ML031190244
| ML031190244 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/23/2003 |
| From: | Katz P Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031190244 (26) | |
Text
Peter E. Katz 1650 Calvert Cliffs Parkway Vice President Lusby, Maryland 20657 Calvert Cliffs Nuclear Power Plant 410 495-4455 Constellation Generation Group, LLC 410 495-3500 Fax Constellation I vEnergy Group April 23, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Core Operating Limits Report for Unit 2, Cycle 15, Revision 0 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 2, Cycle 15, Revision 0 (Attachment 1) is provided for your records.
Please replace the Unit 2 Core Operating Limits Report in its entirety, with the attached Revision 0.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very t ly yours, PEK/CAN/bjd
Attachment:
(1) Core Operating Limits Report for Unit 2, Cycle 15, Revision 0 cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR G. S. Vissing, NRC J1D
ATTACHMENT (1)
CORE OPERATING LIMITS REPORT UNIT 2, CYCLE 15, REVISION 0 Calvert Cliffs Nuclear Power Plant, Inc.
April 23, 2003
CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 15 REVISION 0 INDEPDlIE R /DIATE A,,RIA6P;1E\GiE- FOSU / DATE£ Page 1 of 24 Rev. 0 Calvert Cliffs 2, Cycle 15 2, Cycle COLR 15 COLR Page 1 of 24 Rev. 0
9W CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 15 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 (FsT)........................................................7 3.2.3 Total Integrated Radial Peaking Factor (FT) .................. 7..........................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 Margin vs. Time in Cycle ................................................ 9 Figure 3.1.4 Allowable Time To Realign CEA Versus T Initial Total Integrated Radial Peaking Factor (F )............................................... 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 Figure 3.2.1-3 Total Planar Radial Peaking Factor (F,,y ) vs.
Scaling Factor (N-Factor) .............................. 14 Figure 3.2.2 Total Planar Radial Peaking Factor (FyT) vs. Allowable Fraction of Rated Thermal Power .............................. 15 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 24 Rev. 0 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 2 of 24 Rev. 0
-VW UNIT 2 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 Page 3 of 24 Rev. 0 Calvert Cliffs 2, Calvert Cliffs 2, Cycle 15 COLR Cycle 15 COLR Page 3 of 24 Rev. 0
-VW INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 15. It contains the limits for:
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 (FjT)
Total Integrated Radial Peaking Factor (FP)
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 Unit 2 Cycle 15 COLR (Safety Evaluation SE00485).
Page 4 of 24 Rev. 0 Calvert Cliffs Calvert 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 4 of 24 Rev. 0
-1qPW-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 Y 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 - 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.
Page 5 of 24 Rev. 0 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 5 of 24 Rev. 0
-w CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 15 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)
Tavg > 200 0 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 Inteqrated Radial Peaking Factor (FJT)." 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.
Page 6 of 24 Rev. 0 Calvert Cliffs Calvert 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 6 of 24 Rev. 0
CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 15 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 (F~yT) (SR 3.2.1.1 and SR 3.2.2.1)
The calculated value of F yT shall be limited to < 1.65.
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)
The calculated value of FrT shall be limited to < 1.65.
The allowable combinations of thermal power, CEA position, and FT 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 24 Rev. 0 Cliffs 2, Calvert Cliffs Calvert 2, Cycle lIS COLR Cycle 15 COLR Page 7 of 24 Rev. 0
3.9.1 Boron Concentration (SR 3.9.1.1)
The refueling boron concentration will maintain the kff 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. The 0 Credited CEA requirements shall apply for a Post-Refueling Upper Guide Structure or Reactor Vessel Head Lift of more than 12 inches.
Refueling Boron Concentration Limits 56 Credited CEA f) Cred-ited,r'DEA Post Refueling UGS or RV Head Lift < 12 inches > 12 inches.
