ML080740291
| ML080740291 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/11/2008 |
| From: | Flaherty M Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML080740291 (105) | |
Text
{{#Wiki_filter:Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 Nuclear Generation Group Constellation Energy-March 11, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-317 Core Operating Limits Report for Unit 1, Cycle 19 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 1, Cycle 19, Revisions 0, 1, 2, and 3 (Attachments 1-4), are provided for your records. Please replace the Unit 1 Core Operating Limits Report in its entirety, with the attached Revision 3 (Attachment 4). Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219. Very truly yours, Mark D. Flaherty Manager - Engineering Services MDF/CAN/bjd Attachments: (1) Core Operating Limits Report for Unit 1, Cycle 19, Revision 0 (2) Core Operating Limits Report for Unit 1, Cycle 19, Revision I (3) Core Operating Limits Report for Unit 1, Cycle 19, Revision 2 (4) Core Operating Limits Report for Unit 1, Cycle 19, Revision 3 cc: Resident Inspector, NRC (Without Attachments) D. V. Pickett, NRC S. J. Collins, NRC R. I. McLean, DNR
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ATTACHMENT (1) CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 19, REVISION 0 Calvert Cliffs Nuclear Power Plant, Inc. March 11, 2008
Caution: Valid only for U1C19 Modes 5, 6, or Defueled Conditions Constellation Energy Calvert Cliffs Nuclear Power Plant, Inc. Core Operating Limits Report (COLR) Unit 1 Cycle 19 Revision 0 Effective Date: 2 12t /06, Trn~sc\4.t-r 'V~tLL.N Z~vrs Responsible Engineer // DATE Yndepe 'dent Reviewer DATE Engineering Supervisor - PWR Co e Analysis / DATE Rev. 0 Cycle 19 1, Cycle COLR Page 1 of 25 Calved Cliffs 1, Calvert 19 COLR Page I of 25 Rev. 0
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 19 The following limits are included in this Core Operating Limits Report: Specification Title Page Introduction ................................................................................................................. 4 Definitions .......................................................................................................... 5 3.1.1 Shutdown M argin (SDM ) ...................................................................................... 6 3.1.3 Moderator Temperature Coefficient (M TC) ............................................................ 6 3.1.4 Control Element Assem bly (CEA) Alignment ...................................................... 6 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 6 3.2.1 Linear Heat Rate (LHR) ........................................................................................ 6 3.2.2 Total Planar Radial Peaking Factor (F.yT) ............................................................ 7 3.2.3 Total Integrated Radial Peaking Factor (Fr) ........................................................... 7 3.2.5 Axial Shape Index (ASI) ......................................................................................... 7 3.3.1 Reactor Protective System (RPS) Instrumentation- Operating ............................. 7 3.9.1 Boron Concentration ............................................................................................. 8, List of Approved Methodologies ........................................................................ 21 The following figures are included in this Core Operating Limits Report: / Number Title Page Figure 3.1.1 Shutdown M argin vs. Time in Cycle ...................................................................... 9 Figure 3.1.4 Allowable Time To Realign CEA Versus T Initial Total Integrated Radial Peaking Factor (Fr ) .............................................. 10 Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power ........................ 11 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle .......................................... 12 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits ............................................. 13 T Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fxy ) vs. Scaling Factor (N-Factor) ....................................... 14 Figure 3.2.2 Total Planar Radial Peaking Factor (Fxy ) vs. Allowable Fraction of Rated T herm al Pow er ..................................................................................................... 15 T Figure 3.2.3 Total Integrated Radial Peaking Factor (Fr ) vs. Allowable Fraction of Rated Thermal Power .......................... 16 Figure 3.2.5 DNB Axial Flux Offset Control Limits ............................................................... 17 Figure 3.3. 1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power ................... 18 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 .......................................... 19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 ........................................ 20 Calvert Cliffs 1, Cycle 19 COLR Page 2 of 25 Rev. 0
UNIT 1 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev. No. 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 19 0 20 0 21 0 22 0 23 0 24 0 25 0 Rev. 0 19 COLR Cycle 19 Page 3 of 25 Calvert Cliffs 1, 1, Cycle COLR Page 3 of 25 Rev. 0
INTRODUCTtON This report provides the cycle-specific limits for operation of CalvertCliffs Unit 1, Cycle 19. It contains the limits for: Shutdown Margin (SDM) Moderator Temperature Coefficient (MTC) Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear Heat Rate (LHR) Total Planar Radial Peaking Factor (FxYT) Total Integrated Radial Peaking Factor (Fr,) Axial Shape Index (ASI) Reactor Protective System (RPS) Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specifications. The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologies" section of this report and in the Technical Specifications. COLR Revision 0 Initial release of the.Unit 1 Cycle 19 (U IC 19) COLR per Safety Evaluation SE00499 Revision 0. U 1C 19 is only allowed to operate in Modes 5, 6 or in a defueled condition. Although UICI9 is only authorized to enter Modes 5, 6, and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. Calvert Cliffs 1, Cycle 19 COLR Page 4 of 25 Rev.0
DEFINITIONS Axial Shape Index (ASI) ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core. ASI = lower - upper = YE lower + upper The Axial Shape Index (Yr) used for the trip and pretrip signals int the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that-channel. Y, = AYE + B Total Integrated Radial Peaking Factor - FrT The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core. Total Planar Radial Peaking Factor - F yT The Total Planar Radial Peaking Factor is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes. Calvert Cliffs 1, Cycle 19 COLR Page 5 of 25 Rev. 0
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1) Tavg > 200 OF - Modes 3 and 4: The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1. 1. Tavg S200 OF - Mode 5: The shutdown margin shall be > 3.0% Ap. 3.1.3 Moderator Temperature Coefficient (MTC) (SR 3.1.3.2) The Moderator Temperature Coefficient (MTC) shall be less negative than -3.0 x 10.' Ap/°F at rated thermal power. 3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1) The allowable time to realign a CEA may be provided by the full core power distribution monitoring system (Better Axial Shape Selection System - BASSS) or COLR Figure 3.1.4, "Allowable Time to Realign CEA Versus Initial Total Inteirated Radial Peaking Factor (FrT).y, If COLR Figure 3.1.4 is used, the pre-misaligned F, value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days prior to the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero (0) minutes. 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR 3.1.6.1 and SR 3.1.6.2) The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6. 3.2.1 Linear Heat Rate (LHR) (SR 3.2.1.2 and SR 3.2.1.4) The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1. The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2. When using the excore detector monitoring system (SR 3.2.1.2): The alarm setpoints are equal to the ASI limits; therefore when the alarms are adjusted, they provide indication to the operator that ASI is not within the limits. The axial shape index alarm setpoints are shown as a function of fraction of thermal power on COLR Figure 3.2.1-2. A scaling factor (N-Factor) vs. FxyT is shown in COLR Figure 3.2.1-3. The fraction of thermal power shown in COLR Figure 3.2.1-2 must be scaled by the N-Factor to determine the axial shape index alarm setpoints as a function of fraction of rated thermal power. Rev. 0 19 COLR Page 6 of 25 Calvert Cliffs 1, Cycle Cliffs 1, Cycle 19 COLR Page 6 of 25 Rev. 0
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 When using the incore detector monitoring system (SR 3.2.1.4): The alarm setpoints are adjusted to protect the Linear Heat Rate limits shown on COLR Figure 3.2. 1-1 and uncertainty factors are appropriately included in the setting of these alarms. The uncertainty factors for the incore detector monitoring system are:
- 1. A measurement-calculational uncertainty factor of 1.062, /
- 2. An engineering uncertainty factor of 1.03,
- 3. A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.a For measured thermal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thermal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020. 3.2.2 Total Planar Radial Peaking Factor (FxyT) (SR 3.2.1.1 and SR 3.2.2.1) The calculated value of FxyT shall be limited to < 1.70. The allowable combination of thermal power, CEA position, and FyT are shown on COLR Figure 3.2.2. 3.2.3 Total Integrated Radial Peaking Factor (FrT) (SR 3.2.3.1) TT The calculated value of FrT shall be limited to < 1.65. The allowable combinations of thermal power, CEA position, and F.T are shown on COLR Figure 3.2.3. 3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1) The axial shape index and thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of
< 55% when BASSS is operable, or within the limits of COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.
3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Reactor Trip Setpoints) (TS Table 3.3.1-1) The Axial Power Distribution - High trip setpoint and allowable values are given in COLR Figure 3.3.1-1. The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. The allowable values are to be not less than the larger of (1) 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3. Rev. 0 Page 7 of 25 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 7 of 25 Rev. 0
3.9.1 Boron Concentration (SR 3.9.1.1) The refueling boron concentration will maintain the k~ff at 0.95 or less (including a 1% Ak/k conservative allowance for uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained < 140 OF. Refueling Boron Concentration Limits U1C19C. Lero:13urrnip AOCreditedO E~" Post-Refueling UGS or RV Head No Restriction Lift Height Restrictions. Minimum Required Refueling Boron Concentration: > 2620 ppm This number includes:
" Chemistry Sampling Uncertainty (Notes 1, 2)
- Boron-10 Depletion Allowance
- Margin for dilution of refueling pool between low and high level alarms
- Unlimited number of temporary rotations of fuel assemblies
- Extra Conservatism for empty locations during refueling operations.
