L-09-112, Submittal of Core Operating Limits Report, Cycle 20

Submittal of Core Operating Limits Report, Cycle 20

ML091350055
Person / Time
Site:	Beaver Valley
Issue date:	05/12/2009
From:	Sena P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-09-112
Download: ML091350055 (16)

Text

FENOC FirstEnergyNuclear Operating Company PeterP. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 May 12, 2009 L-09-112 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 Operatingq Limits Report, Cycle 20 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a 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, made effective on April 27, 2009, is enclosed.

No regulatory commitments are contained in this submittal. If there are questions, or additional information is required, please contact Mr. Thomas A. Lentz, Manager -

FENOC Fleet Licensing, at 330-761-6071.

Sinc Peter P. Sena III

Enclosure:

Beaver Valley Power Station Unit No. 1 Core Operating Limits Report, COLR 20 cc: NRC Region I Administrator NRC Senior Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative 4oo0

L-09-112 Enclosure Beaver Valley Power Station Unit No. 1 Core Operating Limits Report COLR 20

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 _Ž1.77% 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 _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 - 4.4 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

5.censing 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]*KZ) for P > 0.5 FQ (Z) _ - K(Z) forP* 0.5 L 0.54 K THERMAL POWER Where: CFQ = 2.40 RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

C =M FQ(Z) FQ(Z) - 1.0815 FI Q(Z) = F(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)

FAH CFAH * (1 + PFAH (1-P))

Where: CFAH = 1.62 PFAH = 0.3 THERMAL POWER

= RATED THERMAL POWER COLR Cycle 20 Beaver Valley Unit 1 5.1 -2 LRM Revision 67

51icensing 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 Overoower 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°F(l)

Nominal pressurizer pressure P' > 2250 psia Measured reactor vessel average temperature lead/lag -ul _>30 secs time constants T2 *! 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 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. Overpower AT Setpoint 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/OF for T > T" heatup coefficient K6 = 0/°F for T*< T" 2

)

Tavg at RATED THERMAL POWER T"<* 577.90F(

Measured reactor vessel average 13 Ž10 secs temperature rate/lag time constant Measured reactor vessel AT lag time 'r 4 6 secs constant Measured reactor vessel average T5

• 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 Boilingq (DNB) Limits Parameter Indicated Value Reactor Coolant System Tavg Tavg _<581.50F(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

ýLicensing 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-1 2945-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 1.995 (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 LEFM4TM System," Revision 0, March 1997.

9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMVTM 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 5.1 670 660 650 640

'-' 630 H.:{ 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 20 Beaver Valley Unit 1 5.1 -8 LRM Revision 67

'Licensing Requirements Manual Core Operating Limits Report 5.1 200 150 /

I I _

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 1.1 0.8 0.6 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 5.1 120 110 100 90 80 70 08 F- '60 I--

0 50 10 40 30 20 10 0

-60 -40 -20 0 20 40 60 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 COLR Cycle 20 Beaver Valley Unit 1 5.1 -11 LRM Revision 67

'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 1.1667 1.2047 1.2410 1.2484 9 10.4 1.1574 1.1944 1.2334 1.2244 10 10.2 1.1466 1.1813 1.2244 1.1976 11 10.0 1.1389 1.1695 1.2153 1.1760 12 9.8 1.1421 1.1634 1.2054 1.1751 13 9.6 1.1402 1.1571 1.1975 1.1768 14 9.4 1.1350 1.1494 1.1941 1.1771 15 9.2 1.1302 1.1411 1.1912 1.1794 16 9.0 1.1243 1.1345 1.1867 1.1962 17 8.8 1.1331 1.1432 1.1951 1.2104 18 8.6 1.1467 1.1560 1.2089 1.2226 19 8.4 1.1574 1.1652 1.2204 1.2351 20 8.2 1.1663 1.1727 1.2293 1.2466 21 8.0 1.1731 1.1780 1.2355 1.2554 22 7.8 1.1778 1.1811 1.2391 1.2615 23 7.6 1.1804 1.1821 1.2400 1.2649 24 7.4 1.1811 1.1811 1.2384 1.2658 25 7.2 1.1800 1.1784 1.2346 1.2643 26 7.0 1.1775 1.1742 1.2288 1.2603 27 6.8 1.1735 1.1685 1.2211 1.2571 28 6.6 1.1682 1.1616 1.2117 1.2536 29 6.4 1.1615 1.1534 1.2005 1.2473 30 6.2 1.1536 1.1440 1.1878 1.2389 31 6.0 1.1449 1.1337 1.1733 1.2284 32 5.8 1.1336 1.1211 1.1583 1.2158 Note: Top and Bottom 10% Excluded COLR Cycle 20 Beaver Valley Unit 1 5.1 -12 LRM Revision 67

. 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 33 5.6 1.1265 1.1134 1.1442 1.2018 34 5.4 1.1266 1.1136 1.1323 1.1884 35 5.2 1.1326 1.1204 1.1242 1.1768 36 5.0 1.1404 1.1272 1.1207 1.1656 37 4.8 1.1480 1.1329 1.1186 1.1586 38 4.6 1.1548 1.1383 1.1150 1.1556 39 4.4 1.1611 1.1431 1.1115 1.1507 40 4.2 1.1667 1.1473 1.1111 1.1450 41 4.0 1.1717 1.1510 1.1112 1.1388 42 3.8 1.1761 1.1543 1.1124 1.1318 43 3.6 1.1800 1.1570 1.1154 1.1246 44 3.4 1.1834 1.1593 1.1186 1.1175 45 3.2 1.1861 1.1640 1.1217 1.1087 46 3.0 1.1899 1.1761 1.1238 1.1128 47 2.8 1.2020 1.1934 1.1314 1.1298 48 2.6 1.2259 1.2097 1.1505 1.1444 49 2.4 1.2494 1.2266 1.1692 1.1594 50 2.2 1.2720 1.2448 1.1872 1.1745 51 2.0 1.2945 1.2631 1.2052 1.1893 52 1.8 1.3160 1.2805 1.2224 1.2037 53 1.6 1.3362 1.2970 1.2387 1.2178 54 1.4 1.3545 1.3119 1.2537 1.2313

• 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 20 Beaver Valley Unit 1 5.1 - 13 LRM Revision 67

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) F0 (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