9.96 45.0 7.50 5.0 10.57 14.0 9.89 50.0 1 6.80 i 6A.......

.......i..............

".4.6.

. 4....

6.0 10.79 15.0 9.83 54.91.

.4.46 7.0 11.01 17.0 9.71 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 bythe most limiting of either O.93 orthe MAPFAC correction, as described in Section 2.

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 23 Figure 12 Power Dependent MAPLHGR Factor - MAPFAC(P) 1.1 U-a.

0 5

10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Below Pbypass (30% Rated Power) the Value Is dependent Upon whether the I

Turbine Bypass System Is In-Service (TBIS) or Out-Of-Service (TBOOS) l MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits Below Core Monitorina Power Threshold (25% Rated Power)

For 25% > P

NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED Below Pbvpass with Turbine Bypass System In-Service (TBIS)

For 25%

/c P < 30%

MAPFAC(P) = 0.600 + 0.005(P-30%)
MAPFAC(P) = 0.460 + 0.005(P-30%)

Below Pbvyass with Turbine Bvyass System Out-Of-Service (TBOOS)

For 25% < P < 30% : MAPFAC(P) = 0.577 + 0.0124(P-30%)

MAPFAC(P) = 0.448 + 0.0092(P-30%)

For < 50% CORE FLOW For > 50% CORE FLOW For <

50% CORE FLOW For > 50% CORE FLOW Above Pbvpass For 30%

P P

MAPFAC(P) = 1.0 + 0.005224(P-100%)

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

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 24 Figure 13 Flow Dependent MAPLHGR Factor - MAPFAC(F) 09 08 U-a-

0.7 06 0.5 OA 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 1100 + Bf)

Af and Bf are Constants Given Below:

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).

If

< ~I TVA Nuclear Fuel TVA-COLR-BF2C13 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 MWD/ST (see nofe 3) 1A0.

139 1.38

°1.37 -

EL

[TBOOS & RPTOOS U

51.36 E 1.35...

w

~1.31 o

TBOOS or RPTOOS

~

132T~rb;ne E~lass and Recrculation Pup Trip In-Serviee a:

1.0 0

0 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 1

Option B TuOption A

BOC13 to (EOR-2Z00 MWD/ST) na 1.33 1.31 BOC13 to (EOR-2200 MWD/ST)

Turbine Bypass (TBOOS) 1.36 1.31 BOC13 to (EOR-2200 MWD/ST)

Recirculaton Pumn TaP (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 (1.08 SLMCPR). Increase any value shown by 0.02 for Single Loop Operation (SLO.SLMCPR=1.10).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with normal Feedwater Heating.

. h TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 26 Figure 15 MCPR Operating Limit for All GE11 & GE13 Bundles Optional forAII Cycle Exposures -RequiredafterEOR-2200 MWD/STI reached (see note 3) 1 46 1 45 -

144-1.43-1A2 1A2 -

= A1 Ao U. 1.41 -

a.1 1.39-

-JE 1 383 1 37-E O. 1.36-0

a. 1.35-U 1.34-1 33-1.32-1 31 1.30 TBOOS & RPTOOS

.RPTOOS Turbine Bypass and Recirculat:lon:P~unpTri In-Servica J

_~~~~

0 Option B 0 1 0.2 03 04 05 06 07 08 09 1

Option A Tau (r)

.DU%- ) LU CVV 1,3 1

Icla I

.o I

.id I I

BO13 to EOC13 I

Turbine Bypass (TBOOS) 1.38 l

1.35 BOC13 to EOC13 Recirculation Pump Trip(RPTOOS) 1.40 1.32 BOC13 to EOC13 l

TBOOS and RPTOOS 1.45 1

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 0.02 for Single Loop Operation (SLO:SLMCPR=1.1 0).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with normal Feedwater Heating.

TVA Nuclear Fuel TVA-COLR-BF2C 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 MWD/ST (see note 3) 1.52 -

151 1 50 4

4.