Note: (1) The above table specifies the minimum technical requirements. It is acceptable for NEOP-13 to conservatively list higher ppm values. (2) See ES200500588-000 Form 8 for detailed information about the included conservatisms. Calvert Cliffs. 1, Cycle 19 COLR Page. 8 of 25 Rev. 0
F; ACCEPTABLE 5- OPERATION (EOC, 4.5) REGION I 6U4-z I (BOC, 3.5) 3 0 MINIMUM SHUTDOWN MARGIN D 24 UNACCEPTABLE Uz OPERATION REGION 1 0 BOC EOC TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 19 COLR Page 9 of 25 Rev. 0
70 F~T Tirneto Fr Realign
- 1.53 60 minutes 60 (1.53, 60) 1.53 60 minutes 1.54 54 minutes 1.55 48 minutes 1.56 42 minutes 50 1.57 36 minutes w
1.58 30 minutes I- 1.59 24 minutes z 1.6 18 minutes 40 1.61 12 minutes 978 - 600 FrT 1.62 6 minutes Uj 1.63 0 minutes 0 > 1.63 0 minutes z(3 30 Z 0 0LU 20 I-w. 10 ALLOWED REGION 0 1.50 1.55 1.60 (1.63,0) I I 1.65 I I I I I 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Note When using the table with pre-calculated Time to Realign (instead of using the formula), always round up the FT value to two (2) decimal places (e.g. an Fr = 1.5712 shall be rounded up to 1.58 which would provide 30 minutes to realign a CEA). Figure 3.1.4 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) Rev. 0 Page 10 of25 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR CvcIe 19 COLR Page 10 of 25 Rev. 0
(1.00 FRTP, Group 5 @ 35% Inserted) 1.000 E (0.90 FRIP, Group 5 @ 35% Inserted) 0.900 (L F-0:. 0.800 UNACCEPTABLE (075. FRTPI, Group 5 @ 50%VInsertedi. E *' (0.70 FRTP, Group 5 @ 60% Inserted) ,'OPERATING 0-0.700 -
" 0o) (0.65 FRTP, Group5 @85% Inserted) REGION 0.600 -
0 , 1** (0.56 FRTP; Group 4 @50% Inserted) 0.500 - 0~ , cn"
*_=,
0 ", U - .' i
- 0.400 - Ea E z
i-. ' v1 Transie nt Insertion Limi 0.300- 00 S .... ........ 0 zO RTP, Group 3 @ 60% Inse hted) a 0.200 1 0.100 (Above Above .Zero Power PDIL iSetpoint, Group 31@ 60% Inserted) ZPPDIL . . .. ; J . . . . . . I I i REGULAmIN GRU-5__ R N G- U 3 REGUATIG GRUP 1 I 1 I I 1 1 I I I 1 1 1 I I 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 135' 108" 81" 54" 2T' 0" 135" 108" 81" 54" 2T' 0" 135" 108" 81" 54" 27" 0. REGLATNGGROP REGUATIG GOUP2 _ I I I I I: I I I I 1 I I 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 135" 108" 81" 54" 27" 0" 135" 108" 81" 54" 27" 0"
%CEA INSERTION INCHES CEA WITHDRAWN (ARO is defined in NEOP-13)
Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Rev. 0 Page 11 of25 Calvert Calvert CliffsCliffs 1, Cycle 19 1, Cycle 19 COLR COLR Page I11 of 25 Rev. 0
17.0 16.5 ----- I-U- 16.0 I-UI I.1. 0 0 15.5 a w -0J 15.0 z 4- UNACCEPTABLE OPERATION w3
- 0. 0_,L Ifl D 14.5 14.3 0
-J 14.0 +----
ACCEPTABLE OPERATION 115 4--- 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Rev. 0 COLR Page 12 of25 Calvert Cliffs Cliffs 1, Cycle 19 1, Cycle 19 COLR Page 12 of 25 Rev. 0
1.10 1.05 1.00 1 0 (0.12, 1.00) 0.95 UNACCEPTABLE UNACCEPTABLE 0.90 OPERATION OPERATION REGION
- REGION 07080.85-W 0
C-I-l 0.70 UA (-0.3,0.70) ACCEPTABLE (0.3,0.70)
-J OPERATION 0.65- REGION C.,
LL 0.8605G 0 z 0.55 0 U. 0.50 (-0.3, 0.50) 0.45-0.40-0.35-0.30 0.25 (-0.42,0.20) (03,00.20) 0.204
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2
-Linear Heat Rate Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Rev. 0 Page 13 of 25 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 13 of 25 Rev. 0
1.00 0.90 0 0.80 I-. U.Ir 0.70 0z I-o 0.60 0 .5 -
~ACCEPTABLE VALUE Z
'i0.50 0.40 0.30 0.20 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxyT Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs.
Scaling Factor (N-Factor) (See NEOP-13 for Administrative Limits) Calvert Cliffs 1, Cycle 19 COLR Page 14 of 25 Rev. 0
1.05 W.0.5 0.95 -- ((1.701.00) 0 I UN REGION U-K/LA CL 0.85-
," 0.75 (1.785, 0.8)
- F)( LIMIT CURVE I-o) w 0.65 u- 0.55 0
z 0 S0.45-U-.3 ACCEPTABLE 0 W OPERATION Ca
<REGION 3' 0.25-0 ~(1.874, 0.20) 0.15--
0.05 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxyT Figure 3.2.2 Total Planar Radial Peaking Factor (FxyT) vs. Allowable Fraction of Rated Thermal Power While operating with FxyT greater than 1.70, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Rev. 0 Page 15 of25 Calvert Cliffs 1, 19 COLR Cycle 19 1, Cycle COLR Page 15 of 25 Rev. 0
1.05 W UI'l-\UULt-' I AbLL LlO 0.95-- OPERATION o: 1 REGION
-J 0.85 (1.7325, 0.80)
L 0.75
-ra . , XF, LIMIT CURVE LU 0.65 u- 0.55 0
z 0 0.45 ACCEPTABLE
- OPERATION 0.35 REGION ,, 0.35 LU < 0.250- -j 0.15--
0.05 1.60 1.65 1.70 1.75 1.80 1.85 FrT Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT) VS. Allowable Fraction of Rated Thermal Power While operating with FrT greater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Calvert Cliffs 1, Cycle 19 COLR Page 16 of 25 Rev. 0
1.10 1.05 1.00
-J > 0.95 LU 0.90 o0.85 0- 0.80 -j ,, 0.75 0 0.70 -j -J 0.65 0.60 ;~0.55 0.50 U.
0 0.45 0 0.40 0.35 U-0.30 0.25 0.204-
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.5 DNB Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Rev. 0 Page 17 of 25 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 17 of 25 Rev. 0
0 1.300 1.250 1.200 1.150 1.100 1.050 1.000 W 0.950 0~ 0.900 0.850 0:800 0.750 0.700 0 0.650 z 0.600 0 0.550 0. 0.500 0.450 0.400 0.350 0.300 0.250 0.200 0.150 -
-0.80 -0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Rev. 0 Cycle 19 COLR Page 18 of25 Calvert Cliffs 1, Calved Cliffs 1, Cycle 19 COLR Page 18 of 25 Rev. 0
0 1.60 Pvar= 2869.5 x (Al) x (QR1) + 17.98 x Tin 1.50 QDN A1 x QRi 1.40 .. 4: 1.30 A1 +0 1667 Al ( 0.5 x1 SI 1 10 1.00 _ 1(0.0 1 0) 0.909I -.
-0.60 -0.50 -0.40 030 020 010 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 (ASI vs. A1 )
Rev. 0 COLR Page 19 of25 Cliffs 1, Calvert Cliffs Calvert Cycle 19 1, Cycle 19 COLR Page 19 of 25 Rev. 0
var = pTr"p 2869.5 x (Al) x (QR1) + 17.98 x Tin - 10820 QDNB =Al x QR1 1.2 (1.2, 1.2) 1.1 1.0 0.9 0.8 0.7
'0.6 0.5 0.4 0.3 0.2 0.1 0.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0:9 1.0 1.1 1.2 1.3 FRACTION OF RATED THERMAL POWER (RTP)
Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR 1 ) Calvert Cliffs 1, Cycle 19 COLR Page 20 of 25 Rev. 0
LIST OF APPROVED METHODOLOGIES (1) CENPD- I99-P, Rev I-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986. Additionally, Supplement 2-P-A dated June 1998. (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (2) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for Calvert Cliffs Units I and LI," December 1979 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.2, 3.2.3) (3) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units I and 2," January 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (4) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (5) CEN-191 (B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (6) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982; Unit I Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)] (7) CEN-348(B)-P, "Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (8) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (10) CENPD-162-P-A, "Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (11) CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-Uniform Axial Power Distribution," December 1984 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (12) CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (13) CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) Rev. 0 19 COLR Cycle 19 Page 21 of25 Cliffs 1, Calvert Cliffs 1, Cycle COLR Page 21 of 25 Rev. 0
(14) CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (16) CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (17) CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (18) CEN-161-(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (19) CEN-161-(B)-P, Supplement I-P, "Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement I -P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement 1-P) (21) CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15, 1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1, 3.2.2) (23) CENPD-132, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1, 3.2.2 and approval of Letter LD-81-095, dated December 15, 1981) (24) CENPD-133, Supplement 5, "CEFLASH-4A, a FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (25) CENPD-134, Supplement 2, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31, 1986, "Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2) (27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2) Calvert Cliffs 1, Cycle 19 COLR Page 22 of 25 Rev. 0
(28) Letter from Mr. R. L.. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD- 135, Supplement 5" (29) CENPD-137, Supplement I-P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27, 1977, "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" (32) CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD- 138, Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1 and 3.1.3 and 3.1.6) (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, "Safety Evaluation Report Approving Unit 1 Cycle 8 License Application"' (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, "Amendment to Operating License No. 50-317, Fifth Cycle License Application" (Section 7.1.2 contains Methodology for Specifications 3.1.1, 3.9.1) (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12, 1980, "Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 & 50-318, Request for Amendment" (Methodology for Specifications 3.1.4) (39) Letter from S. A. McNeil, Jr. (NRC) to Mr. J.A. Tiernan (BG&E), dated July 7, 1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2) (Support for Specification 3.1.4) (40) CENPD-188-A, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) Rev. 0 Page 23 of 25 Calvert Cliffs Calvert 1,Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 23 of 25 Rev. 0
(41) The power distribution monitoring system referenced in various specifications and the BASES, is described in the following documents:
- 1. CENPD-153-P, Revision 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) ii. CEN-1 19(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application) iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7, 1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.4, 3.2.2, 3.2.3, 3.2.5) iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, "Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. McDonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, "Approval to Use Convolution Technique in Main Steam Line Break Analysis -
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. M90897 and M90898)" (Methodology for Specification 3.2.3). (43) CENPD-387-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel" (44) CENPD-199-P, Supplement 2-P-A, Appendix A, Latest Approved Revision, "CE Setpoint Methodology," June 1998. (45) CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLO TM Cladding Material in CE Nuclear Power Fuel Assembly Designs". (46) CENPD-132, Supplement 4-P-A, Latest Approved Revision, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model". (47) CENPD-137, Supplement 2-P-A, Latest Approved Revision; "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model". (48) WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988. (49) WCAP-1 0965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986. (50) WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery," April 1989. Calvert Cliffs 1, Cycle 19 COLR Pagze 24 of 25 Rev. 0
(51) WCAP- 16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004. (52) WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power, Fuel Assembly Designs," August 2004. (53) WCAP-15604-NP, Revision 2-A, "Limited Scope High Burnup Lead Test Assemblies," September 2003. Rev. 0 19 COLR Cycle 19 1,Cycle Cliffs 1, Page 25 of 25 Calvert Cliffs COLR Page 25 of 25 Rev. 0
ATTACHMENT (2) CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 19, REVISION 1 Calvert Cliffs Nuclear Power Plant, Inc. March 11, 2008
