L-18-264, Cycle 21 Core Operating Limits Report
| ML18320A157 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/16/2018 |
| From: | Bologna R FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-18-264 | |
| Download: ML18320A157 (18) | |
Text
FENOC*
FidEneryy N uclear Opra,ling Compny Beaver Valley Power Sfafion P.O. Box 4 Shippingport, PA 1fi77 Richard D. Bologna Srfe Vice Prcsident 72+682-5234 Fax:72*64S8069 November 16, 2018 L-18-264 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DG 20555-0001
SUBJECT:
Beayer Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Qvcle 21 Core Operatinq Limits Report Pursuant to the requirements of Beaver Valley Power Station, Unit No. 2 Technical Specification 5.6.3,.CORE OPERATING LIMITS REPORT (COLR)," FirstEnergy Nuclear Operating Company hereby submits the GOLR for Cycle 21. Technical Specification 5.6.3.d requires, in part, that the COLR be provided to the Nuclear Regulatory Commission upon issuanre for each reload cycle. The Cycle 21 COLR was made effective on November 1, 2018.
There are no regulatory commitments contained in this submittal. !f there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager, FENOC Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.
Sincerely, Richard D. Bologna
Enclosure:
Beaver Valley Power Station, Unit No. 2, Core Operating Limits Report, Cycle 21 cc: NRC Region lAdministrator NRC Resident lnspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure L-18-264 Beaver Valley Power Station, Unit No. 2 Core Operating Limits Repoft, Cycle 21 (16 Pages Follow)
Licensing Requirements Manual 5.0 5.1 ADMIN ISTRATIVE CONTROLS Core Operating Limits Report Core Operating Limits Report 5.1 5.1.1 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.
SL 2.1.1 Reactor Core Safetv. Limits See Figure 5.1-1.
- a. ln MODES 1,2, 3, and 4, SHUTDOWN MARGIN shall be > 1.77o/o Aldk.(1)
- b. Prior to manually blocking the Low Pressurizer Pressure Safety lnjection 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. ln MODE 5, SHUTDOWN MARGIN shall be > 1.Oolo Aldk.
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 Iess negative than -4.29 x 104 AIdld'F at RATED THERMAL POWER.
- c. 300 ppm Surveillance Limit: (- 35 pcm/'F)
- d. The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 10 :
Revised Predicted MTC = Predicted MTC" + AFD Conection** + Predictive Conection***
- where,
- Predicted MTC is calculated from Figure 5.1-5 at the bumup corresponding to the measurement of 300 ppm at RTP conditions, n* AFD Correction is the more negative value of :
{0 pcml'F or (AAFD
- AFD Sensitivity)}
where: AAFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm.
and AFD Sensitivity = 0.10 pcm/"F / AAFD
- Predictive Correction is -3 pcm/oF.
5.1.2 5.1.3 (1) The MODE 1 and MODE 2 with ker ) 1.0 SDM requirements are included to address SDM requirements (e.9., MODE 1 Required Actions to verify SDM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SDM).
COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -1
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.4 lf the revised predicted MTC is less negative than the SR 3.1.3.2 limit (COLR 5.1.3.c) and all of the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 3.1.3.2 is not required.
- e. 60 ppm Surveillance Limit (- 40.5 pcm/"F)
LCO 3.1.5 Shutdown Bank lnsertion Limits The Shutdown Banks shall be withdrawn to at least 225 steps.tz)
LCO 3.1.6 Control Bank lnsertion Limits
- a. Control Banks A and B shall be withdrawn to at least 225 steps.{z)
- b. Gontrol Banks C and D shall be limited in physical insertion as shown in Figure 5.1-2.{e)
- 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.
LCO 3.2.1 Heat FIux Hot Channel Factor (Fo(Z))
5.1.5 5.1.6 The Heat Flux Hot Channel Factor - Fo(Z) limit is defined by:
FQ(z) = [T].*,r, FQ(z)= [H].*,r, Where: CFQ = 2.40 A
THERMAL POWER r=
K(Z) = the function obtained from Figure 5.1-3.
