ML043210142
| ML043210142 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/10/2004 |
| From: | Vanderheyden G Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043210142 (26) | |
Text
George Vanderheyden 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 I Constellation Energy November 10, 2004 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 I Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 2, Cycle 15, Revision I (Attachment 1) is provided for your records.
Please replace the Unit 2 Core Operating Limits Report in its entirety, with the attached Revision 1.
Should you have questions regarding this matter, we will be pleased to dis uss them with you.
GV/CAN/bjd
Attachment:
(1) Core Operating Limits Report for Unit 2, Cycle 15, Revision I cc: (Without Attachment)
J. Petro, Esquire S. J. Collins, NRC J. E. Silberg, Esquire Resident Inspector, NRC R. V. Guzman, NRC R. 1.McLean, DNR
)I
ATTACHMENT (1)
CORE OPERATING LIMITS REPORT UNIT 2, CYCLE 15, REVISION 1 Calvert Cliffs Nuclear Power Plant, Inc.
November 10, 2004
CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 15 REVISION 1 'I
-; a~& .ILMAI142)0 s RESPONSIBLE ENGINEER / DATE DEPENDENT REVIEWERAD A PRINCIPAL ENG -FOSU/DATE Calvert Cliffs 2, Cycle 15 COLR Page I of24 Rev.lIl
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 (F,,T)...................................................................7 3.2.3 Total Integrated Radial Peaking Factor (FJT) ............................................ 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 ......................... II 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,7y ) vs.
Scaling Factor (N-Factor) ................................................... 14 Figure 3.2.2 Total Planar Radial Peaking Factor (Fry ) vs. Allowable Fraction of Rated Thermal Power ................................................... 15 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 I .............................................. 19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 .............................................. 20 Calvert Cliffs 2, Cycle 15 COLR Page 2 of 24 Rev. 0
UNIT 2 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev. No.
I I 2 0 3 1 4 __I 5 L 6 0 7 0 8 1 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 Calvert Cliffs 2, Cycle 15 COLR Page 3 of 24 Rev. I I
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 (FT) -
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 requir-ements 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).
COLR Revision 1 Revised requirements for Refueling Boron Concentration for core burnup > 16 GWD/MTU (Safety Evaluation SE00485) 4 of 24 Rev.l Page 2, Cycle Calvert Cliffs 2' 15 COLR Cycle 15 COLR ,_I. . Page 4 of 24 Rev. I I
I it 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 (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 - F1yT 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 2, Cycle 15 COLR -; Page 5 of 24 Rev. 0 '
CYCLE SPECIFIC LIMITS FOR UNIT 2,-CYCLE 15 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1) -
Tavg > 200 "F- Modes 3 and4:
The'shutdown rMargin shall beequal to'or'greaterthanthe limit line of COLRFigure 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 104 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 (FrT)." If COLR Figure 3.1.4 is used, the pre-misaligned F. value used to determine the allowable time to realigni 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 nmonitoring 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. F,,yT 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 2, Calvert Cliffs 2, Cycle 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 alarns.
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 FT 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 FT shall be limited to < 1.65.
The allowable combinations of thermal power, CEA position, and Fr 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.