Caution: Valid only for U1C19 Mode 6 or Defueled Condition Constellation Energy 6 Calvert Cliffs Nuclear Power Plant, Inc. Core Operating Limits Report (COLR) Unit 1 Cycle 19 Revision 1 Effective Date: 3['/6°o Responsible Engineer / DATE Independe Revie r / DATE 3 / Y/ZoosE Engineering Supervis PWR Core Analysis / DATE Ar 4S?/ý Calvert Cliffs 1, Cycle 19 COLR Page I of 25 Rev. I I
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 19 The following limits are included in this Core Operating Limits Report: Specification Title Page In tro duction ........................................................................................................ ........ 4 Definitions .................................................................................... ............ ............. 5 3.1.1 Shutdown Margin (SDM ) ...................................................................................... 6 3.1.3 M oderator Temperature Coefficient (M TC) .......................................................... 6 3.1.4 Control Element Assembly (CEA) Alignment ..................................................... 6 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 6 3.2.1 Linear Heat Rate (LHR) ........................................................................................ 6 3.2.2 Total Planar Radial Peaking Factor (FyT) .............................................. 7 3.2.3 Total Integrated Radial Peaking Factor (FrT) .............................................................. 7 3.2.5 Axial Shape Index (ASI) ........................................................................................ 7 3.3.1 Reactor Protective System (RPS) Instrumentation - Operating ............................. 7 3.9.1 Boron Concentration ............................................................................................. 8 List of Approved M ethodologies ........................................................................ 21 The following figures are included in this Core Operating Limits Report: Number Title Page Figure 3.1.1 Shutdown M argin vs. Time in Cycle ...................................................................... 9 Figure 3.1.4 Allowable Time To Realign CEA Versus T Initial Total Integrated Radial Peaking Factor (Fr) ............................................. 10 Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power ........... 11..... 1 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle ........................................... 12 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits ............................................ 13 T Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fxy ) vs. Scaling Factor (N -Factor) ................................................................................... 14 T Figure 3.2.2 Total Planar Radial Peaking Factor (Fxy ) vs. Allowable Fraction of Rated Therm al Pow er ................................................................................................... 15 T Figure 3.2.3 Total Integrated Radial Peaking Factor (F1 ) vs. Allowable Fraction of Rated. Thermal Power ...................................................... 16 Figure 3.2.5 DNB Axial Flux Offset ControlLimits ............................................................... 17 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power ................... 18 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 ..................... 19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 ........................................ 20 Calvert Cliffs 1, Cycle 19 COLR Page 2 of 25 Rev. I I
UNIT 1 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev. No. 1 1 2 1 3 1 4 1 5 1 6 1
.7 1 8 1 9 1 10 1 11 1 12 1 13 1 14 1 15 1 16 1 17 1 18 1
.19 1 20 1 21 1 22 1
*23 1 24 1 25 1 Calvert Cliffs 1, Cycle 19 COLR Page 3 of 25 Rev. I I
INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 19. It contains the limits for: Shutdown Margin (SDM) Moderator Temperature Coefficient (MTC) Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear Heat Rate (LHR) Total Planar Radial Peaking Factor (FxyT) T Total Integrated Radial Peaking Factor (Fr) Axial Shape Index (ASI) Reactor Protective System (RPS) Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specifications. The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologies" section of this report and in the Technical Specifications. COLR Revision 0 Initial release of the Unit 1 Cycle 19 (U1C19) COLR per Safety Evaluation SE00499 Revision 0. UIC19 is only allowed to operate in Modes 5, 6 or in a defueled condition. Although U 1C19 is only authorized to enter Modes 5, 6, and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 1 An alternate core loading pattern has been authorized forU1C19 per SE00499 Revision 1. U1C19 is only allowed to operate in Modes 6 or in a defueled condition. Although U 1C 19 is only authorized to enter Mode 6 and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. Rev.1 COLR 19 COLR Page 4 of 25 Cliffs 1, Calvert Cliffs 1, Cycle Cycle 19 Page 4 of 25 Rev.1 II
DEFINITIONS Axial Shape Index (ASI) ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core. ASI = lower- upper . YE lower + upper The Axial Shape Index (Y1) used for the trip and pretrip signals in the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel. Y, = AYE + B Total Integrated Radial Peaking Factor - FrT The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core. Total Planar Radial Peaking Factor - FxyT The Total Planar Radial Peaking Factor is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes. Calvert Cliffs 1, Cycle 19 COLR Page 5 of 25 Rev. I I
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1) Tavg > 200 °F- Modes 3 and 4: The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1. Tavg *200 OF - Mode 5: The shutdown margin shall be > 3.0% Ap. 3.1.3 Moderator Temperature Coefficient (MTC) (SR 3.1.3.2) The Moderator Temperature Coefficient (MTC) shall be less negative than -3.0 x 10-4 Ap/°F at rated thermal power. 3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1) The allowable time to realign a CEA may be provided by the full core power distribution monitoring system (Better Axial Shape Selection System - BASSS) or COLR Figure 3.1.4, "Allowable Time to Realign CEA Versus Initial Total Inte rated Radial Peaking Factor. (FrT). If COLR Figure 3.1.4 is used, the pre-misaligned Fr value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days priorto the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero (0) minutes. 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR 3.1.6.1 and SR 3.1.6.2) The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6. 3.2.1 Linear Heat Rate (LHR) (SR 3.2.1.2 and SR 3.2.1.4) The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1. The axial shape index power dependent control limits are given inCOLR Figure 3.2.1-2. When using the excore detector monitoring system (SR 3.2.1.2): The alarm setpoints are equal to the ASI limits; therefore when the alarms are adjusted, they provide indication to the operator that ASI is notwithin the limits. The axial shape index alarm setpoints are shown as a function of fraction of thermal power on COLRThe 3.2.1-3. Figure 3.2.1-2. fraction A scaling of thermal factor power (N-Factor) shown in COLR vs.Figure FxyT is shown in COLR Figure 3.2.1-2 must be scaled by the N-Factor to determine the axial shape index alarm setpoints as a function of fraction of rated thermal power. Calvert Cliffs 1, Cycle 19 COLR Page 6 of 25 Rev. I I
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 When using the incore detector monitoring system (SR 3.2.1.4): The alarm setpoints are adjusted to protect the Linear Heat Rate limits shown on COLR Figure 3.2.1-I and uncertainty factors are appropriately included in the setting of these alarms. The uncertainty factors for the incore detector monitoring system are:
- 1. A measurement-calculational uncertainty factor of 1.062,
- 2. An engineering uncertainty factor of 1.03,
- 3. A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.a For measured thermal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thermal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020. 3.2.2 Total Planar Radial Peaking Factor (FyT) (SR 3.2.1.1 and SR 3.2.2.1) The calculated value of Fxya shall be limited to < 1.70. The allowable combination of thermal power, CEA position, and FxyT are shown on COLR Figure 3.2.2. 3.2.3 Total Integrated Radial Peaking Factor (FrT) (SR 3.2.3.1) The calculated value of Fr shall be limited to < 1.65. The allowable combinations of thermal power, CEA position, and FrT are shown on COLR Figure 3.2.3. 3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1) The axial shape index and thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of
< 55% when BASSS is operable, or within the limits of COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.
3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Reactor Trip Setpoints) (TS Table 3.3.1-1) The Axial Power Distribution - High trip setpoint and allowable values are given in COLR Figure 3.3.1-1. The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. The allowable values are to be not less than the larger of(1) 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3. Rev.1 Page 7 of 25 1, Cycle Calvert Cliffs 1, 19 COLR Cycle 19 COLR Page 7 of 25 Rev. I I
3.9.1 Boron Concentration (SR 3.9.1.1) The refueling boron concentration will maintain the lff at 0.95 or less (including a 1% Ak/k conservative allowance for uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained< 140 'F. Refueling Boron Concentration Limits No Restriction Post-Refueling UGS or RV Head Lift Height Restrictions. i Minimum Required Refueling Boron Concentration: > 2620 ppm This number includes:
- Chemistry Sampling Uncertainty (Notes 1, 2)
- Boron-10 Depletion Allowance
- Margin for dilution of refueling pool between low and high level alarms
" Unlimited number of temporary rotations of fuel assemblies
" Extra Conservatism for empty locations during refueling operations.
Note: (1) The above table specifies the minimum technical requirements. It is acceptable for NEOP-13 to conservatively list higher ppm values. (2) See ES200500588-000 Form 8 for detailed information about the included conservatisms. Rev.1 Cycle 19 1,Cycle COLR 19 COLR Page 8 of 25 Calvert Cliffs 1, .Calvert Page 8 of 25 Rev. I I
6 ACCEPTABLE
- 5. OPERATION (EOC, 4.5)
REGION I 41-a I 10 z *3 MINIMUM SHUTDOWN MARGIN z o02 4 UNACCEPTABLE I- OPERATION "I REGION C', 1-0 BOC EOC TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 19 COLR Page 9 of 25 Rev. I I
70 Tine to Fr T Realigni 4 1.53 50 minutes 60 (1.53, 60) 1.53 60 minutes 1.54 54 minutes 1.55 48 minutes 1.56 42 minutes 50 1.57 36 minutes 1.58 30 minutes 1.59 24 minutes z 1.6 18 minutes 1 .51 40 1 12 minutes 978 - 600 FrT 1.62 1.63 6 minutes wUJ 0 minutes
>1.63 0 minutes z 30 j 0 20 i I-Lu 10 ALLOWED REGION 0 1 n 1.50 I
l I l I l I l I l 1.55 I l I l I l I l l 1.60 l I l (1.63, 0) l l 1.65 I l I l I l I 4 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Note When using the table with pre-calculated Time to Realign (instead of using the formula), always round up the FrT value to two (2) decimal places (e.g. an FrT = 1.5712 shall be rounded up to 1.58 which would provide 30 minutes to realign a CEA). Figure 3.1.4 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) Calvert Cliffs 1, Cycle 19 COLR Page 10 of 25 Rev. I
(1.00 FRTP, Group 5 @ 35% Inserted) 0.900- - 1 U~0.800 (0U75 FRTP. Group 5 @ 50/0 inserted( {- UNAC E F o "--- IL (0.7 Group FRTP R5 @ 60% Inseted)O 10 E ERT 0.600 (0.65FRTP,(roup0 5 85%n erted) 50%Inse 10 0.600 . , 20-1 0nnserte)it Iop
' *i 0.500 . .. . -
0.400 ' -..