Ffi(z)=FH(z).1.081s$
r$rzl (2) As indicated by the group demand counter
$ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75a/o of the total number of thimbles. lf there are less than 75o/o of the total number of thimbles and at least 50% of the total number of thimbles measured, and additional uncertainty of (0.01).(3-T/12.5) is added to the measurement uncertainty, 1.05, where T is the total number of measured thimbles. This adjusted measurement uncertainty is then multiplied by 1.03 to obtain the total uncertainty to be applied. At least three measured thimbles per core quadrant are also required.
COLR Cycle 21 LRM Revision 94 for P > 0.5 for P < 0.5
= F3 (z). w(z)
Beaver Valley Unit 2 5.1 -2
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.7 s.1.8 5.1.g The W(Z) values are provided in Tables 5.1-1 and 5.1-2. The W(Z) values in Table 5.1-1 were generated assuming that theywill be used for a full power surveillance. The W(Z) values in Table 5.1-2 were generated assuming that they will be used for a part power surveillance during initial cycle startup following the refueling outage. When a part power surveillance is performed, the W(Z) values should be multiplied by the factor 1lP, when P > 0.5. When P is < 0.5, the W(Z) values should be multiplied by the factor 1{0.5), or2.0. This is consistentwith the adjustment in the Fo(Z) limit at part power conditions.
The Fo(Z) penalty function, applied when the analytic Fo(Z) function increases from one monthly measurementto the next, is provided in Table 5.1-3.
LCO 3.z.zNuclear Enthalpy Rise Hot Channel Factor t flrl tuT, =ff^.
Where:
.(1+For(1-R) $
CFAH FFAH P=
= 1.62
= 0.3 THERMAL POWER RATED THERMAL POWER LCO 3.2.3 Axial Flux Difference (AFD)
The AFD acceptable operation limits are provided in Figure 5.14.
LCO 3.3.1 Reactor Trip System lnstrumentation - Overtemperature and Overpower AT Parameter Values from Table Notations 3 and 4
- a. Overtemperature AT Setpoint Parameter Values:
Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Tavg at RATED THERMAL POWER Value K1 < 1.239 K2 > 0.0193/'F K3 > 0.001/psia T'< S74.2op(t)
$ An additional uncertainty is to be applied if the number of measured thimbles for the moveable incore detector system is less than 75o/o of the total number of thimbles. lf there are Iess than 75o/o of the total number of thimbles and at least 50% of the total number of thimbles measured, and additional uncertainty of (0.01)"(3-T/12.5) is added to the standard uncertainty on FNAH of 1.04, where T is the total number of measured thimbles. At least three measured thimbles per core quadrant are also required.
(1) T' represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -3
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 Nominal pressurizer pressure Measured reactor vessel AT lead/lag time constants
(. The response time is toggled off to meet the analysis value of zero.)
Measured reactor vessel AT lag time constant Measured reactor vessel average temperature lead/lag time constants Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient P'> 2250 psia Tr = 0 sec*
tz= 0 sec" b.
Measured reactor vessel average temperature lag 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) Forqt-gu between -37% and +15%, fr(Al) = 0, where Qt and goore percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and Qt + Qu is total THERMAL POWER in percent of RATED THERMAL POWER.
(ii) For each percent that the magnitude of (qr-qu) exceeds -37o/o, the AT trip setpoint shall be automatically reduced by 2.52o/o of its value at RATED THERMAL POWER.
(iai) For each percent that the magnitude of (q1 - Qu) exceeds +15%, the AT trip setpoint shall be automatically reduced by 1.47o/o of its value at RATED THERMAL POWER.
Overpower AT Setpoint Parameter Values:
Parameter Value Overpower AT reactor trip setpoint Tavg heatup coefficient Tavg at RATED THERMAL POWER Measured reactor vessel AT lead/lag time constants ts < 6 secs t+ ) 30 secs rs < 4 secs
- r. ( 2 secs K4 < 1.094 K5 > O.OZl"F for increasing average temperature K5 = 0/'F for decreasing average temperature K6>0.0021/oFforT>T" K6=0/'FforT<T" T,,< 574.2op{tt Tr = 0 sec*
Tz = 0 sec*
the analysis value of zero.)
