ML021140333

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Core Operating Limits Report for Cycle 11 Operation
ML021140333
Person / Time
Site: Browns Ferry 
(DPR-068)
Issue date: 04/15/2002
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TVA-COLR-BF3C11, Rev. 0
Download: ML021140333 (31)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 15, 2002 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Stop OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of

)

Docket No.

50-296 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 -

CORE OPERATING LIMITS REPORT -

FOR UNIT 3 CYCLE 11 OPERATION In accordance with the requirements of Technical Specification 5.6.5.d, enclosed is Revision 0 to the Unit 3 Cycle 11, Core Operating Limits Reports (COLR).

There are no new commitments contained in this letter.

If you have any questions, please contact me at (256) 729-2636.

cerely, T. E. Abn Manage icensin Industry Affarrs Encle~ure cc :

S e- - -aq Pinted on recycled paper

U.S. Nuclear Regulatory Commission Page 2 April 15, 2002 Enclosure cc (Enclosure):

Mr.

Paul E.

Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W.,

Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant P.O.

Box 149 Athens, Alabama 35611 Mr. Kahtan 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 3 CORE OPERATING LIMITS REPORT (COLR),

REVISION 0 FOR CYCLE 11 OPERATION (SEE ATTACHED)

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C I1 Revision 0, Page 1 Browns Ferry Nuclear Plant Unit 3, Cycle 11 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By:

Verified By:

Approved By:

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

  • ,mres F. Lemons, Manager BWR Fuel Engineering Date:

Date:

3/27/0 2 Date:

3L2-7162 Reviewed By:

Reviewed By:

Date:

___2 __/2 Date: __________

Revision 0 (3/27/2002)

Initial Issue Pages Affected: All

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 2 Pages Affected: All

TVA Nuclear Fuel Core Operating Limits Report Revisio Date n

0 TVA-COLR-BF3C 11 Revision 0, Page 3 Revision Log Description Initial Release for New Cycle Affected Pages All 3/27/2002

  • TVA Nuclear Fuel TVA-COLR-BF3 C 1I Core Operating Limits Report Revision 0, Page 4
1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 11 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 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 3, Cycle 11 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-BF3C 11 Core Operating Limits Report Revision 0, Page 5

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 1-6. The APLHGR limits for the GE 13 and GE 14 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.

.jt1,.5-r" 1"11.J5) //-I IUJL GE13-P9HTB386-12GZ GE13-P9DTB400-13GZ1 GE13-P9DTB414-15GZ GE14-P 1ODNAB402-15GZ GE14-PlODNAB401-14GZ 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 7 (reference 11). Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 8 (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 1-6 are applicable for both Turbine Bypass In Service (TBIS) and Out-Of-Service (TBOOS). The off-rated power corrections

[MAPFAC(P)] in Figure 7 contain separate limits to be applied below Pbypass (30% rated power) for TBIS or TBOOS. The off-rated flow corrections

[MAPFAC(F)] in Figure 8 bound both TBIS and TBOOS operation.

The APLHGR limits in Figures 1-6 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 7 and 8 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 multiplier to be applied to this cycle is 0.84 for GE13 and 0.93 for GEl4 (both found in reference 3). It is not necessary to apply both the off-rated MAPFAC and SLO multiplier corrections at the same time.

-r*r.iTl*-*p-7*l 1 1,ir'lr7

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 6

TVA Nuclear Fuel TVA-COLR-BF3C11 Core Operating Limits Report Revision 0, Page 7

3. LHGR LIMIT (TECHNICAL SPECIFICATION 3.2.3)

The LHGR limit is fuel type dependent. For Unit 3 Cycle 11 there are two (2) fuel types in the core, GEl3 and GE14. The limits for these types are given below:

GE13 4-14.4 kw/ft 13.4 kw/ft GE14

  • TVA Nuclear Fuel TVA-COLR-BF3C11 Core Operating Limits Report Revision 0, Page 8
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 9 - 12, as defined in the following table:

[F-4I Type, ýI Eo*s*0 e Ran&e il I

U 9.:i, GEl3 BOC to EOR-1800 MWD/ST e:i*

GE13 BOC to EOC Fiiigwl:

GE14 BOC to EOR-1800 MWD/ST M4Z 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 10 and 12 limits at any point in the cycle.

As noted in the footnotes of Figures 9 through 12, 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 (ref. 10):

T ave

-TB "i = 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 i=1 Tave

n "TB

=

Jt+1.65.

[n*-]

where; jt = 0.830 sec (mean scram time used in transient analysis based on dropout time for notch position 36)

S= 0.019 sec (standard deviation of ýi)

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

  • TVA Nuclear Fuel TVA-COLR-BF3 C 11 Core Operating Limits Report Revision 0, Page 9 "ri = Scram time (dropout time) from fully withdrawn to notch position 36 for the i' rod
b. Startup Limits: Option A OLMCPR limits (1T=1.0) shall be used prior to the determination of T1 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 13 and 14, 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.