;. .. .... '......... ... . (0 20-
....... Group.3.60%.Iserted
,.vU.* Transieýnt Insertion Limit 0 0.3o00......
0 (0.20 F RTP, Gro up 3 @ 60 ne
,%Isied) 0.0
, , , I I I I I I I
/I t /
; ;-S *' . [ e Po e P)L eton, Gru
!er ,
ZPPDIL_ 0%I I I I 0% 1 .I 20% 40% 60% 80% 100% 0.I 0% 20% 40% 60% 80% I 100% 20% 40% 60% 80% 100% 135" - 108", 81" 54" 27" 135" 108" 81" 54" 27' 0. 135" 108" 81", 54" 27" 0" 0% 20%/ 40%/ 60% 80% 100% 0% 20%/ 40%/ 60%/ 80%/ 100% 135" 108" 81" 54" 27" 0" 135" 108" 81" 54" 27" 0"
%CEA INSERTION INCHES CEA WITHDRAWN (ARO is defined in NEOP-13)
Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Rev.1 Cycle 19 COLR 19 COLR Page 11 of25 Calvert Cliffs 1, Calvert Cliffs 1, Cycle Page I I of 25 Rev. I I
17.0 16.5 I-U- 16.0 Ld 0 I- 155 I-I. W a 0
+ 15.0 z .-j UNACCEPTABLE OPERATION w14.5 ..J 14.3 0D -O -. 1 14.0 ACCEPTABLE OPERATION 13.5 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Calvert Cliffs 1, Cycle 19 COLR Page 12 of 25 Rev. I I
1.10 1.05 100 (-0.08, 1.00) (012, 100) 0.95 U UNACCEPTABLEOPRTN UNACCEPTABLE 0.90 OPERATION REGION 0.85-- l~ REGION REGION 3! 0.80 0 a-
. 0.75 0.70 (-0.3, 0.70) ACCEPTABLE (0.3, 0.70)
W*"0.65- OPERATION 0REGION o 0.60 z o 0.55 o 0.50 (-0.3, 0.50)
"- 0.45 0.40 0.35 0.30 0.25 (-0.42, 0.20) (0.3, 0.20) 0.20 I I Ii I
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Y Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Calvert Cliffs 1, Cycle 19 COLR Page 13 of 25 Rev. I I
1.00 0.90 (I1.785, 0.78) a 0.80 I-- LL *,0.70-0
- 0.60 Li-
. ACCEPTABLE VALUE Z
- 0.50 CO 0.40 0.30 (1.874, 0.20) 0.20 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxT Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs.
Scaling Factor (N-Factor) (See NEOP-13 for Administrative Limits) Page 14 of 25 Rev.1 L Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 14 of 25 Rev. I I'
1.05 W .. 8- (1.70, 1.00) REGION 2L 0.85-
~ 0.75 W* .5(1.785, 0.8)
U T F LIMIT CURVE C 0.65-Lu- 0.55 0 z 0 0.45 0.35 ACCEPTABLE
.. OPERATION REGION 0.25 0
~.1. (1.874, 0.20) 0..15-0.05 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxyT Figure 3.2.2 Total Planar Radial Peaking Factor (FYT) vs.
Allowable Fraction of Rated Thermal Power T While operating with FTxy greater than 1.70, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Calvert Cliffs 1, Cycle 19 COLR Page 15 of 25 Rev. I I
1.05 It UNAULLI-' IA-ltL-U 0.95-- OPERATION 0 REGION a.
-- 0.85 (1.7325, 0.80)
W 0.75
*- LIMIT CURVE Uj0.65-u-
0 0.55-z 0 0.45 ACCEPTABLE
. OPERATION 0REGION -J , 0.25 -0 . (1.819, 0.20) I 0.15 -j 0.05 1.60 1.65 1.70 1.75 1.80 1.85 Fr Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT) VS.
Allowable Fraction of Rated Thermal Power While operating with FrT greater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Rev.l Page 16 of 25 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 16 of 25 Rev. I I
1.10-1.05 1.00 (-0.08,1.00)(0.15,1.00)
-J ul 0.95-- UNIJACCEPTABLE UNACCEPTABLE w
IL! OPERATION OPERATION 0.90 REGION REGION 3-1 I.LI 0.85 0. 0.80 (0.3, 0.80) 0~ 0.75 ACCEPTABLE
-j 0.70 (-0.3, 0.70) OPERATION -j REGION ILl 0.65 0.60 0.55 n rrv, 0.50 (-0.3, U.JU) 0 0.45 z
0 0.40 C. 0.35 0.30 0.25 0.42, 0.20) (0.3, 0.20) 0.20 -
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Y Figure 3.2.5 DNB Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Calvert Cliffs 1, Cycle 19 COLR Page 17 of 25 Rev. I I
1.300 1.250 11200 1.150 1.100 1.050 1.000 W .0.950
.0 0.900 0.850 -J 0.800 I-0.750 0.700 U-0 0.650 .
Z 0 0.600 F-0.550
-,L 0.500 0.450 0.400 0.350 0.300 0.250 0.200 0.150 -
-0.80 -0.60 -0.40 -0.20 .0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIAL SHAPE INDEX, Y, Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs 1, Cycle 19 COLR Page 18 of 25 Rev. I1
1.60 1.50 QDNB A1 x QR1 1.40 1.30 (-0.6,1.3) 1.20 Al +0.17xA + 1.0 1.10 - Ai= 0.5x/ S + 1 0 1.00 _ _ __ (0.0, 10) 0.90
-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 3.3.1-2 Thermal MarginlLow Pressure Trip Setpoint - Part I (ASI vs. A1 )
Calvert Cliffs 1, Cycle 19 COLR Page 19 of 25 ,Rev. I I
PvrP -- 2869.5 x (Al) x (QR1) + 17.98 x Tin - 10820 var QDNB = Al x QR1 1.2 P 00 (1.2, 1.2) 1.1 1.0 ( . ,1.0 0.9-0.8-OR1 0.375 x (RIP) + 0.625 0.7 - 0.6-0.5- _ QR 1 = 0.9167 x (RIP) + 0.3 0.4-0.3 1.0, 0.3) 0.2-0.1 - 0.0-0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 FRACTION OF RATED THERMAL POWER (RTP) Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR 1 ) Calvert Cliffs 1, Cycle 19 COLR Page 20 of 25 Rev. I I
LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev 1-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986. Additionally, Supplement 2-P-A dated June 1998. (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3,3.2.5) (2) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.2, 3.2.3) (3) CEN- 124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (4) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (5) CEN- 191 (B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5). (6) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN- 191 (B)-P)] (7) CEN-348(B)-P, "Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (8) Letter from Mr. S. A. McNeil; Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD- 161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (10) CENPD-162-P-A, "Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, :Uniform Axial Power Distribution," April 1975 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (11)- CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-Uniform Axial Power Distribution," December 1984 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (12) CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (13) CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983 (Methodology' for Specifications
- 1. . 3.3.1, 3.1.6, 3.2.3, 3.2.5)
Calvert Cliffs 1, Cycle 19 COLR Page 21 of 25 Rev. I I
(14) CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (16) CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (17) CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (18) CEN-161-(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (19) CEN-161-(B)-P, Supplement l-P, "Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement l-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement l-P) (21) CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15, 1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1, 3.2.2) (23) CENPD-132, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1, 3.2.2 and approval of Letter LD-81-095, dated December 15, 1981) (24) CENPD-133, Supplement 5, "CEFLASH-4A, a FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (25) CENPD-134, Supplement 2, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31, 1986, "Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2) (27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2) Calvert Cliffs 1, Cycle 19 COLR Page 22 of 2.5 Rev. I I
(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD-135, Supplement 5" (29) CENPD- 137, Supplement I -P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27, 1977, "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" (32) CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD-138, Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2'contains Methodology for Specifications 3.1.1 and 3.1.3 and 3.1.6) (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, "Safety Evaluation Report Approving Unit 1 Cycle 8 License Application" (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, "Amendment to Operating License No. 50-317, Fifth Cycle License Application" (Section 7.1.2 contains Methodology for Specifications 3.1.1, 3.9.1) (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12, 1980, "Safety: Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tieman.(BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 & 50-318, Request for Amendment" (Methodology for Specifications 3.1.4) (39) Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7, 1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2) (Support for Specification 3.1.4) (40) CENPD-188-A, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) Calvert Cliffs 1, Cycle 19 COLR Page 23 of 25 Rev. I I
(41) The power distribution monitoring system referenced in various specifications and the BASES, is described in the following documents:
- 1. CENPD-153-P, Revision 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) ii. CEN-l 19(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application) iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7, 1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.4, 3.2.2, 3.2.3, 3.2.5) iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, "Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. McDonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, "Approval to Use Convolution Technique in Main Steam Line Break Analysis -
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. M90897 and M90898)" (Methodology for Specification 3.2.3). (43) CENPD-387-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel" (44) CENPD-199-P, Supplement 2-P-A, Appendix A, Latest Approved Revision, "CE Setpoint Methodology," June 1998. (45) CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs". (46) CENPD- 132, Supplement 4-P-A, Latest Approved Revision, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model". (47) CENPD-137, Supplement 2-P-A, Latest Approved Revision, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model". (48) WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988. (49) WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986. (50) WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery," April 1989. Calvert Cliffs 1, Cycle 19 COLR Page 24 of 25 Rev. I I
(51) WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004. (52) WCAP- 16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," August 2004. (53) WCAP-15604-NP, Revision 2-A, "Limited Scope High Burnup Lead Test Assemblies," September 2003. Calvert Cliffs 1, Cycle 19 COLR Page 25 of 25 Rev. I I
ATTACHMENT (3) CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 19, REVISION 2 Calvert Cliffs Nuclear Power Plant, Inc. March 11, 2008
Caution: Valid only for U1C19 Modes 4, 5, 6 or Defueled Condition Constellation Energy@ Calvert Cliffs Nuclear Power Plant, Inc. Core Operating Limits Report (COLR) Unit 1 Cycle 19 Revision 2 Effective Date: 010/ I 7A 08-& f Timothv A. Schearer - 216,0o% Responsible Engineer / DATE Jlames B. Conch C)*.J2 f l*eJL*
