L-10-015, Core Operating Limits Report, Cycle 20 Revised

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Core Operating Limits Report, Cycle 20 Revised
ML100430418
Person / Time
Site: Beaver Valley
Issue date: 02/01/2010
From: Harden P
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-10-015
Download: ML100430418 (17)
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Text

FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergyNuclear Operating Company Shippingport, PA 15077 PaulA. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 February 1, 2010 L-10-015 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 Operatinq Limits Report, Cycle 20 Revised FirstEnergy Nuclear Operating Company (FENOC) hereby submits a mid-cycle revision 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 20-1, made effective on January 7, 2010, is enclosed.

The mid-cycle revision was made in response to Westinghouse Nuclear Safety Advisory Letter NSAL-09-5 and incorporates a new Relaxed Axial Offset Control analysis that changes the Axial Flux Difference limits and associated W(Z) values. W(Z) is a cycle dependent function that accounts for power distribution transients encountered during normal operation. The mid-cycle revision also adds text to clarify the scaling of the W(Z) factors for partial power. The mid-cycle revision, COLR 20-1, provides additional surveillance margin during the remainder of BVPS Unit No. 1 Cycle 20.

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.

Sincerely, Paul A. Harden

Enclosure:

Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 20-1

Beaver Valley Power Station, Unit No. 1 L-10-015 Page 2 cc: Nuclear Regulatory Commission Region I Administrator Nuclear Regulatory Commission Resident Inspector Nuclear Reactor Regulation Project Manager Director Bureau of Radiation Protection/Department of Environmental Protection (BRP/DEP)

Site BRP/DEP Representative

Enclosure L-10-015 Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 20-1 (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.(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 TemperatureCoefficient (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 20 Beaver Valley Unit 1 5.1 -1 LRM Revision 67

Licensing Requirements Manuai 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) :5 CFQ lK(Z) forP* 0.5 W0.5-THERMAL POWER Where: CFQ = 2.40 = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

FO(Z) = F6 (Z)

  • 1.0815 FQ(Z) = F6(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 l/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 ( FANH)

FNH < CFAH * (1 + PFAH (1-P))

Where: CFAH = 1.62 PFAH = 0.3 THERMAL POWER RATED THERMAL POWER COLR Cycle 20-1 Beaver Valley Unit 1 5.1 -2 LRM Revision 68

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. OvertemDerature AT Setooint 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' < 577.90F(l)

Nominal pressurizer pressure P' _ 2250 psia Measured reactor vessel average temperature lead/lag tc1 >-30 secs time constants T2 < 4 secs Measured reactor vessel AT lag time constant 'E4 *< 6 secs Measured reactor vessel average temperature lag t 5< 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 20 Beaver Valley Unit 1 5.1 -3 LRM Revision 67

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. OverDower AT SetDoint Parameter Values:

Parameter Value Overpower AT reactor trip setpoint K4 < 1.085 Overpower AT reactor trip setpoint Tavg K5 >_0.02/°F for increasing rate/lag coefficient average temperature K5 = 0/°F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 > 0.0021/ 0 F for T > T" heatup coefficient K6 = 0/°F for T < T" 2

577.90F( )

Tavg at RATED THERMAL POWER T" _<

Measured reactor vessel average 13 >- 10 secs temperature rate/lag time constant Measured reactor vessel AT lag time ;4 *-- 6 secs constant Measured reactor vessel average 1U5 < 2 secs temperature lag time constant (2) T" represents the cycle-specific Full Power Tavg value used in core design.

COLR Cycle 20 Beaver Valley Unit 1 5.1 -4 LRM Revision 67

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 Tavg < 581.5oF(l)

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 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 20 Beaver Valley Unit 1 5.1 -5 LRM Revision 67

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 20 Beaver Valley Unit 1 5.1 -6 LRM Revision 67

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-1 0216-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-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-YM 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 20 Beaver Valley Unit 1 5.1 -7 LRM Revision 67

Licensing Requirements Manual Core Operating Limits Report 5.1 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 20 Beaver Valley Unit 1 5.1 -8 LRM Revision 67

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

0 20 40 60 80 100 Relative Power (Percent)

Figure 5.1-2 (Page 1 of 1)

CONTROL ROD INSERTION LIMITS COLR Cycle 20 Beaver Valley Unit 1 5.1 -9 LRM Revision 67

