L-07-137, Core Operating Limits Report, COLR 19 and COLR 19-1

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Core Operating Limits Report, COLR 19 and COLR 19-1
ML073030063
Person / Time
Site: Beaver Valley
Issue date: 10/25/2007
From: Sena P
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-07-137
Download: ML073030063 (323)
v • d • e


Text

FENOC FirstEnergy Nuclear Operating Company Peter P. Sena 111 724-682-5234 Site Vice President Fax: 724-643-8069 October 25, 2007 L-07-137 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Core Operating Limits Report, COLR 19 and COLR 19-1 FirstEnergy Nuclear Operating Company (FENOC) hereby submits two revisions of the Core Operating Limits Report (COLR) for Beaver Valley Power Station (BVPS) Unit No. 1, as required by Section 5.6.3 of the BVPS Technical Specifications. The BVPS Unit No. 1 COLR 19 and COLR 19-1 are enclosed. Unit No. 1 COLR 19, effective October 5, 2007, was issued to reflect the original Unit 1 Cycle 19 core design. Unit No.

1 COLR 19-1, effective October 20, 2007, reflects the replacement of four fuel assemblies in the original Cycle 19 core design.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

FENOC Fleet Licensing, at 330-761-6071.

Sincerel,,

Peter P. Sena III

Enclosures:

A Beaver Valley Power Station Unit No. 1, Core Operating Limits Report, COLR 19 B

Beaver Valley Power Station Unit No. 1, Core Operating Limits Report, COLR 19-1 k3 CO I

Beaver Valley Power Station, Unit No. 1 COLR 18-4 L-07-137 Page 2 c:

Ms. N. S. Morgan, NRR Project Manager Mr. D. L. Werkheiser, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

L-07-137 Enclosure A Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 19

Licensing Requirements Manual Core Operating Limits Report 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report This Core Operating Limits Report provides the cycle specific parameter limits developed in accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 5.6.3.

5.1.1 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1.

5.1.2 SHUTDOWN MARGIN (SDM)

a.

In MODES 1,2, 3, and 4, SHUTDOWN MARGIN shall be 1.77% Ak/k.(1)

b.

Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to _> the MODE 5 boron concentration and shall remain > this boron concentration at all times when this signal is blocked.

c.

In MODE 5, SHUTDOWN MARGIN shall be 2! 1.0% Ak/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a.

Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.

b.

Lower Limit'- MTC shall be maintained less negative than - 4.4 x 10-4 Ak/k/°F at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 37 pcm/°F)

d.

60 ppm Surveillance Limit: (- 43 pcm/°F) 5.1.4 LCO 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.(2) 5.1.5 LCO 3.1.6 Control Bank Insertion Limits

a.

Control Banks A and B shall be withdrawn to at least 225 steps.(2)

b.

Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.(2)

c.

Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.

d.

Overlap Limits(2) - Overlap shall be such that step 129 on banks A, B, and C corresponds to step 1 on the following bank. When C bank is fully withdrawn, these limits are verified by confirming D bank is withdrawn at least to a position equal to the all-rods-out position minus 128 steps.

(1) The MODE 1 and MODE 2 with keff 1.0 SDM requirements are included to address SDM requirements (e.g., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).

(2) As indicated by the group demand counter COLR Cycle 19 Beaver Valley Unit 1 5.1 -1 LRM Revision 59

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.6 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

The Heat Flux Hot Channel Factor - FQ(Z) limit is defined by:

FQ(Z) _ [CFQ*

K(Z) for P > 0.5 FQ(Z)

CFQI *K(Z) forP <0.5 L0.5J Where:

CFQ = 2.40 P =

THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

c M

FQ(Z) = FM(Z)

  • 1.0815 FQ(Z) = F6c(Z)* W(Z)

The W(Z) values are provided in Table 5.1-1.

The FQ(Z) penalty function, applied when the analytic FQ(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-2.