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 9 through 12. Additionally an off-rated MCPR(P) correction from Figure 13 (references 11 & 12) shall be applied for TBOOS when the power is below Pbypass.

e. Single Loop Operation (SLO) Limits: As noted in section 4. a above, a correction of 0.02 is to be applied to the OLMCPR(100) limits for SLO as described in the footnotes of Figures 9 through 12. The same adder applies to the off-rated MCPR(F) as noted in the footnote to Figure 14 and to the MCPR(P) value below Pbypass from Figure 13.

STVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3Cl 1 Revision 0, Page 10

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:

SRB =

MWt)

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

I

. TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 11

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):

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 1.30 (using a safety limit of 1.07), as reported in references 6, 7, and 8.

This is equivalent to the cycle specific minimum Option B MCPR operating limit of 1.31 (using a safety limit of 1.08).

(2)

The unfiltered setpoints are consistent with a nominal RBM fiter 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:

Notes: (1) dual loop operation single loop operation dual loop operation (2)

The MCPR values shown correspond to a SLMCPR of 1.08 for dual recirculation loop operation and 1.10 for single loop operation.

> 27% and < 90%

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

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

> 90%

< 1.41 (g)

  • TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 12 (2)

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

STVA Nuclear Fuel TVA-COLR-BF3C11 Core Operating Limits Report Revision 0, 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.

SDM > 0.38% dk/k

  • TVA Nuclear Fuel TVA-COLR-BF3C11 Core Operating Limits Report Revision 0, Page 14
8. REFERENCES
1. NEDE-24011-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. Jil-03963SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 10 Cycle 11", March 2002.
4. Jil-03963MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 3 Reload 10 Cycle 11", March 2002.
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 1.GE-NE-L12-00889-00-01P Revision 0, "GEl4 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]

TVA-COLR-BF3 Cl1

  • TVA Nuclear Fuel Core Operating Limits Report Revision 0, Page 15 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB372-11GZ (GE13) nal.

4 I

4 uu 4

4 00 00o 00 00 00 00o ACCEPTABLE OPERATION 1

4

1-4 4

.4.

1 4

4 4

+

4 4

4 4

1-

+

+

4 4

4-4

+

4 4

.4-

+

10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 0.0 50.0 Most Limiting Lattice for Each Exposure Point 0.0 10.71 1

7.0 i

12.10 25.0 11.14 09 1077.

80.

12.26 30.0 10.67

.24

1. 0..

1 0.8 9

,9

.0 i.12

.3 6 2.0 i

11.06 100 i

12.50 40.0 i

9.85 3.0 11.25 12.5 12.73 45.0

. 9.49

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

........:~ i*......

i :.....................

  • 5........................ o.........................

i.......... ;.....

4.0 11.44 15.0 12.66 50

9. 5 60.18 0

11 8

57........679 8.47 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.

15.
14.
13.
12.
11.

10.

8.

7.

.-E

'-r 6.00 5.00 4.00 3.00 2.00 1.00 0.00 VU UU nt'l I

. TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 16 Figure 2 APLHGR Limits for Bundle Type GE13-P9HTB386-12GZ (GE13) 10.0 15.00 14.00 13.00 12.00 11.00 10.00 9.00 8.00 7.00 6.00 5.00 4.00 3.00 2.00 1.00 0.00 40.0 20.0 30.0 Cycle Exposure (GWD/ST) 50.0 Most Limiting Lattice for Each Exposure Point U.U IU.i3 0.2 i

10.94 1.0 i

11.08 2.0 i

11.25 3................

Y o................

0..........

S.............

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

.....0..

............................ !..5................

4.0 11.57 5.0 1172 6....................................

I.......... 11...........

88 7.0 12.03 S........

8.0 i

12.19 9 0 i

12.36 10.0 i

12.51

  • ......... 12:5........

12.53 It5.0............................... 2.2....................

S...................................................................

15.0 12.27 17.5.....

... 11.94....

20.0 11.62 S25.0

.* 10.99 30.0 i

10.57 35.0 10.1.7 40.0 9.79 S....................o.....

9 -. -.......

  • 450 9.42 S.......................~~~~~.......

50.0..

9.06 55.0 8.68 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.

U*NACCEPTABLE OPERATION

  • ACEPTABLE O PERATI OLN

-J 0

-J 0.

0.0

  • TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3Cl 1 Revision 0, Page 17 Figure 3 APLHGR Limits for Bundle Type GE13-P9DTB400-13GZ1 (GE13) 10.0 15.00 14.00 13.00 12.00 11.00 10.00 9.00 8.00

.E

-I00

-J I. 6.00 5.00 4.00 3.00 2.00 1.00 0.00 40.0 20.0 30.0 Cycle Exposure (GWD/ST) 50.0 Most Limiting Lattice for Each Exposure Point S................o..0...................................