%/7(S0b S Independ Revieier / DATE Duncan Robinson 71.7CO.-
Engineering Supervisor - PWR Core Analysis / DATE Calvert Cliffs 1, Cycle 19 COLR Page I of 25 Rev. 2
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 19 The following limits are included in this Core Operating Limits Report: Specification Title Page Introduction ........................................................................................................ 4 Definitions ........................................................................................................... 5 3.1.1 Shutdown Margin (SDM) .................................................................................... 6 3.1.3 Moderator Temperature Coefficient (MTC) ............................ 6 3.1.4 Control Element Assembly (CEA) Alignment ..................................................... 6 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 6 3.2.1 Linear Heat Rate (LHR) ........................................................................................ 6 3.2.2 Total Planar Radial Peaking Factor (F,,) ................................................................. 7 3.2.3 Total Integrated Radial Peaking Factor (FrT) .......................................................... 7 3.2.5 Axial Shape Index (ASI) ....................................................................................... 7 3.3.1 Reactor Protective System (RPS) Instrumentation - Operating ............................. 7 3.9.1 Boron Concentration .............................................................................................. 8 List of Approved M ethodologies ....................................................................... 21 The following figures are included in this Core Operating Limits Report: Number Title Page Figure 3.1.1 Shutdown M argin vs. Tim e in Cycle ...................................................................... 9 Figure 3.1.4. Allowable Time To Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) ............................................. 10 Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power 1........... Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle ..................... 12 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control T Limits ...................... 13 Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fxy ) vs. Scaling Factor (N-Factor) ............ 14 T Figure 3.2.2 Total Planar Radial Peaking Factor (Fxy ) vs. Allowable Fraction of Rated T herm al Pow er ...................................................................................................... 15 T Figure 3.2.3 Total Integrated Radial Peaking Factor (Fr ) vs. Allowable Fraction of Rated Thermal Power ...................................................... 16 Figure 3.2.5 DNB Axial Flux Offset Control Limits ............................................................... 17 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power ........................................................ 18 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 .......................................... 19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 ........................................ 20 Cvcl~ 1 Q miR 9 Af9*~ R~v9 I I (22lvPrt Cn lvp.rt C.1 iffi, I1 Cvnle. CIiff'~ 19 COIR Nap. ? nfgg Ryt 9v I
UNIT 1 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev. No. 1 2 2 2 3 2 4 2 5 2 6 2 7 2 8 2 9 2 10 2 11 2 12 2 13 2 14 2 15 2 16 2 17 2 18 2 19 2 20 2 21 2 22 2 23 2 24 2 25 2 Page 3 of 25 Rev.2 I Cliffs 1, Calvert Cliffs Cycle 19 1, Cycle COLR 19 COLR Page 3 of 25 Rev. 2
INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 19. It contains the limits for: Shutdown Margin (SDM) Moderator Temperature Coefficient (MTC) Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear Heat Rate (LHR) Total Planar Radial Peaking Factor (Fxy ) T Total Integrated Radial Peaking Factor (FrT) Axial Shape Index (ASI) Reactor Protective System (RPS) Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specifications. The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologies" section of this report and in the Technical Specifications. COLR Revision 0 Initial release of the Unit 1 Cycle 19 (U1C19) COLR per Safety Evaluation SE00499 Revision 0. U 1C 19 is only allowed to operate in Modes 5, 6 or in a defueled condition. Although U 1C 19 is only authorized to enter Modes 5, 6, and defueled conditions, limits presented Within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 1 An alternate core loading pattern has been authorized for U 1C 19 per SE00499 Revision 1. U1C19 is only allowed to operate in Modes 6 or in a defueled condition. Although U1C19 is only authorized to enter Mode 6 and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 2 U 1C 19 (with the alternate core loading pattern) is now authorized to operate in plant modes 4, 5, 6, and defueled conditions per SE00499 Revision 2. Although all plant modes are not authorized at this time, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. Rev.2 I 19 COLR4 Calvert Cliffs 1, Cycle 19 COLR Calvert Cliffs 1, Cycle Page Page 4 of 25 of 25 Rev. 2 [
DEFINITIONS Axial Shape Index (ASI) ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core. ASI = lower - upper = YE lower + upper The Axial Shape Index (Y1 ) used for the trip and pretrip signals in the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel. YI = AYE + B Total Integrated Radial Peaking Factor - FrT The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core. Total Planar Radial Peaking Factor - FxyT The Total Planar Radial Peaking Factor is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes. PageS of 25 Rev.2 Calvert Cliffs Calvert Cycle 19 1, Cycle Cliffs 1, COLR 19 COLR Page 5 of 25 Rev. 21
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1) Tavg > 200'F - Modes 3 and 4: The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1. Tavg *200 'F - Mode 5: The shutdown margin shall be > 3.0% Ap. 3.1.3 Moderator Temperature Coefficient (MTC) (SR 3.1.3.2) The Moderator Temperature Coefficient (MTC) shall be less negative than -3.0 x 10- 4 Ap/°F at rated thermal power. 3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1) The allowable time to realign a CEA may be provided by the full core power distribution monitoring system (Better Axial Shape Selection System - BASSS) or COLR Figure 3.1.4, "Allowable Time to Realign CEA Versus Initial Total tnte rated Radial Peaking Factor (Fr).' If COLR Figure 3.1.4 is used, the pre-misaligned Fr value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days prior to the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero (0) minutes. 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR 3.1.6.1 and SR 3.1.6.2) The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6. 3.2.1 Linear Heat Rate (LHR) (SR 3.2.1.2 and SR 3.2.1.4) The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1. The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2. When using the excore detector monitoring system (SR 3.2.1.2): The alarm setpoints are equal to the ASI limits; therefore when the alarms are adjusted, they provide indication to the operator that ASI is not within the limits. The axial shape index alarm setpoints are shown as a function of fraction of thermal power on COLR Figure 3.2.1-2. A scaling factor (N-Factor) vs. FxyT is shown in COLR Figure 3.2.1-3. The fraction of thermal power shown in COLR Figure 3.2.1-2 must be scaled by the N-Factor to determine the axial shape index alarm setpoints as a function of fraction of rated thermal power. Page 6 of 25 Rev.2 I Calvert 1, Cycle Cliffs 1, Calvert Cliffs 19 COLR Cycle 19 COLR Page 6 of 25 Rev. 2 1
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 When using the incore detector monitoring system (SR 3.2.1.4): The alarm setpoints are adjusted to protect the Linear Heat Rate limits shown on COLR Figure 3.2.1-1 and uncertainty factors are appropriately included in the setting of these alarms. The uncertainty factors for. the incore detector monitoring system are: I. A measurement-calculational uncertainty factor of 1.062,
- 2. An engineering uncertainty factor of 1.03,
- 3. A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.a For measured thermal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thermal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020. 3.2.2 Total Planar Radial Peaking Factor (FxyT) (SR 3.2.1.1 and SR 3.2.2.1) The calculated value of Fy T shall be limited to < 1.70. The allowable combination of thermal power, CEA position, and FxyT are shown on COLR Figure 3.2.2. 3.2.3 Total Integrated Radial Peaking Factor (Fr T) (SR 3.2.3.1) The calculated value of FrT shall be limited to < 1.65. The allowable combinations of thermal power, CEA position, and FrT are shown on COLR Figure 3.2.3. 3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1) The axial shape index and thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of
< 55% when BASSS is operable, or within the limits of COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.
3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Reactor Trip Setpoints) (TS Table 3.3.1-1) The Axial Power Distribution - High trip setpoint and allowable values are given in COLR Figure 3.3.1-1. The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. The allowable values are to be not less than the larger of (1) 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3. Rev.2 I Cvcle 19 Calvert Cliffs 1, Cycle COLR 19 'COLR Page of 25 Page 77 of 25 Rev. 21
3.9.1 Boron Concentration (SR 3.9.1.1) The refueling boron concentration will maintain the keff at 0.95 or less (including a 1% Ak/k conservative allowance for uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained
< 140 0 F.
Refueling Boron Concentration Limits 0Oiredited.CE'As.~' Post-Refueling UGS or RV Head No Restriction Lift Height Restrictions. Minimum Required Refueling Boron Concentration: > 2620 ppm This number includes:
- Chemistry Sampling Uncertainty (Notes 1, 2)
- Boron-10 Depletion Allowance
- Margin for dilution of refueling pool between low and high level alarms
- Unlimited number of temporary rotations of fuel assemblies
- Extra Conservatism for empty locations during refueling operations.