5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FANH)

N FH _< CFAH* (1 +PFAH (l-P))

Where:

CFAH = 1.62 PFAH =

0.3 P

THERMAL POWER RATED THERMAL POWER COLR Cycle 19 Beaver Valley Unit 1 5.1 -2 LRM Revision 59

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)

The AFD acceptable operation limits are provided in Figure 5.1-4.

5.1.9 LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 1 and 2

a.

Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint K1 _ 1.242 Overtemperature AT reactor trip setpoint Tavg K2 _ 0.0183/°F coefficient Overtemperature AT reactor trip setpoint pressure K3 _ 0.001/psia coefficient Tavg at RATED THERMAL POWER T' < 577.9°Fo)

Nominal pressurizer pressure P'_> 2250 psia Measured reactor vessel average temperature lead/lag

-t1 -> 30 secs time constants t12_< 4 secs Measured reactor vessel'AT lag time constant T4 - 6 secs Measured reactor vessel average temperature lag T5 - 2 secs time constant f (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i)

For qt - qb between -37% and +15%, f(AI) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(1)

T' represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 19 Beaver Vallev Unit 1 5.1 -3 LRM Revision 59

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 (ii)

For each percent that the magnitude of (qt - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.

(iii)

For each percent that the magnitude of (qt - qb) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.

b.

Overpower AT Setpoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant K4*< 1.085 K5 _Ž 0.02/°F for increasing average temperature K5 = 0/0F for decreasing average temperature K6 _ 0.0021/OF forT > T" K6 0/°F for T* T" T"

577.9°F(2)

T3 - 10 secs T4 < 6 secs T5 - 2 secs (2)

T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1

  • 5.1 - 4

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.10 LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Pressurizer Pressure Reactor Coolant System Total Flow Rate Tavg < 581.5°F(

Pressure > 2218 psia(2)

Flow > 267,300 gpm(3)

(1)

The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6 0F) to the cycle specific full power T,vg used in the core design.

(2)

The pressurizer pressure value includes allowances for pressurizer pressure control' operation and verification via control board indication.

(3)

The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -5

Licensing Requirements Manual.

5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained > 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -6

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.12 References

1.

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).

2.

WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and, Thermal Overpower AT Trip Functions," September 1986.

3.

WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (Westinghouse Proprietary).

4.

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification," February 1994.

5.

WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"

October 1999.

6.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"

April 1995 (Westinghouse Proprietary).

7.

WCAP-15025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.

8.

Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMWTM System," Revision 0, March 1997.

9.

Caldon, Inc. Engineering Report-1 60P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM-TM System," Revision 0,.

May 2000.

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -7

Licensing Requirements Manual Core Operating Limits Report 5.1 670 F-0 0.2 0.4 0.6 0.8 1

1.2 FRACTION OF RATED THERMAL POWER 1.4 Figure 5.1-1 (Page 1 of 1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -8

Licensing Requirements Manual Core Operating Limits Report 5.1 200 150 100 50 0

0 20 40 60 80 Relative Power (Percent) 100 Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -9

Licensing Requirements Manual 1.2 0.0, 1.00 1.0 0.8 S0.6 0.4 0.2 0.0 Core Operating Limits Report 5.1 0

2 4

6 8

10 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FaT NORMALIZED OPERATING ENVELOPE, K(Z) 12 COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -10

Licensing Requirements Manual 120 110 100 UNACCEPTABLE 90 OPERATION 80 Core Operating Limits Report 5.1 0,

0L E~

70 60 50 40 30 20 10 0

-60

-40

-20 0

20 40 Axial Flux Difference (Delta I)%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC 60 COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -11

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)