S................... 2.

1.0 i

10.72 2.0 10.87 S.......................................

S............................3.0 3.0 11.26 1126 5.0 I

11.46 S.........6 o.0

............ 1*161....

S...................................... i...........

I.T

.,9 4 ~

9. U...

1..

90 i

12.13 10.00 12.30 125..

1-2.47....

2.

1

  • r 15.0 1239

.75 12.18 18................"

1.1.24 30.0 i

106 S....................:*..............

S................... '.

o..................I ....... 9 i...

45.0 9.10 50.0..

8.71 55.0.

..0 8.39 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.

,UNACCEPTABLE OPERATION

  • ACCEPTABLE OPERATION*

0.0 6.0

  • TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 18 Figure 4 APLHGR Limits for Bundle Type GE13-P9DTB414-15GZ (GE13) 00 00 oo QNACCEPTABLE OPERATION 00 00 00 00 00 (ACCEPTABLE OPERATION) 7.00 flA.4-I

+

1 1

10.0 20.0 30.0 40.0

.00

.00

.00

.00

.00-0.0 50.0 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point 0.0 10.40 7.0 11.43 25.0 11.09 1 0 4 6.....

.I. 8..........................

3 0......

1 0o.

.o

............... 7.....

.................... I............................................................

3.0 10.88 12.5 11.8945092 4.0 i

11.04 15.0 11.95 50.0 8.85 5.0 11.18

17.

11.80 55.0 8.4.3 60.13 008 155

-781-8.20 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.

15.'

14.
13.
12.

11..

10.

9.

8.

n,'

-J 1a 4

C 5

4 3

2 1

I aJ~

TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C1 I Revision 0, Page 19 Figure 5 APLHGR Limits for Bundle Type GE14-P1ODNAB402-15GZ (GE14) 00o (U.NACCEPTABLE OPERATION*

00 00 s

00 00 00 00

__________________ I

_______________-.

__________________ I

___________________ I 4

4

.4 I.

f 4

.4

1 L

4 4

.4

1

10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0 Most Limiting Lattice for Each Exposure Point 0.2 9.61 1.0 9.68 2.0 9.82 3 0 9.99 40 10.18 5.0 10.38 6.0 10.58 8.0

10. 8 11.0 11.04.8.

11.0 11.04 15.0 11.04 25.0 0 10.50 30.0 10.10 35.0 9.66 45.0 8.59 50.0 8.03 3....

5783 492 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.

12.
11.

10.

9.
8.
7.
6.
5.

A E

-I 0o 3.00 2.00 1.00 0.00 0.0 70 10.72 I

  • TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3CI I Revision 0, Page 20 Figure 6 APLHGR Limits for Bundle Type GE14-P1ODNAB401-14GZ (GE14) 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point 0.2 967

i.....

1.0 9.73 S2.0 9.86.

S..

.3.0 10.01 8 0 10.67 190.1.7 120 in 10.

1i:l 10g.q 20.0 10.87 25.0 10.5*0.....

30.0 10.10 9............

6 4

..,64 40.0 9.11

......................... 8.5 45.0 8.57 5.0 4.0371098050.0 8.03 6.0 10.50 15.0 10.99 5 55.0 6.30 7.0 10.58 17.0 10.99 57.72 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.

14.00 13.00 12.00 11.00 10.00 9.00 8.00 7.00 6.00 5.00 4.00 3.00 2.00 1.00 0.00 E

-j.I 0.0

  • TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3Cl 1 Revision 0, Page 21 Figure 7 Power Dependent MAPLHGR Factor - MAPFAC(P) 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 Turbine Bypass System is In-Service (TBIS) or Out-Of-Service (TBOOS)

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

For 25% > P NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED Below Pbypass with Turbine Bypass System In-Service (TBIS)

For 25% < P < 30%

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

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

Below Pbypass with Turbine Bypass 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%)

Above Pbypass For 30% < P For <

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

50% CORE FLOW For >

50% CORE FLOW

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

These Curves Bound both the Recirculation Pump Trip In-Service (RPTIS) and Out-Of-Service (RPTOOS) 4 U-

.TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 22 Figure 8 Flow Dependent MAPLHGR Factor - MAPFAC(F) 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:

1 102.5 1

0.6784 1

0.4861 107.0 0.6758 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).