Note: (1) The above table specifies the minimum technical requirements. It is acceptable for NEOP-13 to conservatively list higher ppm values. (2) See ES200500588-000 Form 8 for detailed information about the included conservatisms. Calvert Cliffs 1_ Cycle 19 COLR Paize 8 of 25 Rev. 2 1
6 ACCEPTABLE 5+ OPERATION (EOC, 4.5) REGION I I (BOC, 3.5)
*3 MINIMUM SHUTDOWN MARGIN z
3:l 0 2 UNACCEPTABLE I-- OPERATION
-I- REGION 1-0 EOC BOC BOG EOC TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Page 9 of 25 Rev.2 I Calvert Cliffs 1, Cycle 19 1, Cycle COLR 19 COLR Page 9 of 25 Rev. 2 1
70 Timeto FrT Realign
< 1.53 60 minutes 60 < (1.53, 60) 1.53 60 minutes 1.54 54 minutes 1.55 48 minutes 1.56 42 minutes 50 - 1.57 36 minutes 1.58 30 minutes IU 1.59 24 minutes 1.6 18 minutes z
40 1 1.61 12 minutes 1.62 6 minutes 978 -600 FrT 1.63 0 minutes
> 1.63 0 minutes z 30 -,I 0.LI 20 I-W 0-10 - ALLOWED REGION I
0-(1.63, 0) 1.50 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Note When using the table with pre-calculated Time to Realign (instead of using the formula), always round up the FrT value to two (2) decimal places (e.g. an FrT = 1.5712 shall be rounded up to 1.58 which would provide 30 minutes to realign a CEA). Figure 3.1.4 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) P P~e 10of25 Rev~2 I C~1u~rt CHM CnIxn-.rt Cvr1~ 10 (?Iiff~~ I1 Cvr.It-. IQ COI COIR pq ge, 10 nf ?. j Rev-I "I
(1.00 FRTP, Group 5 @ 35% Inserted) 0.900 '___ 4__---- -_ 0.800 - I (0 75 FRTF, Group @50% Inserted* ur.'ACCEPT BLE 070 -_____(0.70 FRTP, GrJup5@ 5 0% Ins ted)P E A T IN G O 0.0 - (0.6 FRTP, roup
- 85% In erted) RRFlOIN 0.600 : M-. , (0.6 FRTP Group 4 @ 50% nserted)
IC Ed _- __1 1 _ 0~ 1 =.' cLn ' 2 ,t- , . = '*. I . /Transi nt Inserl ion LimitI 0.200 - -{! z 0) I Setpoint in. 1 0.400 Abv ,~ (Above 7ero Pover PDILlSetpoint, Group 3I@ 60% nserted) ZPPDIL ___ _____ 4 1 ! 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 135" 108" 81" 54" 27" 0' 135" 108" 81" 54" 27" 0" 135" 108" 81" 54" 27" 0" 0% 20% 40% 60%/ 80%/ 100%/ 0% 20%/ 40% 60% 80% 100%/ 135" 108" 81" 54" 27" 0" 135" 108" 81" 54" 27" 0"
%CEA INSERTION INCHES CEA WITHDRAWN (ARC is defined in NEOP-13)
Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Rev.2 I I (72lvPrt Cn CvHe. 19 C1iff'~ II (7vcI~"~ lvert C~liffq 19 COIR
*C0T,R Pacre 11 P~we I I of2~
of 25 Rev- 2 1
17.0 16.5 i i + I-- IL 16.0 I-0 1- 15.5 I-0 _z+ 15.0 UNACCEPTABLE OPERATION
-j CO w 14.5 0~ -14.3 ,.J -. 1 14.0 ACCEPTABLE OPERATION 13.5 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Calvert Cliffs 1, Cycle 19 COLR Page 12 of 25 Rev. 2 1
1.10 1.05 1.00 (-0.08,1.00)0.12,1.00) 0.95 U UNACCEPTABLE UNACCEPTABLE 0.90 OPERATION OPERATION REGION 0.85 REGION W 3.1 80 0.80 0
-J 0.75 0.70 (-0.3, 0.70) ACCEPTABLE (0.3, 0.70)
I OPERATION 0.65- REGION 0 0.60 z 0 0.55 P= 0 0.50 (-0.3, 0.50) 0.45 0.40 0.35 0.30 0.25 (-0.42, 0.20) (0.3, 0.20) 0.20 i I I
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Calvert Cliffs 1, Cycle 19 COLR Page 13 of 25 Rev. 2
1.00 (1.40, 0.90-(1.785, 0.78)
°11 o 0.80 I-0.70-0I-,
o 0.60-U- 0 ACCEPTABLE VALUE zn 0.50 0.40 0.30 (1.874, 0.20) 0.20 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 F T Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs. Scaling Factor (N-Factor) (See NEOP-13 for Administrative Limits) Cycle 19 COLR Page 14 of 25 Rev.2 I I Cliffs 1, Calvert Cliffs 1, Cycle 19 COLR Page 14 of 25 Rev. 2 1
1.05 0.95-- 0.95 (1.70, 1.00) REGIONI IUI
-urtKt/A 0.85,-
(1.785, 0.8) W 0.75.R F, r LIMIT CURVE W 0.65 u- 0.55 0 z 0 P 0.45
.0.35 ACCEPTABLE Ij OPERATION REGION 0.25 0
(1.874, 0.20) 0.15 0.05 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxyT Figure 3.2.2 Total Planar Radial Peaking Factor (FxyT) vs. Allowable Fraction of Rated Thermal Power While operating with Fxy greater than 1.70, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Calvert Cliffs 1, Cycle 19 COLR Page 15 of 25 Rev. 2
1.05 W UNAUUL;'H I AbL:
.1:10.95-- OPERATION 0 REGION 0L
-- 0.85 (10.7325, 0.80) wU 0.75-zT
*-r LIMIT CURVE W 0.65 u- 0.55-0 z
0 0.45 ACCEPTABLE OPERATION Uý0.35- REGION
-j , 0.25 0 (1.819,0.20)
- i0.15-0.05 1.60 1.65 1.70 1.75 1.80 1.85 FrT Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT) VS.
Allowable Fraction of Rated Thermal Power While operating with Fr greater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Page 16 of25 Rev.2 I Calvert Cliffs 1. Cvcle Cliffs 1. 19 COLR Cycle 19 COLR Page 16 of 25 Rev. 2 1
1.10 1.05 - 1.00- (-0.08,1.00).15,1.00)
-1 LU. UNACCEPTABLE UNACCEPTABLE w 0.95 - -,J ,_1 OPERATION OPERATION REGION 0.90- REGION U.,
0.85 - 0
- 0. (0.3, 0.80)
LU 0.80 -
-I 0.75- ACCEPTABLE
(-0.3, 0.70) OPERATION 0 0.70-C
-j REGION 0.65-0.60-0.55 +
A 0.50 + (-0.3, uAju) 0 z 0.45+/- 0 0.40+/- C., 0.35+/- 0.30+/- 0.25- 0.42, 0.20) (0.3, 0.20) 0.20 ,,I Jl I I I F I
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.5 DNB Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Page 17 of 25 Rev.2 I Calvert Cliffs 1,1, Cycle 19 COLR Cycle 19 COLR Page 17 of 25 Rev. 2 1
1.300 1.250 1.200 1.150 1.100 1.050 1.000 W 0.950 0- 0.900 CL 0.850 _1 0.800
,LI 0.750 U--
LL 0.700 0.650 0 z 0.600 0
-,, 0.550 0.500 0.450 0.400 0.350 0.300 0.250 0.200 0.150
-0.80 -0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs 1, Cycle 19 COLR Page 18 of 25 Rev. 21
1.60 1.50 QDNB A1 x QR1 1.40 1.30 (-06,1.3) 1.20 J--* Al +0.166'7 x ASI + 1.(* (+0 .6 , 1.1) 1.10 - , _ 1.00 _ _ ____ _ (0.0,1 .0) 0.90
-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 (ASI vs. A1 )
Page 19 of25 Rev.2 Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 19 of 25 Rev. 2 1
pTrip Pvar = 2869.5 x (Al) x (QR1) + 17.98 x Ti, - 10820
-2 QDNB =A1 x QR1 1.2 (1.2, 1.2) 1.1 1.0 0.9 0.8 0.7 S0.6 a
0.5 0.4 0.3 0.2 0.1 0.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 FRACTION OF RATED THERMAL POWER (RTP) Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR 1 ) Calvert Cliffs 1, Cycle 19 COLR Page 20 of 25 Rev. 2 1
LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev 1-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986. Additionally, Supplement 2-P-A dated June 1998. (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (2) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.2, 3..2.3) (3) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (4) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units I and 2," March 1980 (Methodology for Specifications 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2," December 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (6) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)] (7) CEN-348(B)-P, "Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (8) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (10) CENPD-162-P-A, "Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (11) CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-Uniform Axial Power Distribution," December 1984 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (12) CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (13) CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications dh 3.3.1, 3.1.6, 3.2.3, 3.2.5) Calvert Cliffs 1, Cycle 19 COLR Page 21 of 25 Rev. 2
(14) CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (16) CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (17) CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (18) CEN-161-(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (19) CEN-161-(B)-P, Supplement l-P, "Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tieman (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement l-P, Improvements to Fuel Evaluation Model" (Approval of CEN- 161 (B), Supplement l-P) (21) CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15, 1981, LD 095, Enclosure l-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1, 3.2.2) (23) CENPD-132, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1, 3.2.2 and approval of Letter LD-81-095, dated December 15, 1981) (24) CENPD-133, Supplement 5, "CEFLASH-4A, a FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (25) CENPD-134, Supplement 2, "COMPERC-1I, a Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31, 1986, "Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2) (27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2) Calvert Cliffs 1, Cycle 19 COLR Page 22 of 25 Rev. 21
(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD-135, Supplement 5" (29) CENPD-137, Supplement l-P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27, 1977, "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" (32) CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD-138, Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1 and 3.1.3 and 3.1.6) (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, "Safety Evaluation Report Approving Unit I Cycle 8 License Application" (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, "Amendment to Operating License No. 50-317, Fifth Cycle License Application" (Section 7.1.2 contains Methodology for Specifications 3.1.1, 3.9. 1) (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12, 1980, "Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 & 50-318, Request for Amendment" (Methodology for Specifications 3.1.4) (39) Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7, 1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)-(Support for Specification 3.1.4) (40) CENPD-188-A, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) Page 23 of 25 Rev.2 I Cliffs 1, Calvert Cliffs Cycle 19 1, Cycle COLR 19 COLR Page 23 of 25 Rev. 2 1
(41) The power distribution monitoring system referenced in various specifications and the BASES, is described in the following documents:
- i. CENPD-153-P, Revision 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) ii. CEN-1 19(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application) iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7, 1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.4, 3.2.2, 3.2.3, 3.2.5) iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, "Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. McDonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, "Approval to Use Convolution Technique in Main Steam Line Break Analysis - Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. M90897 and M90898)" (Methodology for Specification 3.2.3).