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 20 Beaver Valley Unit 1 5.1 -10 LRM Revision 67

Licensing Requirements Manual Core Operating Limits Report 5.1 110 1.00 90 So

~70 60 c-- 50

-50' , -40 -30 -20 10  : 0 10 -20 30 4G Axial Flux Differ-2ace (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 COLR Cycle 20-1 Beaver Valley Unit 1 5.1 -11 LRM Revision 68

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 3000 10000 18000 Zone Point (feet) MWD/MTU' MWD/MTU MWD/MTU

  • 1 12.0 1.0000 1.0000 1.0000
  • 2 11.8 1.0000 1.0000 1.0000
  • 3 11.6 1.0000 1.0000 1.0000
  • 4 11.4 1.0000 1.0000 1.0000
  • 5 11.2 1.0000 1.0000 1.0000
  • 6 11.0 1.0000 1.0000 1.0000
  • 7 10.8 1.0000 1.0000 1.0000 8 10.6 1.1596 1.2362 1.2161 9 10.4 1.1529 1.2254 1.1922 10 10.2 1.1450 1.2119 1.1725 11 10.0 1.1402 1.1992 1.1678 12 9.8 1.1458 1.1888 1.1725 13 9.6 1.1451 1.1799 1.1790 14 9.4 1.1404 1.1717 1.1857 15 9.2 1.1357 1.1621 1.1917 16 9.0 1.1304 1.1529 1.1954 17 8.8 1.1385 1.1577 1.2005 18 8.6 1.1500 1.1710 1.2124 19 8.4 1.1580 1.1844 1.2290 20 8.2 1.1644 1.1948 1.2449 21 8.0 1.1687 1.2029 1.2576 22 7.8 1.1710 1.2085 1.2672 23 7.6 1.1712 1.2117 1.2739 24 7.4 1.1697 1.2126 1.2775 25 7.2 1.1666 1.2114 1.2785 26 7.0 1.1620 1.2085 1.2770 27 6.8 1.1563 1.2038 1.2732 28 6.6 1.1494 1.1975 1.2671 29 6.4 1.1412 1.1896 1.2586 30 6.2 1.1319 1.1802 1.2478 31 6.0 1.1236 1.1693 1.2350 32 5.8 1.1166 1.1570 1.2197 Note: Top and Bottom 10% Excluded COLR Cycle 20-1 Beaver Valley Unit 1 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 3000 10000 18000 Zone Point (feet) MWD/MTU MWD/MTU MWD/MTU 33 5.6 1.1118 1.1438 1.2035 34 5.4 1.1092 1.1314 1.1883 35 5.2 1 .1119 1.1213 1.1738 36 5.0 1.1163 1.1135 1.1630 37 4.8 1.1203 1.1077 1.1558 38 4.6 1.1239 1.1026 1.1494 39 4.4 1.1269 1.0972 1.1416 40 4.2 1.1295 1.0949 1.1330 41 4.0 1.1318 1.0930 1.1240 42 3.8 1.1336 1.0917 1.1137 43 3.6 1.1352 1.0920 1.1042 44 3.4 1.1366 1.0941 1.1006 45 3.2 1.1378 1.0966 1.0978 46 3.0 1.1466 1.0980 1.0957 47 2.8 1.1642 1.1014 1.0959 48 2.6 1.1845 1.1173 1.1043 49 2.4 1.2081 1.1338 1.1155 50 2.2 1.2321 1.1499 1.1270 51 2.0 1.2555 1.1659 1.1384 52 1.8 1.2781 1.1814 1.1497 53 1.6 1.2995 1.1960 1.1608 54 1.4 1.3190 1.2096 1.1722

  • 55 1.2 1.0000 1.0000 1.0000
  • 56 1.0 1.0000 1.0000 1.0000
  • 57 0.8 1.0000 1.0000 1.0000
  • 58 0.6 1.0000 1.0000 1.0000
  • 59 0.4 1.0000 1.0000 1.0000
  • 60 0.2 1.0000 1.0000 1.0000
  • 61 0 1.0000 1.0000 1.0000 Note: Top and Bottom 10% Excluded COLR Cycle 20-1 Beaver Valley Unit 1 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 1350 1.0321

> 1350 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 20 Beaver Valley Unit 1 5.1 - 14 LRM Revision 67

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