LL IL 0.9 0.8 0.7 0.6 0.5 0.4 MAX FLOW= 102.5%

S~MAX FLOW = 107%

30

.TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 23 Figure 9 MCPR Operating Limit for All GE13 Bundles For Cycle Exposures up to EOR-1800 MWD/ST (see note 3) 1.41 1.40 1.39

-1.38 a

S1.37 0

-J 0 Z 1.36 S1.35 o 1.34 S1.33 1.32 1.31 1.30 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

n,+i-, M Option A Tau (T)

ECXI11 to (LU( -IbUU MVVU/Z I) na 1

1.54 1.1 BOC11 to (EOR-1800 MWIDIST)

Turbine Bypass (TBOOS) 1.38 1.33 BOC11 to (EOR-1800 MWVD/ST)

Recirculation Pump Trip (RPTOOS) 1.36 1.31 BOCI1 to (EOR-1800 MWD/ST)

TBOOS and RPTOOS 1.40 1.35 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 Capability at Rated Flow with normal Feedwater Heating.

TBOOS & RPTOOS TbeOOS and e

ua pT i

Q urbine gtpass and -Recirculation Pump Trip In-Service

.TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C I Revision 0, Page 24 Figure 10 MCPR Operating Limit for All GE13 Bundles Optional for AlI Cycle Exposures -Required after EOR-1800 MWD/ST is reached (see note 3) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

Option B Option A Tau (t)

BO(11 to 1-U(11 BOCI1 to EOC1I BOC11 to EOC11 BOC11 to EOCI1 1.34 I1 Turbine Bypass (TBOOS)

Recirculation Pump Trip (RPTOOS)

TBOOS and RPTOOS 1.36 1 36 1.33 1 40 14 1 3 1 4A 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=I.10).
3. EOR refers to the end of Full Power Capability at Rated Flow with normal Feedwater Heating.

0

-J 0

n

0.
0.

U 1.31 1.33 1.32 1 37 I 1 34 1.31

.TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 25 Figure 11 MCPR Operating Limit for All GE14 Bundles For Cyde Exposures up to EOR-1800 MWDIST (see note 3) 1.55 1.54 1.53 C

9L E

0..

Q, 0

o.

'U

'U 1.52 1.51 I.5o CTBOOS & RPTOOS 1.49-\\..i 1.48 1.47-RP

- o ""

1.45 1.44 1.43 -

1.42 TBOOS 1.40 1.391 1.38

-\\

1.37 1.36 Turbine Bypass and Recirculatlon Pump Trip In-Service 0

Option B 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

Option A Tau (T)

T)I Recirculation Pump Trip (RPTOOS) I 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 Capability at Rated Flow with normal Feedwater Heating.

--4 1

-TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C 11 Revision 0, Page 26 Figure 12 MCPR Operating Limit for All GE14 Bundles Optional for All Cycle Exposures - Required after EOR-1800 MWDIST is reached (see note 3) 0 O.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

Option B Option A Tau Cl to EOC11 Cl to EOC11 Cl to EOC11 Cl1 to FOCl1 na Turbine Bypass (TBOOS)

Recirculation Pump Tri RPTOOSQ TBOOS and RPTOOS 1.41 1.47 1.60 1.65 1.38 1.44 1.43 1.48 I 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 Capability at Rated Flow with normal Feedwater Heating.

a a

0.

-J 0

-z n

(U

-TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF30C 1 Revision 0, Page 27 Figure 13 Power Dependent MCPR(P) Limits C

V, I. -J o0 AU V.

2U 12A 4

3.8 3.6 3.4 3.2 3

2.8 2.6 2.4 2.2 2

1.8 1.6 1.4 1.2 0

10 20 30 40 50 Power (% Rated) 60 70 80 90 100 Below Pbypass (30% Rated Power) the Value is dependent Upon whether the Turbine Bypass System Is In-Service (TBIS) or Out-Of-Service (TBOOS)

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 Pbypass 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 Pbypass with Turbine Bypass System Out-Of-Service (TBOOS)

For 25% < P<

30%

Above Pbypass For 30% < P<45%

For 45% < P<60%

For 60% < P MCPR(P) = 2.55 + 0.072(30%-P)

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

Kp = 1.28 + 0.01340(45%-P)

Kp = 1.15 + 0.00867(60%-P)

Kp = 1.00 + 0.00375 (1 00%-P)

For <

50% CORE FLOW For >

50% CORE FLOW For <

50% CORE FLOW For >

50% CORE FLOW 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].

TBOOS: >50% Core Flow A

I I

I TBOS: _<50% Core Flow TBIS: >50% Core Flow

_TBIS:

<50% Core Flow-I I

.TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF3C l1 Revision 0, Page 28 (Final)

Figure 14 Flow Dependent MCPR Operating Limit - MCPR(F) 1.6 1.5 1.4 A.

C, 1.3 1.2 1.1 40 50 60 70 Core Flow (% Rated)

For Wc

> 30%

80 90 100

MCPR(F) = MAX(1.21, Af*Wcll00 + Bf)

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

1 102.5 1

-0.576 1

1.670 107.0

-0.591 1.713 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).

MMX FLOW= 107%

MAX FLOW 102.5%

30

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