Fa Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1

12.0 1.0000 1.0000 1.0000 1.0000 2

11.8 1.0000 1.0000 1.0000 1.0000 3

11.6 1.0000 1.0000 1.0000 1.0000 4

11.4 1.0000 1.0000 1.0000 1.0000 5

11.2 1.0000 1.0000 1.0000 1.0000 6

11.0 1.0000 1.0000 1.0000 1.0000

  • 7 10.8 1.0000 1.0000 1.0000 1.0000 8

10.6 1.1989 1.2524 1.2759 1.2468 9

10.4 1.1850 1.2495 1.2651, 1.2279 10 10.2 1.1714 1.2401 1.2521 1.2103 11 10.0 1.1596 1.2292 1.2393 1.2023 12 9.8 1.1497 1.2190 1.2265 1.2035 13 9.6 1.1378 1.2091 1.2119 1.2080 14 9.4 1.1341 1.1994 1.2028 1.2136 15 9.2 1.1349 1.1889 1.1983 1.2183 16 9.0 1.1332 1.1783 1.1923 1.2207 17 8.8 1.1441 1.1770 1.1993 1.2259 18 8.6 1.1583 1.1795 1.2108 1.2329 19 8.4 1.1685 1.1842 1.2191 1.2413 20 8.2 1.1770 1.1863 1.2251 1.2505 21 8.0 1.1832 1.1868 1.2287 1.2566 22 7.8 1.1872 1.1857 1.2299 1.2599 23 7.6 1.1891 1.1829 1.2288 1.2607 24 7.4 1.1891 1.1788 1.2256 1.2590 25 7.2 1.1872 1.1745 1.2203 1.2549 26 7.0 1.1835 1.1700 1.2131 1.2484 27 6.8 1.1783 1.1643 1.2041 1.2399 28 6.6 1.1715 1.1571 1.1935 1.2292 29 6.4 1.1634 1.1487 1.1814 1.2171 30 6.2 1.1541 1.1391 1.1680 1.2060 Note: Top and Bottom 10% Excluded COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -12

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 of 2)

FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU 31 6.0 1.1440 1.1289 1.1532 1.1965 32 5.8 1.1317 1.1166 1.1386 1.1863 33 5.6 1.1274 1.1112 1.1263 1.1742 34 5.4 1.1380 1.1187 1.1175 1.1650 35 5.2 1.1472 1.1246 1.1128 1.1660 36 5.0 1.1552 1.1295 1.1129 1.1674 37 4.8 1.1631 1.1342 1.1144 1.1664 38 4.6 1.1702 1.1383 1.1148 1-.1649 39 4.4 1.1767 1.1420 1.1149 1.1622 40 4.2 1.1826 1.1446 1.1145 1.1587 41 4.0 1.1880 1.1496 1.1147 1.1544 42 3.8 1.1923 1.1563 1.1173 1.1492 43 3.6 1.1967 1.1619 1.1225 1.1438 44 3.4 1.2047 1.1669 1.1270 1.1400 45 3.2 1.2148 1.1743 1.1294 1.1387 46 3.0 1.2240 1.1839 1.1381 1.1427 47 2.8 1.2340 1.1997 1.1553 1.1581 48 2.6 1.2504 1.2251 1.1744 1.1768 49 2.4 1.2752 1.2504 1.1935 1.1951 50 2.2 1.3012 1.2752 1.2123 1.2128 51 2.0 1.3257 1.2999 1.2306 1.2300 52 1.8 1.3495 1.3236 1.2481 1.2465 53 1.6 1.3718 1.3460 1.2646 1.2621 54 1.4 1.3919 1.3664 1.2797 1.2767 55 1.2 1.0000 1.0000 1.0000 1.0000 56 1.0 1.0000 1.0000 1.0000 1.0000 57 0.8 1.0000 1.0000 1.0000 1.0000 58 0.6 1.0000 1.0000 1.0000 1.0000 59 0.4 1.0000 1.0000 1.0000 1.0000 60 0.2 1.0000 1.0000 1.0000 1.0000 61 0.0 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 -13

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 1)

FQ(Z) Penalty Factor versus Burnup Cycle Burnup.(MWD/MTU)

FQ(Z) Penalty Factor 0-900 1.0202 901-4950 1.02 4951 -5550 1.0225

> 5550 1.02 Note:

The Penalty Factor, to be applied to FQ(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.

