L-11-119, Submission of the Core Operating Limits Report, Cycle 16

Submission of the Core Operating Limits Report, Cycle 16

ML110960732
Person / Time
Site:	Beaver Valley
Issue date:	04/04/2011
From:	Harden P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-11-119
Download: ML110960732 (16)

Text

FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergyNuclear Operating Company Shippingport,PA 15077

-PaulA. Harden 724-682-5234

,.ite Vice President Fax: 724-643-8069 April 4, 2011 L-11-119 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Submission of the Core Operating Limits Report, Cycle 16 Pursuant to the requirements of Beaver Valley Power Station (BVPS) Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company (FENOC) hereby submits the BVPS, Unit No. 2, COLR Cycle 16. The effective date of the COLR is March 18, 2011.

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 -

Fleet Licensing, at 330-761-6071.

Sinoer, Paul A. Harden

Enclosure:

Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, COLR Cycle 16 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site Representative (BRP/DEP)

Enclosure L-11-119 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Report, COLR Cycle 16 (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% Ak/k.01)

b. Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to _Žthe 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 Ž1.0% 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 - 4.29 x 10 4 Ak/k/°F at RATED THERMAL POWER.

c. 300 ppm Surveillance Limit: (- 35 pcm/OF)

d. 60 ppm Surveillance Limit: (- 41 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 16 Beaver Valley Unit 2 5.1 - 1 LRM Revision 68

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:

for P > 0.5 FoLZ) CFQ lK(Z FQ (Z) C. ] K(Z forP*< 0.5 Whee CF0.5]

THERMAL POWER P = RATED Where: CFQ = 2.40 THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

FO(Z) = Fý (Z)

• 1.0815 FWV(Z) = F (Z)

• W(Z)

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 lIP, 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.

N 5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FAHF)

FNH AH-

<CFLH *(1+PF (1-P))

AH Where: CF = 1.62 AH PFAH" = 0.3 THERMAL POWER RATED THERMAL POWER 5.1.8 LCO 3.2.3 Axial Flux Difference (AFD)

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

COLR Cycle 16 Beaver Valley Unit 2 5.1 -2 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 5.1 Core Operating Limits Report 5.1.9 LCO 3.3.1 Reactor Trip System Instrumerntation - Overtemperature and Overpower AT Parameter Values from Table Notations 3 and 4

a. Overtemperature AT Setpoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint K1 < 1.239 Overtemperature AT reactor trip setpoint Tavg K2 Ž0.01 83/°F coefficient Overtemperature AT reactor trip setpoint pressure K3 > 0.001/psia coefficient Tavg at RATED THERMAL POWER T'7 574.2oF(l)

Nominal pressurizer pressure P'_> 2250 psia Measured reactor vessel AT lead/lag time constants ti = 0 sec*

(* The response time is toggled off to meet the analysis T2 = 0 sec*

value of zero.)

Measured reactor vessel AT lag time constant T3 -<6 secs Measured reactor vessel average temperature lead/lag T4 > 30 secs time constants T5 < 4 secs Measured reactor vessel average temperature lag time T6*< 2 secs 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 re'sponse during plant startup tests such-that:.

(i) For qt - qb between -37% and +15%, f1 (Al) = 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 16 Beaver Valley Unit 2 5.1 -3 LRM Revision 68

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 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. Overnower AT Setnoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint K4

• 1.094 Overpower AT reactor trip setpoint Tavg K5 > 0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/0 F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 > 0.0021/°F for T > T" heatup coefficient K6 = 0/F for T < T" Tavg at RATED THERMAL POWER T" < 574.20F(1 )

Measured reactor vessel AT lead/lag T, = 0 sec*

time constants T2 = 0 sec*

(* The response time is toggled off to meet the analysis value of zero.)

Measured reactor vessel AT lag time T3 -<6 secs constant Measured reactor vessel average T6 -<2 secs temperature lag time constant Measured reactor vessel average *T Ž 10 secs temperature rate/lag time constant (1) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 16 Beaver Valley Unit 2 5.1 -4 LRM Revision 68

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 Boilinq (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg < 577.8°F(1)

Pressurizer Pressure Pressure > 2214 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 0 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 16 Beaver Valley Unit 2 5.1 -5 LRM Revision 68

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 61 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 16 Beaver Valley Unit 2 5.1 -6 LRM Revision 68

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 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 LEFM-IM 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.

COLR Cycle 16 Beaver Valley Unit 2 I.-1 -7 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 670 660 650 640 630 620 610 600 590 580 0 0.2 0.4 0.6 0.8 1 1.2 1.4 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)

COLR Cycle 16 Beaver Valley Unit 2 5.1 -8 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 225 200 175 (U 150 125 0.

(U 100 0

zy 75 50 25 0

0 10' 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS' AS A FUNCTION OF RATED POWER LEVEL COLR Cycle 16 Beaver Valley Unit 2 5.1-9 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 1.2 1.0.

0.8' S0.6 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (feet)

Figure 5.1-3 (Page 1 of 1)

FQT NORMALIZED OPERATING ENVELOPE, K(Z)

COLR Cycle 16 Beaver Valley Unit 2 5.1 -10 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 120 110

.~ ~ F- ( 9.

100-90 UTNACCEPTABIE OPEIRATION So-R-.

