L-12-181, Submittal of Core Operating Limits Report, Cycle 16-1

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Submittal of Core Operating Limits Report, Cycle 16-1
ML12166A267
Person / Time
Site: Beaver Valley
Issue date: 06/11/2012
From: Harden P
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-12-181
Download: ML12166A267 (17)
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Text

FENOC Beaver Valley Power Station FirstEnergy Nuclear OperatingCompany Shippingport, PA 15077 PaulA. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 June 11, 2012 L-12-181 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 Core Operating Limits Report, Cycle 16-1 Pursuant to the requirements of Beaver Valley Power Station (BVPS) Technical Specification 5.6.3, "CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company is submitting an update to the BVPS Unit No. 2 COLR for the remainder of BVPS Unit No. 2 Cycle 16. COLR Cycle 16-1 is enclosed.

The update incorporates a correction to the W(Z) factors due to an identified error in the existing values. The error, which only affected BVPS Unit No. 2 Cycle 16, resulted in the W(Z) factors being shifted by one axial plane. The results from the surveillances performed on the Heat Flux Hot Channel Factor [FQ(Z)] for Cycle 16.prior to the implementation of the corrected values were reviewed. The review verified that positive margin to the FQ(Z) limit would still have existed had the correct W(Z) factors been used in those surveillances. COLR Cycle 16-1 changes pages 5.1-12 and 13 only and is otherwise unchanged from COLR Cycle 16 as submitted to the Nuclear Regulatory Commission on April 4, 2011 (Accession No. ML110960732).

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

Sincerel Paul A. Harden

Beaver Valley Power Station Unit No. 2 L-12-181 Page 2

Enclosure:

Beaver Valley Power Station Unit No. 2 Core Operating Limits Report, Cycle 16-1 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative

Enclosure L-12-181 Beaver Valley Power Station Unit No. 2 Core Operating Limits Report, Cycle 16-1 (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 2! 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 - 4.29 x 10-4 Ak/k/°F at RATED THERMAL POWER.
c. 300 ppm Surveillance Limit: (- 35 pcm/PF)
d. 60 ppm Surveillance Limit: (- 41 pcm/PF) 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:

FQ (Z) LCFQ K(Z) for P > 0.5 FQ(Z) < C2Q40 for P

  • 0.5 10.5 *KZ THERMAL POWER Where: CFQ = 2.40 = RATED THERMAL POWER K(Z) = the function obtained from Figure 5.1-3.

FC(Z) = F3(Z) - 1.0815 FQWv(Z) F6 (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.

5.1.7 LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor( FNH)

N < CF *(1+PF (1-P))

FH AH 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 Instrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 3 and 4

a. OvertemDerature AT SetDoint Parameter Values:

Parameter Value Overtemperature AT reactor trip setpoint K1 *1.239 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' __574.2°F(1 )

Nominal pressurizer pressure P' > 2250 psia Measured reactor vessel AT lead/lag time constants ,'i = 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 3 <--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 response during plant startup tests such that:

(i) For qt - qb between -37% and +15%, f1 (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 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. OverDower AT SetDoint 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/°F for decreasing average temperature Overpower AT reactor trip setpoint Tavg K6 > 0.0021/°F for T > T" heatup coefficient K6 = 0/°Ffor T*<_ T" Tavg at RATED THERMAL POWER T" _< 574.20F(1)

Measured reactor vessel AT lead/lag -;1 = 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 13 *-* 6secs constant Measured reactor vessel average 6 -<2 secs temperature lag time constant Measured reactor vessel average T7 >- 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(l)

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 allowancesfor 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 15.1 -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 6)

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

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-rM System," Revision 0, March 1997.
9. Caldon, Inc. Engineering Report-160P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFM4YM System," Revision 0, May 2000.

COLR Cycle 16 Beaver Valley Unit 2 5.1 -7 LRM Revision 68

Licensing Requirements Manual Core Operating Limits Report 5.1 "T

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 5.1 225 200 175 150 C,,

0~ 125 0'

z 100 0

0 0~

zý 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 0.0, 1.00 0.8 i 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)

FaT 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 I -9.