COLR Cycle 19 LRM Revision 59 Beaver Valley Unit 1 5.1 - 14

L-07-137 Enclosure B Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 19-1

Licensing Requirements Manual Core Operating Limits Report 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report This Core Operating Limits Report provides the cycle specific parameter limits developed in accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 5.6.3.

5.1.1 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1.

5.1.2 SHUTDOWN MARGIN (SDM)

a.

In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be > 1.77% Ak/k.(1)

b.

Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to > the MODE 5 boron concentration and shall remain > this boron concentration at all times when this signal is blocked.

c.

In MODE 5, SHUTDOWN MARGIN shall be > 1.0% Ak/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a.

Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3.1.3-1.

b.

Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 Ak/k/OF at RATED THERMAL POWER.

c.

300 ppm Surveillance Limit: (- 37 pcm/°F)

d.

60 ppm Surveillance Limit: (- 43 pcm/0 F) 5.1.4 LCO 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.(2) 5.1.5 LCO 3.1.6 Control Bank Insertion Limits

a.

Control Banks A and B shall be withdrawn to at least 225 steps.(2)

b.

Control Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.(2)

c.

Sequence Limits - The sequence of withdrawal shall be A, B, C and D bank, in that order.

d.

Overlap Limits(2) - Overlap shall be such that step 129 on banks A, B, and C corresponds to step 1 on the following bank. When C bank is fully withdrawn, these limits are verified by confirming D bank is withdrawn at least to a position equal to the all-rods-out position minus 128 steps.

(1) The MODE 1 and MODE 2 with keff > 1.0 SDM requirements are included to address SDM requirements (e.g., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).

(2) As indicated by the group demand counter COLR Cycle 19-1 Beaver Valley Unit 1 5.1 -1 LRM Revision 62

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.6 LCO 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

The Heat Flux Hot Channel Factor - FQ(Z) limit is defined by:

FQ(Z)

[CFQ]* K(Z) for P > 0.5 FQ(Z)

[CFQ]* K(Z) forP* 0.5 LO.5j Where:

CFQ = 2.40 P =

THERMAL POWER W RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

FC(Z) = F6 (Z) " 1.0815 FW(Z) = Fc(Z)* W(Z)

The W(Z) values are provided in Table 5.1-1.

The FQ(Z) penalty function, applied when the analytic FQ(Z) function increases from one monthly measurement to the next, is provided in Table 5.1-2.

5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FNH)

F N < CFAH * (1 + PFAH (1-P))

Where:

CFAH = 1.62 PFAH = 0.3 THERMAL POWER

= RATED THERMAL POWER COLR Cycle 19-1 Beaver Valley Unit 1 5.1 - 2 LRM Revision 62

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)

The AFD acceptable operation limits are provided in Figure 5.1-4.

5.1.9 LCO 3.3.1 Reactor Trip System Instrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 1 and 2

a.

Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint K1 < 1.242 Overtemperature AT reactor trip setpoint Tavg K2 > 0.0183/0F coefficient Overtemperature AT reactor trip setpoint pressure K3 > 0.001/psia coefficient Tavg at RATED THERMAL POWER T' < 577.9°01)

Nominal pressurizer pressure P' > 2250 psia Measured reactor vessel average temperature lead/lag T1 > 30 secs time constants t 2 -< 4 secs Measured reactor vessel AT lag time constant t 4 -< 6 secs Measured reactor vessel average temperature lag tc5 < 2 secs time constant f (Al) is a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i)

For qt - qb between -37% and +15%, f(AI) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(1)

T' represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 19-1 Beaver Valley Unit 1 5.1 - 3 LRM Revision 62

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 (ii)

For each percent that the magnitude of (qt - qb) exceeds -37%, the AT trip setpoint shall be automatically reduced by 2.52% of its value at RATED THERMAL POWER.