Height Restrictions:
COLR/Tech Spec Limit 2255 ppm 2626 ppm 1% Chemistry Sampling Uncertainty 23 ppm 27 ppm Boron-1O Depletion to 19.40 a/o 47 ppm 54 ppm Refueling Boron Concentration Limit including Chemistry Sampling > 2325 ppm > 2707 ppm uncertainty and Boron-1O Depletion Dilution of the Refueling Pool between Low and High Level Alarms 73 ppm 86 ppm with Refueling Pool Flooded Temporary Rotations of Fuel 0 ppm 0 ppm Assemblies (20 ppm allowance is already included in above COLR/Tech Spec Limit)
Refueling Boron Concentration > 2398 ppm > 2793 ppm Administrative Limit ___ _
Page 8 of 24 Rev. 0 Cliffs 2, Calvert Cliffs Cycle 15 2, Cycle COLR 15 COLR Page 8 of 24 Rev. 0
6 I-ACCEPTABLE 5+ OPERATION REGION (EOC, 4.4)
-4
~1131
-J (BOG, 3.5) z C) 3 MINIMUM SHUTDOWN MARGIN 2 2 I- UNACCEPTABLE Cl OPERATION REGION U,
1 0
BOC EOC TIME INCYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Page 9 of 24 Rev. 0 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 9 of 24 Rev. 0
70 60 (1.53, 60) 50 z
40 ,978 - 600 FrT CD, zM 30\
O LU 20 102 10 ALLOWED REGION 0
(1.63,0) 1.50 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Figure 3.1.4 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor (FrT)
Page 10 of 24 Rev. 0 COLR Calvert Cliffs 2, Calvert Cliffs Cycle 15 2, Cycle }5 COLR Page 10 of 24 Rev. 0
o 0.800 - (J G _ .
> r \( .75, G oup 5 @ S0°%)
0.700 -(7,ro -%
(O05, Gr up 5 85%)
- 0.600 -
w _.56. G up 4 @50%)
S 0.500 Lng TermSteady O State Insertion LUmit,
°i 0 Group 5 25%-
. 0.400 -
LL 0
z 0.300 -
o o . 00 (0.2( ~Grou) 3 0%) - -
- Short Term Steady 0.100 _ State Insertion Limit, l __
- Group 4 i20%
-7 (0.0 .Grou 30 0%) - -
Allowable BASSS - (Group 5 @ 55%)
LOperating Region 5 3 1 0 20 40 60 80 100 0 20 40 60 i
80 100 0 20 40 60 80 1C 136.0 108.8 81.6 54A 27.2 0.0 136.0 108.8 81.6 54.4 27.2 0.0 136.0 108.8 81.6 54.4 27.2 0..0 I I 1 41 1 1 1 1 1 2 1 1 1 0 20 40 60 80 100 0 20 40 60 80 100 1360 108.8 81.6 544 27.2 0.0 136.0 108.8 81.6 54.4 27.2 0.0
%CEA INSERTION INCHES CEA WITHDRAWN (ARO is defined in NEOP-23)
Figure 3.1.6
17.0 7 . I 16.5 1 + F L L 16.0 t l l l I Fc ww0 ff 15.5 I ILI A: a IM 0 W + 15.0 1 1- 1 i I z D
=i UNACCEPTABLE
<: 0 us -i y- +
a' X 14.5 D l l i M - 14.3 0
j 14.0 1t
____ _ 1ACCEPTABLE OPERATION _
13.5 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Page 12 of 24 Rev. 0 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 12 of 24 Rev. 0
1.100 -
1.050 -
1.000 - (-0.06.1.00) 12,1.00) 0.950 UNACCEPTABLE UNACCEPTABLE 0.900 OPERATION OPERATION 080REGION REGION 3 0.800 0
L 0.750 E 0.700 (-0.3, 0.70) ACCEPTABLE (0.3, 0.70) us OPERATION 0.650- REGION o 0.600 z
o 0.550 0 0.500 (-0.3,0.50)
UL 0.450 0.400 0.350 0.300 -/
0.250 (-0.42, 0.20) (0.3, 0.20) 0.200- _
-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)
(See NEOP-23 for Administrative Limits)
Page 13 of 24 Rev. 0 COLR Calvert Cliffs Cycle 15 2, Cycle Cliffs 2, 15 COLR Page 13 of 24 Rev. 0
1.00 0.90 -
0 0.80 zi 0.70 2:
sO U.
0 0.60 z
0.50 C,
U),
0.40 0.30 0.20
- 1.40 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 1.85 F T Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxT) vs.