100 -T-9o- UNACCEPTABLE OPERATION 80

.70 6o-C 0) o* i (-26.,5o) I 50 -40 -30 -20 -10 0 10 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 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 1.1565 1.1948 1.2492 1.2056 1.2163 9 10.5 1.1468 1.1875 1.2411 1.1991 1.2101 10 10.3 1.1353 1.1791 1.2320 1.1925 1.2055 11 10.1 1.1240 1.1701 1.2220 1.1863 1.2022 12 9.9 1.1138 1.1673 1.2114 1.1789 1.1981 13 9.7 1.1085 1.1672 1.2000 1.1773 1.1928 14 9.5 1.1075 1.1652 1.1885 1.1819 1.1906 15 9.3 1.1045 1.1612 1.1768 1.1886 1.1962 16 9.1 1.1024 1.1542 1.1624 1.1920 1.2019 17 8.9 1.1059 1.1551 1.1629 1.1965 1.2039 18 8.7 1.1172 1.1603 1.1759 1.2077 1.2068 19 8.5 1.1287 1.1617 1.1876 1.2239 1.2153 20 8.3 1.1379 1.1615 1.1966 1.2362 1.2267 21 8.1 1.1453 1.1588 1.2032 1.2456 1.2360 22 7.9 1.1509 1.1580 1.2076 1.2525 1.2428 23 7.6 1.1549 1.1590 1.2099 1.2570 1.2476 24 7.4 1.1575 1.1581 1.2103 1.2590 1.2503 25 7.2 1.1584 1.1562 1.2085 1.2585 1,2509 26 7.0 1.1579 1.1551 1.2048 1.2554 1.2487 27 6.8 1.1559 1.1536 1.1991 1.2500 1.2457 28 6.6 1.1524 1.1502 1.1916 1.2421 1.2426 29 6.4 1.1477 1.1457 1.1823 1.2321 1.2377 30 6.2 1.1416 1.1398 1.1715 1.2200 1.2306 31 6.0 1.1349 1.1329 1.1593 1.2061 1.2214 32 5.8 1.1257 1.1247 1.1459 1.1898 1,2102 Note: Top and Bottom 10% Excluded COLR Cycle 16-1 Beaver Valley Unit 2 5.1 - 12 LRM Revision 73

9 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 1.1188 1.1160 1.1335 1.1731 1.1971 34 5.4 1.1225 1.1099 1.1238 1.1598 1.1831 35 5.2 1.1279 1.1096 1.1121 1.1448 1.1724 36 5.0 1.1321 1.1117 1.1058 1.1347 1.1622 37 4.8 1.1360 1.1135 1.1042 1.1293 1.1519 38 4.6 1.1392 1.1149 1.1009 1.1229 1.1425 39 4.4 1.1420 1.1160 1.0975 1.1175 1.1315 40 4.2 1.1444 1.1172 1.0939 1.1138 1.1231 41 4.0 1.1463 1.1197 1.0901 1.1102 1.1162 42 3.8 1.1479 1.1232 1.0867 1.1060 1.1086 43 3.6 1.1500 1.1262 1.0844 1.1023 1.1008 44 3.4 1.1550 1.1286 1.0866 1.1002 1.0941 45 3.2 1.1639 1.1326 1.0880 1.0991 1.0891 46 3.0 1.1772 1.1412 1.0948 1.1017 1.0904 47 2.8 1.1950 1.1576 1.1112 1.1150 1.1000 48 2.6 1.2166 1.1820 1.1278 1.1318 1.1130 49 2.4 1.2419 1.2076 1.1447 1.1489 1.1288 50 2.2 1.2679 1.2327 1.1618. 1.1656 1.1450 51 2.0 1.2931 1.2577 1.1785 1.1821 1.1607 52 1.8 1.3175 1.2820 1.1948 1.1981 1.1760 53 1.6 1.3407 1.3051 1.2103 1.2134 1.1908 54 1.4 1.3618 1.3261 1.2244 1.2276 1.2048

  • 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 16-1 Beaver Valley Unit 2 5.1 -13 LRM Revision 73

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

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