(iii)

For each percent that the magnitude of (qt - qb) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.

b.

Overpower AT Setpoint Parameter Values:

Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Value K4 *< 1.085 Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel average temperature rate/lag time constant Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lag time constant K5 >_ 0.02/°F for increasing average temperature K5 = 0/°F for decreasing average temperature K6 _ 0.0021/°F for T > T" K6 =0/F for T _< T" 7"_ 577.90F(2) 13 Ž- 10 secs 14 5 6 secs

  • 5 - 2 secs (2)

T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -4

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.10 LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Pressurizer Pressure Reactor Coolant System Total Flow Rate Tavg < 581.5°F(')

Pressure > 2218 psia(2)

Flow > 267,300 gpm(3)

(1)

The Reactor Coolant System (RCS) indicated Tavg value is determined by adding the appropriate allowances for rod control operation and verification via control board indication (3.6 0F) to the cycle specific full power Tavg used in the core design.

(2)

The pressurizer pressure value includes allowances for pressurizer pressure control operation and verification via control board indication.

(3)

The RCS total flow rate includes allowances for normalization of the cold leg elbow taps with a beginning of cycle precision RCS flow calorimetric measurement and verification on a periodic basis via control board indication.

COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -5

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.11 LCO 3.9.1 Boron Concentration (MODE 6)

The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained _> 2400 ppm. This value includes a 50 ppm conservative allowance for uncertainties.

COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -6

Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.12 References

1.

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).

2.

WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.

3.

WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (Westinghouse Proprietary).

4.

WCAP-1 0216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-F0 Surveillance Technical Specification," February 1994.

5.

WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"

October 1999.

6.

WCAP-1 2610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"

April 1995 (Westinghouse Proprietary).

7.

WCAP-1 5025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicating Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.

8.

Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM,/TM System," Revision 0, March 1997.

9.

Caldon, Inc. Engineering Report-1 60P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMJ1M System," Revision 0, May 2000.

COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -7

Licensing Requirements Manual Core Operating Limits Report 5.1 670 o1~

F-0 0.2 0.4 0.6 0.8 1

1.2 FRACTION OF RATED THERMAL POWER Figure 5.1-1 (Page 1 of 1)

REACTOR CORE SAFETY LIMIT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1) 1.4 COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -8

Licensing Requirements Manual 200 150 K0,]114 100 50 8,0 0-Core Operating Limits Report 5.1 0

20 40 60 80 Relative Power (Percent) 100 Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -9

Licensing Requirements Manual 1.2 0.0, 1.00 1.0 0.8 0.6 0.4 0.2 0.0 Core Operating Limits Report 5.1 0

2 4

6 8

10 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FaT NORMALIZED OPERATING ENVELOPE, K(Z) 12 COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -10

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110 100 90 80 0

0-n, 0-70 60 50 40 30 20 10 0

-60

-40

-20 0

20 40 Axial Flux Difference (Delta 1)%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC 60 COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -11

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)

FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1

12.0 1.0000 1.0000 1.0000 1.0000 2

11.8 1.0000 1.0000 1.0000 1.0000 3

11.6 1.0000 1.0000 1.0000 1.0000 4

11.4 1.0000 1.0000 1.0000 1.0000 5

11.2 1.0000 1.0000 1.0000 1.0000 6

11.0 1.0000 1.0000 1.0000 1.0000 7

10.8 1.0000 1.0000 1.0000 1.0000 8

10.6 1.1633 1.1809 1.2302 1.2354 9

10.4 1.1504 1.1709 1.2240 1.2152 10 10.2 1.1384 1.1588 1.2172 1.1948 11 10.0 1.1299 1.1482 1.2094 1.1826 12 9.8 1.1272 1.1458 1.2044 1.1845 13 9.6 1.1237 1.1435 1.1981 1.1863 14 9.4 1.1201 1.1395 1.1909 1.1856 15 9.2 1.1180 1.1344 1.1820 1.1857 16 9.0 1.1173 1.1292 1.1729 1.1885 17 8.8 1.1260 1.1331 1.1823 1.1884 18 8.6 1.1368 1.1430 1.1961 1.1931 19 8.4 1.1447 1.1531 1.2051 1.2044 20 8.2 1.1513 1.1605 1.2124 1.2142 21 8.0 1.1561 1.1659 1.2172 1.2217 22 7.8 1.1591 1.1693 1.2195 1.2269 23 7.6 1.1603 1.1707 1.2194 1.2298 24 7.4 1.1600 1.1702 1.2170 1.2304 25 7.2 1.1589 1.1681 1.2126 1.2289 26 7.0 1.1587 1.1646 1.2064 1.2254 27 6.8 1.1576 1.1597 1.1987 1.2224 28 6.6 1.1549 1.1536 1.1894 1.2192 29 6.4 1.1511 1.1463 1.1788 1.2142 30 6.2 1.1461 1.1379 1.1668 1.2074 Note: Top and Bottom 10% Excluded COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 - 12

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 of 2)

FQ Surveillance W(Z) Function versus Burnup Exclusion Axial Elevation 150 3000 10000 18000 Zone Point (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU 31 6.0 1.1406 1.1282 1.1533 1.1987 32 5.8 1.1319 1.1188 1.1397 1.1885 33 5.6 1.1280 1.1181 1.1269 1.1764 34 5.4 1.1360 1.1296 1.1167 1.1658 35 5.2 1.1449 1.1394 1.1139 1.1653 36 5.0 1.1530 1.1481 1.1163 1.1654 37 4.8 1.1607 1.1566 1.1223 1.1644 38 4.6 1.1677 1.1643 1.1271 1.1626 39 4.4 1.1741 1.1713 1.1315 1.1597 40 4.2 1.1800 1.1778 1.1353 1.1560 41 4.0 1.1847 1.1837 1.1387 1.1509 42 3.8 1.1906 1.1888 1.1417 1.1487 43 3.6 1.2000 1.1938 1.1443 1.1519 44 3,4 1.2115 1.2014 1.1465 1.1538 45 3.2 1.2222 1.2130 1.1487 1.1549 46 3.0 1.2335 1.2273 1.1504 1.1579 47 2.8 1.2477 1.2436 1.1573 1.1658 48 2.6 1.2641 1.2626 1.1749 1.1802 49 2.4 1.2801 1.2844 1.1921 1.1978 50 2.2 1.2948 1.3088 1.2088 1.2155 51 2.0 1.3108 1.3338 1.2256 1.2328 52 1.8 1.3304 1.3577 1.2424 1.2502 53 1.6 1.3515 1.3805 1.2592 1.2669 54 1.4 1.3707 1.4013 1.2746 1.2825 55 1.2 1.0000 1.0000 1.0000 1.0000 56 1.0 1.0000 1.0000 1.0000 1.0000 57 0.8 1.0000 1.0000 1.0000 1.0000 58 0.6 1.0000 1.0000 1.0000 1.0000 59 0.4 1.0000.

1.0000 1.0000 1.0000 60 0.2 1.0000 1.0000 1.0000 1.0000 61 0.0 1.0000 1.0000

.1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 -13

4 Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 1)

FQ(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)

FQ(Z) Penalty Factor 0-450 1.02 451 -1650 1.0309 1651 -4200 1.02 4201 - 5100 1.0225

> 5100 1.02 Note:

The Penalty Factor, to be applied to FQ(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 Effective Full Power Day (EFPD) interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.

COLR Cycle 19-1 LRM Revision 62 Beaver Valley Unit 1 5.1 - 14

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