Scaling Factor (N-Factor)
(See NEOP-23 for Administrative Limits)
Page 14 of 24 Rev. 0 Calvert Cliffs Calvert Cliffs 2, 15 COLR Cycle IS 2, Cycle COLR Page 14 of 24 Rev. 0
1.05 a 0.95 OPERATION w REGION 0
C. 0.85 (1.7325, 0.80)
-J 0 0.75 F,<,T LIMIT CURVE
\
n 0.65 ACCEPTABLE L 0.55 OPERATION 0 0.4 REGION\
P: 0.45-IL 035
\
g 0.25 - (1.819, 0.20
-j
<1 0.15 0.05 I 1.60 1.65 1.70 1.75 1.80 1.85 T
Fxy Figure 3.2.2 Total Planar Radial Peaking Factor (FxT) vs.
Allowable Fraction of Rated Thermal Power While operating with FxyT greater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6)
Page 15 of24 Rev. 0 Cliffs 2, Calvert Cliffs Calvert Cycle 15 2, Cycle COLR 15 COLR Page 1S of 24 Rev. 0
1.05 0.95 OPERATION REGION 0.85 n(1.7325, 0.80) 0 EL
-j Fr LIMIT CURVE w
': 0.65 I 0.55 o
zO ACCEPTABLE I- OPERATION a 0.45 REGION
'U
-J t 0.35 0
- 0.25 (1.819,0.20) 0.15 0.05 I I I 1.60 1.65 1.70 1.75 1.80 1.85 T
Fr Figure 3.2.3 Total Integrated Radial Peaking Factor (FT) 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 16of24 Rev. 0 Calve2rt Cliffs Calvert 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 16 of 24 Rev. 0
1.100' I 1.050 -
1.000 - (-0.08,1 .00) X(0. I 1.00)
-J w
0.950 - UNACCEPTABLE UNACCEPTABLE w OPERATION OPERATION uI 0.900 -
w REGION / \ REGION 0.850 -
0.
IL All 0.800 - (0.3, 0.80)
-j 0.750 -
w to ACCEPTABLE 0 0.700 - (-0.3, 0.70) OPPATIIN
-j
-J REGION 0.650 -
0.600 -
IL 0
0.550-0.500 - (-0.3, 0.50) z 0.450 -
0 0.400-U 0.350 -
10 0.300 -
0.250 t D..42, 0.20) (0.3, 0.20) 0.200 1- I 7)
-0.60I -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 (See NEOP-23 for Administrative Limits)
Page 17of24 Rev. 0 Calvert Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 17of 24 Rev. 0
1.300 -
1.250 1.200 1.150 1.100 1.050 1.000 ILl 0.950 0 0.900 IL 0.850 0.800 CM O
0.750 LU 0.700 M 0.650 0
z 0.600 0
C.) 0.550 U~. 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 Page 18 of 24 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cyvcle 15 COLR Page I18 of 24 Rev. 0
1.60 E § f P var= 2869.5 x (Al) x (QRI) + 17.98 x Min - 10820 1.50 Q Al X QRI 1.40 - == = = = =
1.30 ( 0.6.1.3)_
1.20- v_-
Al 40.1 67xASI+1.
1.10- / L}. .1 Al 0.5 x }i) 1 0~
O \i 1.00- _ _
(0.0,1I 0)
-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 )
Rev. 0 Page 19 of 24 Calvert Cliffs 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR Page 19 of 24 Rev. 0
1.2 1.2) 1.1 1.0 0.9 0.8 0.7 a 0.6 0.5 0.4 0.3 0.2 0.1 i
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 Figure 3.3.1-3 Thermal MarginlLow Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR 1 )
Page 20 of 24 Rev. 0 Cliffs 2, Calvert Cliffs Cycle 15 2, Cycle COLR 15 COLFR Page 20 of 24 Rev. 0
LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev -P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986 (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-l 91 (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 50-3 18, "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-1 62-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-Uniforn 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, 3.1.6,32.3,3.2.5)
(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)
Page 21 of 24 Rev. 0 Cliffs 2, Calvert Cliffs Cycle 15 2, Cycle COLR IS COLR Page 21 of 24 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-13 9-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 1-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-1 32, 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-il, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2)
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(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD-1 35, Supplement 5" (29) CENPD-137, Supplement 1-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-1 37, Supplement I-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. I & 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-1 88-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)
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(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 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-3 87-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) CENPD404-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".
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