L-12-140, Core Operating Limits Report, Cycle 22

Core Operating Limits Report, Cycle 22

ML12129A221
Person / Time
Site:	Beaver Valley
Issue date:	05/07/2012
From:	Harden P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-12-140
Download: ML12129A221 (18)

Text

FE DC Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Paul A. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 May 7, 2012 L-12-140 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, Cycle 22 Pursuant to the requirements of Beaver Valley Power Station (BVPS) Technical Specification 5.6.3, "Core Operating Limits Report (COLR)," FirstEnergy Nuclear Operating Company hereby submits the BVPS, Unit No.1, Cycle 22 COLR. The COLR went effective on April 26, 2012.

There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor - Fleet Licensing, at (330) 315-6808.

Enclosure:

Beaver Valley Power Station, Unit No.1, Core Operating Limits Report, COLR Cycle 22 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-12-140 Beaver Valley Power Station, Unit No.1, Core Operating Limits Report, COLR Cycle 22 (14 Pages Follow)

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% flklk.(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% flklk.

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 flklkloF at RATED THERMAL POWER.

c. 300 ppm Surveillance Limit: (- 37 pcm/oF)

d. 60 ppm Surveillance Limit: (- 43 pcm/oF) 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 0 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 0 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 0 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 keft ~ 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 22 Beaver Valley Unit 1 5.1 - 1 LRM Revision 78

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) ~ [C:Q]*K{Z) for P > 0.5 F (Z)

Q

~ [CFQ]*K{Z) 0.5 for P ~ 0.5 THERMAL POWER Where: CFQ =2.40 P = RATED THERMAL POWER K{Z) =the function obtained from Figure 5.1-3.

F5 (Z) =F~ (Z)

• 1.0815 F't (Z) =F5 (Z)

• W{Z)

The W{Z) values are provided in Table 5.1-1. The W{Z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is performed, the W{Z) values should be multiplied by the factor 1/P, when P > 0.5. When P is ~ 0.5, the W{z) values should be multiplied by the factor 1/{0.5), or 2.0. This is consistent with the adjustment in the FQ{Z) limit at part power conditions.

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 ( F~H)

Where: CFL\H = 1.62 PFL\H = 0.3 THERMAL POWER P = RATED THERMAL POWER COLR Cycle 22 Beaver Valley Unit 1 5.1 - 2 LRM Revision 78

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 i1T Parameter Values from Table Notations 1 and 2

a. Overtemperature i1 T Setpoint Parameter Values:

Parameter Overtemperature i1T reactor trip setpoint K1 s; 1.242 Overtemperature i1T reactor trip setpoint Tavg coefficient Overtemperature i1 T reactor trip setpoint pressure K3;;:: 0.001/psia coefficient Tavg at RATED THERMAL POWER Nominal pressurizer pressure P' ;;:: 2250 psia Measured reactor vessel average temperature leadllag 11;;:: 30 secs time constants 12 s; 4 secs Measured reactor vessel i1T lag time constant 14 s; 6 secs Measured reactor vessel average temperature lag 15 s; 2 secs time constant f (i1I) 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(i1I) = 0 (where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and % + qb is total THERMAL POWER in percent of RATED THERMAL POWER).

(1) T' represents the cycle-specific Fu" Power Tavg value used in core design.

COLR Cycle 22 Beaver Valley Unit 1 5.1 - 3 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report (ii) For each percent that the magnitude of (qt - qb) exceeds -37%, the ~ T 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 ~ T trip setpoint shall be automatically reduced by 1.47% of its value at RATED THERMAL POWER.

b. Overpower ~ T Setpoint Parameter Values:

Parameter Overpower ~ T reactor trip setpoint K4:s; 1.085 Overpower ~ T reactor trip setpoint Tavg K5 ;:::: 0.02/0F for increasing rate/lag coefficient average temperature K5 = O/OF for decreasing average temperature Overpower ~ T reactor trip setpoint Tavg K6;:::: 0.0021/0F for T > Til heatup coefficient =

K6 O/oF for T :s; Til Tavg at RATED THERMAL POWER T":s; 577.9°F(2)

Measured reactor vessel average 1:3 ;:::: 10 secs temperature rate/lag time constant Measured reactor vessel ~ T lag time 1:4 :s; 6 secs constant Measured reactor vessel average 1:5 :s; 2 secs temperature lag time constant (2) Til represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 22 Beaver Valley Unit 1 5.1 - 4 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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 Pressure;;::: 2218 pSia(2)

Reactor Coolant System Total Flow Rate 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°F) 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 22 Beaver Valley Unit 1 5.1 - 5 LRM Revision 78

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 22 Beaver Valley Unit 1 5.1 - 6 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 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 ~T and Thermal Overpower ~ T 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-F Q 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 LEFMf"M System," Revision 0, March 1997.

9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM"TM System," Revision 0, May 2000.

10. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM),"

Revision 0, January 2005.