(43) CENPD-387-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel" (44) CENPD-199-P, Supplement 2-P-A, Appendix A, Latest Approved Revision, "CE Setpoint Methodology," June 1998. (45) CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLO TM Cladding Material in CE Nuclear Power Fuel Assembly Designs". (46) CENPD-132, Supplement 4-P-A, Latest Approved Revision, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model". (47) CENPD-137, Supplement 2-P-A, Latest Approved Revision, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model". (48) WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988. (49) WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986. (50) WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery," April 1989. Calvert Cliffs 1, Cycle 19 COLR Page 24 of 25 Rev. 2
(51) WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004. (52) WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," August 2004. (53) WCAP-1 5604-NP, Revision 2-A, "Limited Scope High Burnup Lead Test Assemblies," September 2003. Calvert Cliffs 1, Cycle 19 COLR Page 25 of 25 Rev. 2 1
ATTACHMENT (4) CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 19, REVISION 3 Calvert Cliffs Nuclear Power Plant, Inc. March 11, 2008
Constellation Energy Calvert Cliffs Nuclear Power Plant, Inc. Core Operating Limits Report (COLR) Unit 1 Cycle 19 Revision 3 Effective Date: 3 Timothy A. Schearer Z t*,a .Alo 3)%)6o Responsible Engineer / DATE James B. Couchi a.[o Independ/pyReviewtr DT Duncan Robinson /04ý Engineering Supervisor - PWR Core Analysis / DATE Calvert Cliffs 1, Cycle 19 COLR Page 1 of 25 Rev. 3
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 19 The following limits are included in this Core Operating Limits Report: Specification Title Page Introduction ......................................................................................................... 4 Definitions .......................................................................................................... 5 3.1.1 Shutdown Margin (SDM) ...................................................................................... 6 3.1.3 Moderator Temperature Coefficient (MTC) ........................................................... 6 3.1.4 Control Element Assembly (CEA) Alignment ...................................................... 6 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 6 3.2.1 Linear Heat Rate (LHR) ......................................................................................... 6 3.2.2 Total Planar Radial Peaking Factor (FyT) ............................................................. 7 3.2.3 Total Integrated Radial Peaking Factor (FrT) ........................................................... 7 3.2.5 Axial Shape Index (AS[) ......................................... 7 3.3.1 Reactor Protective System (RPS) Instrumentation - Operating ............................. 7 3.9.1 Boron Concentration ............................................................................................. 8 List of Approved Methodologies ........................................................................ 21 The following figures are included in this Core Operating Limits Report: Number Title Page Figure 3.1.1 Shutdown M argin vs. Tim e in Cycle ...................................................................... 9 Figure 3.1.4 Allowable Time To Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) .............................................. 10 Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power ........................ 11 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle .......................................... 12 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits ............................................. 13 T Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fxy ) vs. Scaling Factor (N-Factor) .............. 14 T Figure 3.2.2 Total Planar Radial Peaking Factor (Fxy ) vs. Allowable Fraction of Rated T herm al Pow er ..................................................................................... .................... 15 T Figure 3.2.3 Total Integrated Radial Peaking Factor (F, ) vs. Allowable Fraction of Rated Thermal Power ..................................................... 16 Figure 3.2.5 DNB Axial Flux Offset Control Limits ............................................................... 17 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power ........................................................ 18 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 .......................................... 19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 .......................... 20 Page 2 of 25 Rev.3 I Cliffs 1, Calvert Cliffs Cycle 19 1, Cycle COLR 19 COLR Page 2 of 25 Rev. 3 1
UNIT 1 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev. No. 1 3 2 3 3 3 4 3 5 3 6 3 7 3 8 3 9 3 10 3 11 3 12 3 13 3 14 3 15 3 16 3 17 3 18 3 19 3 20 3 21 3 22 3 23 3 24 3 25 3 Calvert Cliffs 1, Cycle 19 COLR Page 3 of 25 Rev. 3 1
INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 19. It contains the limits for: Shutdown Margin (SDM) Moderator Temperature Coefficient (MTC) Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear Heat Rate (LHR) Total Planar Radial Peaking Factor (F~yT) T Total Integrated Radial Peaking Factor (Fr) Axial Shape Index (ASI) Reactor Protective System (RPS) Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specifications. The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologies" section of this report and in the Technical Specifications. COLR Revision 0 Initial release of the Unit I Cycle 19 (U1C 19) COLR per Safety Evaluation SE00499 Revision 0. UIC19 is only allowed to operate in Modes 5,6 or in a defueled condition. Although U1C 19 is only authorized to enter Modes 5, 6, and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 1 An alternate core loading pattern has been authorized for U 1C 19 per SE00499 Revision 1. U 1C 19 is only allowed to operate in Modes 6 or in a defueled condition. Although U 1C 19 is only authorized to enter Mode 6 and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 2 U 1C 19 (with the alternate core loading pattern) is now authorized to operate in plant modes 4, 5, 6, and defueled conditions per SE00499 Revision 2. Although all plant modes are not authorized at this time, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes. COLR Revision 3 U 1C 19 (with the alternate core loading pattern) is now authorized to operate in all plant modes per SE00499 Revision 3. Page 4 of 25 Rev.3 I Calvert Cliffs 1,Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 4 of 25 Rev. 3 1
DEFINITIONS Axial Shape Index (ASI) ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core. ASI = lower- upper . YE lower + upper The Axial Shape Index (Y1 ) used for the trip and pretrip signals in the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel. Y, = AYE + B Total Integrated Radial Peaking Factor - FrT The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core. Total Planar Radial Peaking Factor - FxyT The Total Planar Radial Peaking Factor is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes. Page 5 of 25 Rev.3 I Calvert Cliffs Calvert 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 5 of 25 Rev. 3 1
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1) Tavg > 200 0F- Modes 3 and 4: The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1. Tavg*52000 F - Mode 5. The shutdown margin shall be > 3.0% Ap. 3.1.3 Moderator Temperature Coefficient (MTC) (SR 3.1.3.2) The Moderator Temperature Coefficient (MTC) shall be less negative than -3.0 x 10-4 Ap/°F at rated thermal power. 3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1) The allowable time to realign a CEA may be provided by the full core power distribution monitoring system (Better Axial Shape Selection System - BASSS) or COLR Figure 3.1.4, "Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (VrT).y, If COLR Figure 3.1.4 is used, the pre-misaligned F, value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days prior to the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero (0) minutes. 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR 3.1.6.1 and SR 3.1.6.2) The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6. 3.2.1 Linear Heat Rate (LHR) (SR 3.2.1.2 and SR 3.2.1.4) The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1. The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2. When using the excore detector monitoring system (SR 3.2.1.2): The alarm setpoints are equal to the ASI limits; therefore when the alarms are adjusted, they provide indication to the operator that ASI is not within the limits. The axial shape index alarm setpoints are shown as a function of fraction of thermal power on COLR Figure 3.2.1-2. A scaling factor (N-Factor) vs. FxyT is shown in COLR Figure 3.2.1-3. The fraction of thermal power shown in CQLR Figure 3.2.1-2 must be scaled by the N-Factor to determine the axial shape index alarm setpoints as a function of fraction of rated thermal power. Calvert Cliffs 1, Cycle 19 COLR Page 6 of 25 Rev. 3 1
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 19 When using the incore detector monitoring system (SR 3.2.1.4): The alarm setpoints are adjusted to protect the Linear Heat Rate limits shown on COLR Figure 3.2. l-1 and uncertainty factors are appropriately included in the setting of these alarms. The uncertainty factors for the incore detector monitoring system are:
- 1. A measurement-calculational uncertainty factor of 1.062,
- 2. An engineering uncertainty factor of 1.03,
- 3. A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.a For measured thermal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thermal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020. 3.2.2 Total Planar Radial Peaking Factor (FxyT) (SR 3.2.1.1 and SR 3.2.2.1) The calculated value of FxyT shall be limited to < 1.70. The allowable combination of thermal power, CEA position, and FxyT are shown on COLR Figure 3.2.2. 3.2.3 Total Integrated Radial Peaking Factor (FrT) (SR 3.2.3.1) The calculated value of Fr shall be limited to < 1.65. The allowable combinations of thermal power, CEA position, and FrT are shown on COLR Figure 3.2.3. 3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1) The axial shape index and thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of
< 55% when BASSS is operable, or within the limits of COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.
3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Reactor Trip Setpoints) (TS Table 3.3.1-1) The Axial Power Distribution -,High trip setpoint and allowable values are given in COLR Figure 3.3.1-1. The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. The allowable values are to be not less than the larger of(1) 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3. Page 7 of 25 Rev.3 I 1, Cycle Calvert Cliffs 1, 19 COLR Cycle 19 COLR .Page 7 of 25 Rev. 3 1
3.9.1 Boron Concentration (SR 3.9.1.1) The refueling boron concentration will maintain the keff at 0.95 or less (including a 1% Ak/k conservative allowance for -uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained
< 140 0 F.
Refueling Boron Concentration Limits Post-Refueling UGS or RV Head No Restriction Lift Height Restrictions. Minimum Required Refueling Boron Concentration: > 2620 ppm This number includes:
- Chemistry Sampling Uncertainty (Notes 1, 2)
- Boron- 1O Depletion Allowance
- Margin for dilution of refueling pool between low and high level alarms
- Unlimited number of temporary rotations of fuel assemblies
- Extra Conservatism for empty locations during refueling operations.