Calvert Cliffs 2, Cycle 15 COLR Page 7 of 24 kev.O ,
3.9.1 Boron Concentration (SR 3.9.1.1)
The refueling boron concentration will maintain the kfrfat 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 0 Credited CEAs U2C15 > 16 GWD/MTU Post Refueling UGS or RV Head Lift No restriction Height Restrictions:
COLRTech Spec Limit 2255 ppm 1% Chemistry Sampling Uncertainty 23 ppm Boron-10 Depletion to 19.40 a/o 47 ppm Refueling Boron Concentration Limit including Chemistry Sampling > 2325 ppm uncertainty and Boron-1O Depletion Dilution of the Refueling Pool between Low and High Level Alarms 73 ppm with Refueling Pool Flooded Temporary Rotations of Fuel Assemblies (20 ppm allowance is 0 ppm already included in above COLR/Tech Spec Limit)
Refueling Boron Concentration > 2398 ppm Administrative Limit Calvert Cliffs 2, Cycle 15 COLR Page 8 of 24 Rev. I I
6 ACCEPTABLE 5+ OPERATION REGION (EOC, 4.4)
I cx 1* 4-
-J 4 -
z MINIMUM SHUTDOWN MARGIN z
022 I UNACCEPTABLE I- OPERATION REGION Cn 1I 0
BOC EOC TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Page 9 of 24 Rev. 0 Calvert Cliffs 2, Cycle Cliffs 2, Cycle 15 COLR 15 COLR Page 9 of 24 Rev. 0
70 60 3 (1.53, 60) 50 W
I-z 40 978 - 600 T Z 30 W.,
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)
Calvert Cliffs 2, Cycle 15 COLR Page IO of 24 Rev. 0
1.000 0.900 - , - - - -
uLJ C 0.800 - _-\_ _ _
- n. ((.75, G oup 5 50O )
-j 4 .0. 0 ,Grou 5a ; 0%)-_
0.700 - I (0 5, Gr up5 ! 85%)
I..
ILL ; .DUV .56, G oup4 50')
0.500 Long Term Steady . -
LL i State Insertion Limit, 0.400
- Group 5 @ 25%
C 4
U-
.0.200 _ -- -
Short Term Steady 0.100
- State Insertion Limit, _ _
- Group 4 @ 20%
n nnn Allowable BASSS _ - (Group 5 @ 55%)
Operating Regiojn 5 3 I 1 1 I _I I I I I I I L L 1 I LI 0 20 40 60 80 100 0 20 40 60 80 100 0 20 40 60 80 100 136.0 108.8 81.6 64.4 27.2 0.0 136.0 108.8 81.6 54.4 27.2 0.0 136.0 108.8 81.6 64.4 27.2 0.0 4
L 0 20 40 60
-I 80 100 I 0 I
20 I 12 1 40 60 1
80 100 1
136.0 108.8 81.6 ; 54.4 27.2 0.0 136.0 108.8 81.6 54.4 27.2 0.0
%CEA INSERTION INCHES CEA WITHDRAWN (ARO isdefined in NEOP-23)
Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Page 11 of 24 Rev. 0 Calvert Cliffs Cycle 15 2, Cycle Cliffs 2, 15 COLR COLR Page I11 of 24 Rev. 0
17.0 16.5 I--
U.
16.0 0
Cl - 14.5 LU 0
0
+ 15.0 z a I UNACCEPTABLE OPERATION
- a. -j LU 14.5
-j
.' 14.3 0
-j
-j 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 2, 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 z 0.850 REGION REGION 3 0.800- /
0
° 0.750-/
E 0.700 - (-0.3, 0.70) ACCEPTABLE (0.3, 0.70)
OPERATION j 0.650 REGION 0 0.600-z o 0.550 - -
L 0.500 (-0.3, 0.50) 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 Calvert Cliffs Cycle 15 2, Cycle Cliffs 2, COLR 15 COLR Page 13 of 24 Rev. 0
1.00 0.90 -.
t 0.80 IL z 0.70 0
o 0.60 .
U.
z:3 0.50 .
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 T
FxY Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs.
Scaling Factor (N-Factor)
(See NEOP-23 for Administrative Limits)
Calvert Cliffs 2, Cycle 15 COLR Page 14 of 24 Rev. 0
1.05 i -(1.65,1.00)
UNACCEPTABLE W 0.95 - OPERATION w REGION
° 0.85-
-1 (1.7325, 0.80)
W 0.75-w \ FOUT LIMIT CUP RVE I-
@ 0.65- Il ACCEPTABLE IL 0.55- I OPERATION 0 REGION z
0 P 0.45- I-I.
-J im 2 0.25- I.