(. The response time is toggled off to meet (1) T" represents the cycle-specific Full Power Tavg value used in core design.
COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 s.1 -4
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 Measured reactor vessel AT lag time constant Measured reactor vessel average temperature Iag time constant Measured reactor vessel average temperature rate/lag time constant rs < 6 secs to < 2 secs u > 10 secs 5.1.1 0 LCO 3.4.1. RCS Temnerature. and Flow D re from Nucleate Boilinq (DNB) Limits Parameter Reactor Coolant System Tavg Pressurizer Pressure Reactor Coolant System Total Flow Rate Indicated Value Tavg < 577.9o5(t)
Pressure > 2214 psiatz)
Flow > 267,483 gpm(s) 5.1.11 LCO 3.9.1 Boron centration (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.
(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 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 5
Licensing Requirements Manual 5.1 Core Operating Limits Report Core Operating Limits Report 5.1 5.1.12 References 1
2 3
WCAP.g 272.P -A. "W EST I N G HO U S E RE LOAD SAFETY EVALUAT I O N METHODOLOGY," July 1 985 (Westinghouse Proprietary).
WGAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986.
WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1 998 (Westinghouse Proprietary).
WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-Fo Surveillance Technical Specification," February 1 994.
WCAP-1 4565-P-A, "VIPRE-O1 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"
October 1999.
- 6. WCAP-1261O-P-A, 'VANTAGE+ Fuel Assembly Reference Core Report,"
April 1 995 (Westinghouse Proprietary).
- 7. WCAP-15025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicting Gritical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.
- 8. Caldon, lnc. Engineering Report-80P, "lmproving Thermal Power Accuracy and Plant Safety While lncreasing Operating Power Level Using the LEFM.FM Systein," Revision 0, lrrtlrcfr 1997:
- 9. Caldon, lnc. Engineering Report-160P, "supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMfM Systffi," Revision 0, May 2000.
- 10. WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1 997 (Westinghouse Proprietary).
1 1. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.
- 12. WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
4 5
COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -6
Licensing Requirements Manual 0.2 Core Operating Limits Report 5.1 670 660 650 640 n
630 tr{
EO o)a bo cdFi 620 610 600 590 580 0
0.4 0.6 0.8 I
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) 1.2 1.4 2435 PSIA UNACCEPTABLE OPERATTON I92O PSIA
\\
ACCEPTABLE OPERATION COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -7
Licensing Requirements Manual 225 200 150 125 100 75 50 25 175 c
B (E
LE
.C=E U'
CLoa zo Eao (L
Yz trIootr Core Operating Limits Report 5.1 80 90 100 0
0 10 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER Figure 5.1-2 (Page 1 of 1)
CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL
/
(#.53,225 BANK C (100,187)
I /
/
/
/
/
/
114 BANK D
/
/
/
/
/
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,l 8,0 E
g E
COLR Gycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -8
Licensing Requirements Manual 1.2 l"o o.8 N
F4 o.6 o-4 o.2 o.o Core Operating Limits Report 5.1 o.o, 1.oo 6-0, l.OO r
12-o, o.925 o
6 Core Height (feet) lo t2 Figure 5.1-3 (Page 1 of 1)
FoT NORMALIZED OPERATING ENVELOPE, K(Z)
I 4
2 COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 -9
Licensing Requirements Manual 120 110 100 90 80 70 50 50 40 30 20 10 0
-50
-50
-40 20 -10 0
r_0 Axial Flux Diffierence (Delta l)%
Core Operating Limits Report 5.1 20 30 40 s0 60 l-o
=o tr-E E
t-o l-T'ou (E
E tFo s
Figure 5.14 (Page 1 of 1)
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF PERCENT OF RATED THERMAL POWER FOR RAOC
.l I
+
I J
I
\\
I t
IINAC CE PTAB LE OPERAT ION t
UNACCE PTABLE O PE RATI ON I
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I t
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I t
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IT m
m E E r
m m
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l=l-Tl-]
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E COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 10
Licensing Requirements Manual
-29.00
-30.00 00
-32.00 1{000
-31 fr.