Note: (1) The above table specifies the minimum technical requirements. It is acceptable for NEOP-13 to conservatively list higher ppm values. (2) See ES200500588-000 Form 8 for detailed information about the included conservatisms. Calvert Cliffs 1, Cycle 19 COLR Page 8 of 25 Rev. 3 1
6 ACCEPTABLE 5+ OPERATION (EOC, 4.5) I 44 I (BOC, 3.5) 34 MINIMUM SHUTDOWN MARGIN 0 zo 24 UNACCEPTABLE OPERATION REGION 1+/-+ 0 BOC EOC TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 19 COLR Page 9 of 25 Rev. 3 1
70 Tirneto FrT Realign
- 1.53 60 minutes 60 (1.53, 60) 1.53 60 minutes 1.54 54 minutes 1.55 48 minutes 1.56 42 minutes 50 . 1.57 36 minutes (0
a 1.58 30 minutes I- 1.59 24 minutes 1.6 18 minutes 40 + 1.61 12 minutes a 1.62 6 minutes z 978 -60 0 FrT I-, 1.63 0 minutes
<j w 1.63 0 minutes z
Uj 30
..J I.LI 20 0
I-- wJ. 10 + ALLOWED REGION 0-f J (1.63,0) 1.50 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Note When using the table with pre-calculated Time to Realign (instead of using the formula), always round up the FrT value to two (2) decimal places (e.g. an FrT = 1.5712 shall be rounded up to 1.58 which would provide 30 minutes to realign a CEA). Figure 3.1.4 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT) Page 10 of25 Rev.3 Calvert Cliffs 1, Cycle 19 1, Cycle COLR 19 COLR Page 10 of 25 Rev. 31
(1.00 FRTP, Group 5 @ 35% Inserted) 0.900 - 4Z44 . .4.I- ,,- 0.800 - - -serted). 05FRTP Group @-- -- -- N An- IE , E 1 (0.70 F TP, Gr up 5 @ 60%.Insehed) I iOPELRATING 3: 0.700 - I i 0- .60 (0.6 FRTP, Group 5@85%Inerted) 1 R I_
.(0.56 FRTPJ Group 4 @ T rns int nserted)
,o Iol s:,' a 0
w 0.400 - FD _ _ u,: ___. t=_I .t Aoe t (Abov Z ser~onPwrDL epint Gru @6°/ sre ZPPDIL.... i ons e 4 0* __EA A _E _ 100% 02000 CCE . 20___ 40 _ 0 0°0 __. INITO10 0°_ 20, 0 0/ 0 0% Lr Inse r ti I I Transien oRted hr a Po 0%RO 0.1.6 isFiur defindoin NEOP-13 Ab CEA GroupeInsertionwLimits vs.pFractionuof3Rated ThermalePower Calvert Cliffs 1. Cycle 19 COLR Page I1I of 25 Rev. 3
17.0 r 7. 16.5 LL 16.0 15.5 W W
=0 W + 15.0
__-J UNACCEPTABLE OPERATION CL _j W W 14.5 M !!.-14.3 0 14.0 ACCEPTABLE OPERA-PON 13.5 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle 25 Rev.3 I Calvert Cliffs 1, Cycle 19 COLR 12 of Page. 12 Page of 25 Rev. 31
1.10 1.05 1.00 0.95 0.90 t 0.85 W
? 0.80 0
0.
, 0.75 0.70 W
M 0.65 o 0.60 z 0 0.55 o 0.50 U-0.45 0.40 0.35 0.30 0.25 (-0.42, 0.20) (0.3, 0.20) 0.20 6
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Page 13 of25 Rev.3 I Cliffs 1, Calvert Cliffs Cycle 19 1, Cycle COLR 19 COLR Page 13 of 25 Rev. 3 1
1.00 (1.4U, 0.90 (1.785, 0.78) I0 0.80 I-C, 0.70 0I-o 0.60 U-a.t ACCEPTABLE VALUE z_i 0.50 CO 0.40 0.30 (1.874, 0.20) 0.20 1.35 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 1.90 T Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs. Scaling Factor (N-Factor) (See NEOP-13 for Administrative Limits) Page 14 of25 Rev.3 I Calvert Cliffs Calvert Cycle 19 1, Cycle Cliffs 1, COLR 19 COLR Page 14 of 25 Rev. 3 1
1.05 S0.95-- w 0.95 (1.70, 1.00) urttK/i-REGIONI IUN
,. 0.85 0.75 I*0.75 (1.785, 0.8) w FT J- LIMIT CURVE 0.65 LL 0.55 0
z 0 i-0.45 U-0.35- ACCEPTABLE
-J OPERATION REGION S0.25 0
(1.874, 0.20) 0.15 0.05 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FxyT T Figure 3.2.2 Total Planar Radial Peaking Factor (F,7T) vs. Allowable Fraction of Rated Thermal Power While operating with FxyT greater than 1.70, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Calvert Cliffs 1, Cycle 19 COLR Page 15 of 25 Rev. 3
1.05 W UNAUUt.-HIAbL-OW0.95 OPERATION 0 REGION CL
-- 0.85 (10.7325, 0.80)
WJ 0.75 I- Tr LIMIT CURVE w 0.65 u- 0.55-- 0 z 0 0.45 ACCEPTABLE OPERATION 0.35 REGION
-1 0.25 0 - (1.819,.0.20) . 0.15 0.05 1.60 1.65 1.70 1.75 1.80 1.85 FrT Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT) VS.
Allowable Fraction of Rated Thermal Power While operating with FrT greater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6) Page 16of25 Rev.3 l Calvert Cliffs 1, Cycle Cliffs 1, 19 COLR Cycle 19 COLR Page 16 of 25 Rev. 3 1
1.10 1.05
,-I 1.00 W > 0.95 -J 0.90 WU 3 0.85 0
0- 0.80 m 0.75 0 0.70
-I -J 0.65 0.60 R 0.55 0.50 L-z 0.45 0
C.-- 0.40 0.35 0.30 0.25 (-0.42, 0.20) (0.3, 0.20) 0.20 6
-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.5 DNIB Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power per SE00433)
(See NEOP-13 for Administrative Limits) Page 17 of25 Rev.3 I COLR 19 COLR Calvert Cliffs 1, Cycle 19 Page 17 of 25 Rev. 3 1
1.300 1.250 1.200 UNACCEPTABLE (0.0, 1.17) UNACCEPTABLE 1.150 OPERATION OPERATION REGION REGION 1.100 1.050 1.000 (-0.2, 1.00) (0.2,1.00) W 0.950 O 0.900 a.
. 0.850 n 0.800 C- 0.750 UJ0.700 u, 0.650 0
Z 0.600 ACCEPTABLE P OPERATION o 0.550 ~REGION R LL 0.500 0.450 0.400 (-0.6, 0.40) (0.6, 0.40) 0.350 0.300 0.250 0.200 0.150 I I I I I
-0.80 -0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIAL SHAPE INDEX, Y, Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs 1, Cycle 19 COLR Page 18 of 25 Rev. 3
1.60 P var= 2869.5 x (Al) x (QR1) + 17.98 x Tin -10820 1.501 QDN= Al x QR1 1.40 (-0.6, 1.3) 1.30 1.20
~~Al +.67 x AS;I + 1.(
J /0.6, 1.1 1.10 Ai= 0.5 x ,SI + 1 *0 1.00 0.0, 1 0) 03.QO
-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 (ASI vs. A 1 )
Calvert Cliffs 1, Cycle 19 COLR Page 19 of 25 Rev. 3
PvrI = 2869.5 x (Al) x (QR1) + 17.98 x Ti,- 10820 var QDNB =Al x ORi 1.2 (1.2, 1.2) 1.1 1.0 0.9 0.8 0.7 t 0.6 0.5 0.4 0.3 0.2 0.1 0.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 FRACTION OF RATED THERMAL POWER (RTP) Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR 1) Calvert Cliffs 1, Cycle 19 COLR Page 20 of 25 Rev. 3 1
LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev 1-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986. Additionally, Supplement 2-P-A dated June 1998. (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (2) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for Calvert Cliffs Units I and IL," December 1979 (Methodology forSpecifications 3.3.1, 3.1.6, 3.2.2, 3.2.3) (3) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (4) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2," December 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (6) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit 1 Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN- 191 (B)-P)] (7) CEN-348(B)-P, "Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (8) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987,. Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-16 1-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (10) CENPD-162-P-A, "Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (11) CENPD-207-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-Uniform Axial Power Distribution," December 1984 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (12) CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) (13) CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) Calvert Cliffs 1, Cycle 19 COLR Page 21 of 25 Rev. 3
(14) CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (16) CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) (17) CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (18) CEN-161-(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (19) CEN-161-(B)-P, Supplement l-P, "Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement l-P, Improvements to Fuel Evaluation Model" (Approval of CEN- 161 (B), Supplement 1-P) (21) CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2) (22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15, 1981, LD-8 1-095, Enclosure l-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1, 3.272) (23) CENPD-132, Supplement 3-P-A, "Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1, 3.2.2 and approval of Letter LD-81-095, dated December 15, 1981) (24) CENPD-133, Supplement 5, "CEFLASH-4A, a FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (25) CENPD-134, Supplement 2, "COMPERC-Il, a Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1, 3.2.2) (26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31, 1986, "Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2) (27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2) 22 of 25 Page 22 of 25 Rev.3 ! Calvert Cliffs 1, Cycle 19 1, Cycle COLR 19 COLR Page Rev. 3 1
(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD-135, Supplement 5" (29) CENPD-137, Supplement l-P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27, 1977, "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" (32) CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod.and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1, 3.2.2) (33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD- 138, Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1 and 3.1.3 and 3.1.6) (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, "Safety Evaluation Report Approving Unit 1 Cycle 8 License Application" (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, "Amendment to Operating License No. 50-317, Fifth Cycle License Application" (Section 7.1.2 contains Methodology for Specifications 3.1.1, 3.9. 1) (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12, 1980, "Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 & 50-318, Request for Amendment" (Methodology for Specifications 3.1.4) (39) Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7, 1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2) (Support for Specification 3.1.4) (40) CENPD-188-A, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) Page 23 of 25 Rev.3 Calvert Cycle 19 1, Cycle Calvert Cliffs 1, GOLR 19 COLR Page 23 of 25 Rev. 3 1
(41) The power distribution monitoring system referenced in various specifications and the BASES, is described in the following documents: CENPD-153-P, Revision i-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5) ii. CEN-1 19(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application) iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7, 1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.4, 3.2.2, 3.2.3, 3.2.5) iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, "Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. McDonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, "Approval to Use Convolution Technique in Main Steam Line Break Analysis - Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. M90897 and M90898)" (Methodology for Specification 3.2.3). (43) CENPD-387-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel" (44) CENPD-199-P, Supplement 2-P-A, Appendix A, Latest Approved Revision, "CE Setpoint Methodology," June 1998. (45) CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs". (46) CENPD-132, Supplement 4-P-A, Latest Approved Revision, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model". (47) CENPD-137, Supplement 2-P-A, Latest Approved Revision, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model". (48) WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores,". June 1988. (49) WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986. (50) WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery," April 1989. Calvert Cliffs 1, Cycle 19 COLR Page 24 of 25 Rev. 3
(51) WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004. (52) WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," August 2004. (53) WCAP-15604-NP, Revision 2-A, "Limited Scope High Burnup Lead Test Assemblies," September 2003. Calvert Cliffs 1, Cycle 19 COLR Page 25 of 25 Rev. 3}}