149 1.48 a147 r 1.46 -

TBOOS & RPTOOS 1A5

°1.44

...4 /......

oE IRPT OSE-c1.42 a1 4

Ir 1

40 1.37 v

136 -"

135

.Turbine 131pass and Recirculation Punp Tr In-Service I.34

..... I.,.,..I.j.j.I.I 0

01

.2 03 04 0.5 06 07 08 09 1

Option B Option A Tau (T)

BOC13 to (EOR-2200 MWD/ST) na 1.38 1.35 BOC13 to (EOR-2200 MWDIST)

Turbine Bypass (TBOOS)

I 1.42 I 1.39 OC13 to (EOR-2200 MWD/ST)

Recirculaton Pum Tn RPTOOS 1.47 1.36 BOC13 to (EOR-2200 MWD/ST)

TBUU and RPIOD5 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=1.1 0).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with normal Feedwater Heating.

TVA Nuclear Fuel TVA-COLR-BF2C 13 Core Operating Limits Report Revision 0, Page 28 Figure 17 MCPR Operating Limit for All GE14 Bundles OptionalforAll Cycle Exposures - RequiredafterEOR-2200 MWD/STIsreached (see note 3) 1.65 1.64..

1.63.

162.

161.

160 1 59 1 58 y

1 57 t57 TBOOS & RPTOOS Ib.5.....'....b,

^

o 1.55 1.54

¢,..

1 1.53 1.512

_-^.

X.

~1.51 A\\

r 50 RPTOOS t

49 O1.48,

0 C 1 47 t 1 46 1.45

-~~..

_ v..

--v.

1 44

-v...

v-144 143 Turbine pass and Recirculatlon Punp Trip In-Servce 1 42 1.40 1.38 0

01 02 03 04 05 0.6 0.7 08 09 t

Option B Option A Tau (T)

I

?...

.....4 BOC13 to EOC13 na 1.42 1.39 80C13 to EOC13 Turbine Bypass (TBOOS) 1.47 1.44 BOC13 to EOC13 Recirculation Pump Tnp (RPTOOS) 1.59 1.42 BOC 3 to EOC1 3 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=1.10).
3. EOR refers to the end of Full Power Capabilityat Rated Flow with normal Feedwater Heating.

4.,

S t

I TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C13 Revision 0, Page 29 Figure 18 Power Dependent MCPR(P) Limits

-(UT EL i e

U-SV

?SC I(

U 4 2 4

.2

38 TBOOS >50%ComeFlow 3

l..

A_

2.6 2.6

.5 2.4..

22

'TBIS >50% Core Flo.

1 8 TBIS 150% Com F..

16

'.1 1.4 1 2

__ A...

1 2.-

0 10 20 30 40 50 60 Power (% Rated) 70 80 90 100 110 Below Pbypass (30% Rated Power) the Value Is dependent Upon whether the I

Turbine Bypass System Is In-Service (TBIS) or Out-Of-Service (TBOOS)

I OPERATING LIMIT MCPR(P) = Kp

Below Core Monitoring Power Threshold (25% Rated Power)

For P < 25%

NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED Below Pbvoass with Turbine Bypass System In-Service (TBIS)

For 25% ' P <

30%

MCPR(P) = 2.09 + 0.022(30%-P)
MCPR(P) = 2.31 + 0.034(30%-P)

Below Pbvpass with Turbine Bypass System Out-Of-Service (TBOOS)

For < 50% CORE FLOW For >

50% CORE FLOW For 5 50% CORE FLOW For >

50% CORE FLOW For 25%

F P <

30%

MCPR(P) = 2.55 + 0.072(30%-P)
MCPR(P) = 3.35 + 0.102(30%-P)

Above Pbvrass For 30% 5 P < 45%

For 45% 5 P < 60%

For 60% < P

Kp = 1.28 + 0.01340(45%-P)
Kp = 1.15 + 0.00867(60%-P)
Kp = 1.00 + 0.00375(100%.P)

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

Note: The OLMCPR below Pbypass Is based upon the dual recirculation loop SLMCPR of 1.08.

Add 0.02 to the OLMCPR in Single Loop Operation [SLMCPR(for SLO) = 1.10].

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C 13 Revision 0, Page 30 (Final)

Figure 19,

t +

Flow Dependent MCPR Operating Limit - MCPR(F) 1 6 1 5 1.4 12 1 1 30 40 50 60 70 80 90 100 Core Flow (V. Rated)

For Wc > 30%

MCPR(F) = MAX(1.21, Af*Wcd100 + Bf)

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

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 1.08.

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

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