70-j(-265 0)

-40 -30 -20 -10 0 10 20 30 6o Axial Flux Difference (Delta i)9%

Figure 5.1-4 (Page 1 of 1)

AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC COLR Cycle 16 Beaver Valley Unit 2 5.1 -11 LRM Revision 68

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 8000 14000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU

• 1 12.1 1.0000 1.0000 1.0000 1.0000 1.0000

• 2 11.9 1.0000 1.0000 1.0000 1.0000 1.0000

• 3 11.7 1.0000 1.0000 1.0000 1.0000 1.0000

• 4 11.5 1.0000 1.0000 1.0000 1.0000 1.0000

• 5 11.3 1.0000 1.0000 1.0000' 1.0000 1.0000

• 6 11.1 1.0000 1.0000 1.0000 1.0000 1.0000

• 7 10.9 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.7 1.1644 1.2015 1.2564 1.2190 1.2228 9 10.5 1.1565 1.1948 1.2492 1.2056 1.2163 10 10.3 1.1468 1.1875 1.2411 1.1991 1.2101 11 10.1 1.1353 1.1791 1.2320 1,1925 1.2055 12 9.9 1.1240 1.1701 1.2220 1.1863 1.2022 13 9.7 1.1138 1.1673 1.2114 1.1789 1.1981 14 9.5 1.1085 1.1672 1.2000 1.1773 1.1928 15 9.3 1.1075 1.1652 1.1885 1.1819 1.1906 16 9.1 1.1045 1.1612 1.1768 1.1886, 1.1962 17 8.9 1.1024 1.1542 1.1624 1.1920 1.2019 18 8.7 1.1059 1.1551 1.1629 1.1965 1.2039 19 8.5 1.1172 1.1603 1.1759 1.2077 1.2068 20 8.3 1.1287 1.1617 1.1876 1.2239 1.2153 21 8.1 1.1379 1.1615 1.1966 1.2362 1.2267.

22 7.9 1.1453 1.1588 1.2032 1.2456 1.2360 23 7.6 1.1509 1-.1580 1.2076 1.2525 1.2428 24 7.4 1.1549 1.1590 1.2099 1.2570 1.2476 25 7.2 1.1575 1.1581 1.2103 1.2590 1.2503 26 7.0 1.1584 1.1562 1.2085 1.2585 1.2509 27 6.8 1.1579 1.1551 1.2048 1.2554 1.2487 28 6.6 1.1559 1.1536 1.1991 1.2500 1.2457 29 6.4 1.1524 1.1502 1.1916 1.2421 1.2426 30 6.2 1.1477 1.1457 1.1823 1.2321 1.2377 31 6.0 1.1416 1.1398 1.1715 1.2200 1.2306 32 5.8 1.1349 1.1329 1.1593 1.2061 1.2214 Note: Top and Bottom 10% Excluded COLR Cycle 16 Beaver Valley Unit 2 5.1 -12 LRM Revision 68

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 8000 14000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 33 5.6 1.1257 1.1247 1.1459, 1.1898 1.2102 34 5.4 1.1188 1.1160 1.1335 1.1731 1.1971 35 5.2 1.1225 1.1099 1.1238 1.1598 1.1831 36 5.0 1.1279 1.1096 1.1121 1.1448 1.1724 37 4.8 1.1321 1.1117 1.1058 1.1347 1.1622 38 4.6 1.1360 1.1135 1.1042 1.1293- 1.1519 39 4.4 1.1392 1.1149 1.1009 1.1229 1.1425 40 4.2 1.1420 1.1160 1.0975 1.1175 1.1315 41 4.0 1.1444 1.1172 1.0939 1.1138 1.1231 42 3.8 1.1463 1.1197 1.0901 1.1102 1.1162 43 3.6 1.1479 1.1232 1.0867 1.1060 1.1086 44 3.4 1.1500 1.1262 1.0844 1.1023 1.1008 45 3.2 1.1550 1.1286 1.0866 1.1002 1.0941 46 3.0 1.1639 1.1326 1.0880 1.0991 1.0891 47 2.8 1.1772 1.1412 1.0948 1.1017 1.0904 48 2.6 1.1950 1.1576 1.1112 1.1150 1.1000 49 2.4 1.2166 1.1820 1.1278 1.1318 1.1130 50 2.2 1.2419 1.2076 1.1447 1.1489 1.1288 51 2.0 1.2679 1.2327 1.1618 1.1656 1.1450 52 1.8 1.2931 1.2577 1.1785 1.1821 1.1607 53 1.6 1.3175 1.2820 1.1948 1.1981 1.1760 54 1.4 1.3407 1.3051 1.2103 1.2134 1.1908

• 55 1.2 1.0000 1.0000 1.0000 1.0000 1.0000

• 56 1.0 1.0000 1.0000 1.0000 1.0000 1.0000

• 57 0.8 1.0000 1.0000 1.0000 1.0000 1.0000

• 58 0.6 1.0000 1.0000 1.0000 1.0000 1.0000

• 59 0.4 1.0000 1.0000 1.0000 1.0000 1.0000

• 60 0.2 1.0000 1.0000 1.0000 1.0000 1.0000

• 61 0.0 1.0000 1.0000 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 16 Beaver Valley Unit 2 5.1 -13 LRM Revision 68

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 to 900 1.0251

> 900 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 16 Beaver Valley Unit 2 5.1 -14 LRM Revision 68