o EI E{E lrlHUH Er Er EIoU EIfrD Eldfr EI B
EIH froH fi FI EIoE Core Operating Limits Report 5-1 18000 15000 16000 17000 cYcrE BT RNIIP (tII{D/tmU}
Figure 5.1-5 (Page 1 of 1)
HOT FULL POWER PREDICTED MODERATOR TEMPERATURE COEF FICI ENT AS A FUNCTION OF CYCLE BURNUP WHEN 3OO PPM IS ACHIEVED CTCLE BT'RI{UP (tfirD/HErr, 1{000 18000 I{EC (pm/oF)
-30.11
-31. {0
\\
\\
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COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 11
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 1 of 2)
Fo Surveillance W(Z) Function versus Burnup at 100% RTP Note: Top and Bottom 10% Excluded Exclusion Zone Axial Point Elevation (feet) 150 (MWD/MTU) 3000 (MWD/MTU) 8000 (MWD/MTU) 1 2000 (MWD/MTU) 1 6000 (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 I
10.7 1.1713 1.2064 1.2174 1.2248 1.1814 I
10.5 1.1661 1.2031 1.2152 1.2193 1.1774 10 10.3 1.1 594 1.1973 1.2108 1.2127 1.1744 11 10.1 1.1518 1.1898 1.2046 1.2051 1.1739 12 9.9 1.1522 1.1 864 1.1976 1.1969 1.1794 13 9.7 1.1539 1.1 839 1.1899 1.1907 1.1844 14 9,5 1.1541 1.1805 1.1823 1.1953 1.1875 15 9.3 1.1509 1.1727 1.1760 1.1967 1.1912 16 9.1 1.1497 1.1 691 1.1 692 1.2036 1.1987 17 8.9 1.1500 1.1665 1.1654 1.2103 1.2017 18 8.7 1.1591 1.1730 1.1698 1.2166 1.2025 19 8.5 1.1660 1.1779 1.1775 1.2238 1.2040 20 8.3 1.1713 1.1815 1.1829 1.2303 1.2133 21 8.1 1.1 750 1.1832 1.1864 1.233s 1.2223 22 7.9 1.1774 1.1837 1.1883 1.2356 1.2293 23 7.6 1.1773 1.1818 1.1878 1.2346 1.2338 24 7.4 1.1760 1.1788 1.1861 1.2321 1.2367 25 7.2 1.1726 1.1736 1.1818 1.2261 1.2359*
26 7.0 1.1686 1.1676 1.1759 1.2180 1.2326 27 6.8 1.1635 1.1607 1.1694 1.2091 1.2277 28 6.6 1.1566 1.1521 1.1615 1.1986 1.2216 29 6.4 1.1490 1.1427 1.152s 1.1865 1.2134 30 6.2 1.1407 1.1325 1.1425 1.17?8 1.2033 31 6.0 1.1314 1.1215 1.1317 1.1582 1.1918 32 5.8 1.1211 1.1093 1.1202 1.1429 1.1791 COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 12
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-1 (Page 2 ot 2)
Fo Surveillance W(Z) Function versus Bumup at 100% RTP Note: Top and Bottom 1lolo Excluded Exclusion Zone Axial Point Elevation (feet) 150 (MWDIMTU) 3000 (MWD/MTU) 8000 ffiWD/MTU) 1 2000 (MWD/MTU) 1 6000 (MWD/MTU) 33 5.6 1.1 105 1.1033 1.1081 1.1267 1.1 649 34 5.4 1.1 079 1.1009 1.0995 1.1157 1.1490 35 5.2 1.1084 1.1010 1.0956 1.1135 1.1420 36 5.0 1.1103 1.1015 1.0928 1.1096 1.1373 37 4.8 1.1116 1.101 5 1.0897 1.1056 1.1316 38 4.6 1.1125 1.1016 1.0863 1.1012 1.1252 39 4.4 1.1138 1.1030 1.0829 1.0966 1.1181 40 4.2 1.1175 1.1 049 1.0794 1.0916 