0 (1.819. 0.20)
-j
< 0.15 -
^^ Io II I I U.UZD -- _
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 F Tgreater than 1.65, withdraw CEAs to or above the Long Term S¶eady State Insertion Limits (Figure 3.1.6)
Calvert Cliffs 2, Cycle 15 COLR Page 15 of 24 Rev. 0
1.05 W: ' _ UNACCtiP I AULM W 0.95 OPERATION 0 REGION EL
-10.85 (1.7325, 0.80) wu 0.75 UJ 0.5 - \FIT LIMIT CURVE w 0.65 055
.5 \
0 2
0 0.45 ACCEPTABLE C OPERATION Lg 0.35 REGION Lu LU
,M 0.25 0.15 (1.819, 0.20 J0.15-0.05 I 1.60 1.65 1.70 1.75 1.80 1.85 T
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)
Calvert Cliffs 2, Cycle 15 COLR Page 16 of 24 Rev. 0
1.100 -
1.050 1.000 - - (-0.08,1.00) .15,1.00) t 0.950 UNACCEPTABLE UNACCEPTABLE X OPERATION OPERATION E 0.00 REGION REGION
~: 0.850 0
IL 0.800 (0.3, 0.80)
L1 0.750- ACCEPTABLE 2 0.700 (-0.3,0.70) OPERATION J 0.650 REGION 2 0.600
> 0.500 (-0.3.0.50)
LL 0
0.450 0
, 0.400 g 0.350 U.
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 3.2.5 DNB Axial Flux Offset Control Limits (See NEOP-23 for Administrative Limits)
Page 17 of 24 Rev. 0 Calvert Cliffs Cycle 15 2, Cycle Cliffs 2, COLR 15 COLR Page 17 of 24 Rev. 0
1.300 _
1.250 1.200 1.150 1.100 1.050 1.000 tw 0.950 O 0.900 g 0.850 a 0.800 a 0.750 0.700 x; 0.650 0
zo 0.600-U 0.550
- a. 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 Cycle 15 COLR Page 18 of 24 Rev. 0
1.60 P var= 2869.5 x (Al) x (QR1) + 17.98 x Tin - 10820 1.50 -
QDN Al XQRI 1.40
(-0.6,11.3) 1.30 1.20
,X.Al- +0.1E D7 X A'S +061.1-1.10 Al = *0.5x XI +1 0 \
1.00 _ _ I (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 MarginlLow Pressure Trip Setpoint - Part I (ASI vs. A1 )
Page 19of24 Rev. 0 Calvert Cliffs Cycle 15 2, Cycle Cliffs 2, 15 COLR COLR Page 19 of 24 Rev. 0
Trip = 2869.5 x (Al) x (QRI) + 17.98 x Tin - 10820 var QDNB==Al xQRl 1.2 I I I I I (1.2,1.2) 1.1 . l l l ] QR, =(RTP) +0.0 zi 1.0 0.9 0.8 0.7 _ QRI = 0.375 x (RTP) + 0.625 a 0.6 0.5 0.4
- = /; I V-QR
-T I 1 = 0.9167 x (RTP) + 0.3 0.3 = = - - i -
0.2 1 (0.0.10.3) 0.1 0.0 III 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 Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QRI)
Rev. 0 Cycle 15 2, Cycle Cliffs 2, COLR 15 COLR Page 20 of 24 Calvert Cliffs Page 20 of 24 Rev. 0
LIST OF APPROVED METHODOLOGIES (1) CENPD-199-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 (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 Systerm 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 Meth6ds 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-Uniformn 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)i Page 21 of 24 Rev. 0 Calvert Cliffs Calvert 2, Cycle Cliffs 2, 15 COLR Cycle 15 COLR ; - I 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 Desigris 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, Supplemrent 1-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 Modelt' (Approval of CEN-161(B), Supplement I-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, Su plement 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-135, 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, Supplemenit 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977T (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, Suppleinent 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 Applicatior" (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)
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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-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 UseConvolution 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-I99-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, Suppleinent 2-P-A, Latest Approved Revision, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model".
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