COLR Cycle 22 Beaver Valley Unit 1 5.1 - 7 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 ~

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

COLR Cycle 22 Beaver Valley Unit 1 5.1 - 8 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1

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CONTROL ROD INSERTION LIMITS COLR Cycle 22 Beaver Valley Unit 1 5.1 - 9 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 1 0 . 0 , 1.00 J 16.0, 1.001 1.0 I 12.0, 0.925 I 0.8

~ 0.6 0.4 0.2 0.0 o 2 4 6 8 10 12 Core Height (feet)

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FQ T NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 22 Beaver Valley Unit 1 5.1 - 10 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110

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AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC COLR Cycle 22 Beaver Valley Unit 1 5.1 - 11 LRM Revision 78

Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of2)

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

• 1 12.08 1.0000 1.0000 1.0000 1.0000

• 2 11.88 1.0000 1.0000 1.0000 1.0000

• 3 11.68 1.0000 1.0000 1.0000 1.0000

• 4 11.47 1.0000 1.0000 1.0000 1.0000

• 5 11.27 1.0000 1.0000 1.0000 1.0000

• 6 11.07 1.0000 1.0000 1.0000 1.0000

• 7 10.87 1.0000 1.0000 1.0000 1.0000 8 10.67 1.1364 1.1639 1.2388 1.2382 9 10.47 1.1316 1.1708 1.2334 1.2233 10 10.27 1.1261 1.1673 1.2287 1.2088 11 10.06 1.1203 1.1671 1.2225 1.2022 12 9.86 1.1149 1.1645 1.2148 1.1957 13 9.66 1.1136 1.1594 1.2060 1.1881 14 9.46 1.1140 1.1538 1.1965 1.1798 15 9.26 1.1131 1.1465 1.1864 1.1719 16 9.06 1.1135 1.1429 1.1765 1.1729 17 8.86 1.1219 1.1394 1.1812 1.1756 18 8.66 1.1341 1.1322 1.1941 1.1819 19 8.45 1.1431 1.1266 1.2023 1.1951 20 8.25 1.1506 1.1311 1.2088 1.2067 21 8.05 1.1564 1.1367 1.2131 1.2158 22 7.85 1.1603 1.1402 1.2150 1.2225 23 7.65 1.1625 1.1423 1.2147 1.2266 24 7.45 1.1630 1.1428 1.2122 1.2283 25 7.25 1.1621 1.1422 1.2077 1.2278 26 7.05 1.1610 1.1413 1.2024 1.2252 27 6.84 1.1592 1.1398 1.1962 1.2216 28 6.64 1.1560 1.1371 1.1890 1.2173 29 6.44 1.1518 1.1335 1.1803 1.2114 30 6.24 1.1464 1.1288 1.1701 1.2037 31 6.04 1.1399 1.1231 1.1588 1.1943 32 5.84 1.1331 1.1171 1.1461 1.1834 Note: Top and Bottom 10% Excluded COLR Cycle 22 Beaver Valley Unit 1 5.1 - 12 LRM Revision 78

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) MWO/MTU MWO/MTU MWO/MTU MWO/MTU 33 5.64 1.1279 1.1130 1.1329 1.1708 34 5.44 1.1252 1.1128 1.1222 1.1577 35 5.23 1.1253 1.1163 1.1135 1.1509 36 5.03 1.1272 1.1209 1.1079 1.1457 37 4.83 1.1308 1.1245 1.1042 1.1384 38 4.63 1.1335 1.1277 1.1000 1.1306 39 4.43 1.1358 1.1305 1.0966 1.1234 40 4.23 1.1376 1.1329 1.0930 1.1162 41 4.03 1.1389 1.1349 1.0888 1.1085 42 3.83 1.1400 1.1366 1.0849 1.1002 43 3.62 1.1407 1.1381 1.0827 1.0923 44 3.42 1.1411 1.1393 1.0817 1.0859 45 3.22 1.1431 1.1428 1.0806 1.0798 46 3.02 1.1524 1.1516 1.0814 1.0782 47 2.82 1.1689 1.1684 1.0909 1.0858 48 2.62 1.1847 1.1936 1.1071 1.1007 49 2.42 1.2013 1.2198 1.1238 1.1159 50 2.21 1.2207 1.2458 1.1404 1.1306 51 2.01 1.2412 1.2716 1.1571 1.1453 52 1.81 1.2608 1.2967 1.1735 1.1596 53 1.61 1.2796 1.3206 1.1892 1.1736 54 1.41 1.2967 1.3425 1.2039 1.1868

• 55 1.21 1.0000 1.0000 1.0000 1.0000

• 56 1.01 1.0000 1.0000 1.0000 1.0000

• 57 0.81 1.0000 1.0000 1.0000 1.0000

• 58 0.60 1.0000 1.0000 1.0000 1.0000

• 59 0.40 1.0000 1.0000 1.0000 1.0000

• 60 0.20 1.0000 1.0000 1.0000 1.0000

• 61 0.00 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 22 Beaver Valley Unit 1 5.1 - 13 LRM Revision 78

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 o to 1200 1.0337

> 1200 to < 3600 1.0200 3600 to 5400 1.0277

> 5400 1.0200 Note: The Penalty Factor, to be applied to Fo(Z) in accordance with Technical Specification Surveillance Requirement (SR) 3.2.1.2, is the maximum factor by which Fo(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 22 Beaver Valley Unit 1 5.1 - 14 LRM Revision 78