1.1109 41 4.0 1.1219 1.1065 1.0762 1.0880 1.1034 42 3.8 1.1 260 1.1079 1.0759 1.0868 1.0962 43 3.6 1.1 300 1.1 101 1.0772 1.0852 1.0912 44 3.4 1.1332 1.1132 1.0780 1.0834 1.0873 45 3.2 1.1382 1.1 164 1.0793 1.0820 1.0817 46 3.0 1.1419 1.1 190 1.0796 1.0802 1.0870 47 2.8 1.1 558 1.1351 1.0856 1,0835 1.1009 48 2.6 1.1797 I.1 s97 1.0982 1.0951 1.1 151 49 2.4 1.2038 1.1830 1.1120 1.1 081 1.1 302 50 2.2 1.2283 1.2073 1.1262 1.1215 1.1455 51 2.0 1.2529 1.2317 1.1401 1.1342 1.1 596 52 1.8 1.2771 1.2557 1.1536 1.1463 1.1728 53 1.6 1.2996 1.2782 1.1 664 1.1581 1.1 855 54 1.4 1.3200 1.2987 1.1781 1.16s0 1.1975 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 COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 13
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 1 of 2)
Fo Surveillance W(Z) Function at lnitial Cycle Startup at7lo/o RTP Note: Top and Bottom 10% Excluded Exclusion Zone Axial Point Elevation (feet) 75o/o RTP 1
12.1 1.0000 2
1 1.9 1.0000 3
11.7 1,0000 4
11.5 1.0000 5
11.3 1.0000 o
11.1 1.0000 7
10.9 1.0000 I
10.7 1.2564 I
10.5 1.2338 10 10.3 1.2122 11 1 0.1 1.1896 12 g_9 1.1764 13 9.7 1.1630 14 9.5 1.1 504 15 9.3 1.1341 16 9.1 1.1212 17 8.9 1.1136 18 8.7 1.1147 19 8.5 1.1150 20 8.3 1.1149 21 8.1 1.1 139 22 7.9 1.1129 23 7.6 1.1 109 24 7.4 1.1 065 25 7.2 1.1036 26 7.0 1.0996 27 6.8 1.0948 28 6.6 1.0888 29 6.4 1.0833 30 6.2 1.0769 31 6.0 1.0705 32 5.8 1.0611 COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 14
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-2 (Page 2 ot 2)
Fo Surveillance W(Z) Function at lnitial Cycle Startup at75o/o RTP Note: Top and Bottom 10o/o Excluded Exclusion Zone Axial Point Elevation (feet) 75o/o RTP 33 5.6 1.0541 34 5.4 1.0543 35 5.2 1.0576 36 5.0 1.0627 37 4.8 1.0667 38 4.6 1.0711 3g 4.4 1.0760 40 4.2 1.0825 41 4.0 1.0888 42 3.8 1.0968 43 3.6 1.1041 44 3.4 1.1 104 45 3.2 1.1201 46 3.0 1.1271 47 2.8 1.1450 48 2.6 1.1722 49 2.4 1.2007 50 2.2 1.2283 51 2.0 1.2597 52 1.8 1.2875 53 1.6 1.3150 54 1.4 1.3390 55 1.2 1.0000 56 1.0 1.0000 57 0.8 1.0000 58 0.6 1.0000 59 0.4 1.0000 60 o.2 1.0000 61 0.0 1.0000 COLR Cycle 21 LRM Revision 94 Beaver Valley Unit 2 5.1 - 15
Licensing Requirements Manual Core Operating Limits Report 5.1 Table 5.1-3 (Page 1 of 1)
Fo(Z) Penalty Factor versus Burnup Cycle Burnup (MWD/MTU)
Fo(Z) Penalty Factor
< 751 1.0200 751 - 1051 1.0201
> 1051 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 25o/o of the surveillance interval per Technical Specification SR 3.0.2) starting from the burnup at which the Fo(Z) was determined.