ML061170429
| ML061170429 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/11/2006 |
| From: | Spina J Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML061170429 (27) | |
Text
e James A. Spina Vice President Calvert Cliffs Nuclear Power Plant, Inc.
1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.4455 410.495.3500 Fax Constellation Energy, Generation Group April 11, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Core Operating Limits Report for Unit 1. Cycle 18, Revision 2 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 1, Cycle 18, Revision 2 (Attachment 1) is provided for your records. Note that we have not provided Revision 0 or Revision I for this Cycle because they were temporary and only applied to Modes 5 and 6 and the defueled condition. Revision 2 covers Unit 1, Cycle 18 for all modes of operation.
Please replace the Unit I Core Operating Limits Report in its entirety, with the attached Revision 2.
Should you have questions regarding this matter, please contact Mr. L. S. Larragoite at (410) 495-4922.
Very truly yours, 4Aw 6t,1.
JAS/PSF/bjd
Attachment:
(1)
Core Operating Limits Report for Unit 1, Cycle 18, Revision 2 cc:
Resident Inspector, NRC (Without Attachment)
P. D. Milano, NRC S. J. Collins, NRC R. I. McLean, DNR 4bb'1
ATTACHMENT (1)
CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 18, REVISION 2 Calvert Cliffs Nuclear Power Plant, Inc.
April 11, 2006
I Constellation Energy Calvert Cliffs Nuclear Power Plant, Inc.
Core Operating Limits Report (COLR)
Unit 1 Cycle 18 Revision 2
.1 Effective Date:
L113),O(.
&1, 10W
'I v
RESPONSIBLE ENGINEER
/
DATE Q 6 @
- 6-e 2 / l D (
D., --
VI&DE}ENDENT REVIEWER
/
DATE PRI CIPAL ENG1 ER - FOSU I DATE
( A Calvert Cliffs 1, Cycle 18 COLR Page 1 of 25 Rev.
Calvert Cliffs 1, Cycle 18 COLR Page I of 25 Rev. 2! I
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CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 18 The following limits are included in this Core Operating Limits Report:
Specification Title Page 3.1.1 3.1.3 3.1.4 3.1.6 3.2.1 3.2.2 3.2.3 3.2.5 3.3.1 3.9.1 Introduction...........................................
4 Definitions....................................................................................................................5 Shutdown Margin (SDM)..........................................
6 Moderator Temperature Coefficient (MTC)...........................................
6 Control Element Assembly (CEA) Alignment................
........................... 6 Regulating Control Element Assembly (CEA) Insertion Limits................................ 6 Linear Heat Rate (LHR)...........................................
6 Total Planar Radial Peaking Factor (FyT).............
7..............................7 Total Integrated Radial Peaking Factor (FT)..........................................
7 Axial Shape Index (ASI)...........................................
7 Reactor Protective System (RPS) Instrumentation - Operating.................................. 7 Boron Concentration..........................................
8 List of Approved Methodologies.......................................... 21 The following figures are included in this Core Operating Limits Report:
U Number Title Page Figure 3.1.1 Figure 3.1.4 Figure 3.1.6 Figure 3.2.1-1 Figure 3.2.1-2 Figure 3.2.1-3 Figure 3.2.2 Figure 3.2.3 Figure 3.2.5 Figure 3.3.1-1 Figure 3.3.1-2 Figure 3.3.1-3 Shutdown Margin vs. Time in Cycle....................................................
9 Allowable Time To Realign CEA Versus T
Initial Total Integrated Radial Peaking Factor (F. ).10 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power.1 Allowable Peak Linear Heat Rate vs. Time in Cycle.12 Linear Heat Rate Axial Flux Offset Control Limits.13 Total Planar Radial Peaking Factor (Fxy ) vs.
Scaling Factor (N-Factor).14 Total Planar Radial Peaking Factor (Fxy T) vs. Allowable Fraction of Rated Thermal Power.15 Total Integrated Radial Peaking Factor (F. ) vs.
Allowable Fraction of Rated Thermal Power.16 DNB Axial Flux Offset Control Limits.17 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power.18 Thermal Margin/Low Pressure Trip Setpoint -Part 1.19 Thermal Margin/Low Pressure Trip Setpoint - Part 2.20 Calvert Cliffs 1, Cycle 18 COLR Page 2 of 25 Rev. 0
UNIT 1 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No.
Rev. No.
1 2
2 0
3 2
4 2
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
2 1 0
22 0
23 0
24 0
25 0
.I.
Calvert Cliffs 1, Cycle 18 COLR Page 3 of 25 Rev.2 Calvert Cliffs I, Cycle 18 COLR Page 3 of 25 Rev. 2 l
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INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 18. 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 (FxT)
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 K
Initial release of the Unit 1 Cycle 18 (UICl8) COLR per Safety Evaluation SE00497 Rev. 0. U1Cl8 is only allowed to operate in Mode 6 or in a defueled condition. Although UIC18 is only authorized to enter Mode 6, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes.
COLR Revision 1 Revised to now allow operation ofUlCl8 in plant modes 5, 6, or defiueled per SE00497 Rev. 1. Although UlI C 8 is only authorized to enter Modes 5 and 6, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes.
COLR Revision 2 Revised to now allow eration ofUIC18 in all plant modes per SE00497 Rev. 2.
Calvert Cliffs 1, Cycle 18 COLR Page 4 of 25 Rev.2 Calvert Cliffs 1, Cycle 18 COLR Page 4 of 25 Rev.2 I
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 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 - F'T-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.
(;I Calvert Cliffs 1, Cycle 18 COLR Page 5 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 5 of 25 Rev. 0
CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 18 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*: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 104 Ap/F at rated thermal power.
3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.R.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 Inteqyated 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 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. FyT 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.
Calvert Cliffs 1, Cycle 18 COLR Page 6 of 25 Rev. 0
CYCLE SPECIFIC LIMITS FOR UNIT i, CYCLE 18 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 (Fy T) (SR 3.2.1.1 and SR 3.2.2.1)
The calculated value of F17y shall be limited to < 1.70.
The allowable combination of thermal power, CEA position, and F7yT are shown on COLR Figure 3.2.2.
r 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 Sbape 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.
U' Calvert Cliffs 1, Cycle 18 COLR Page 7 of 25 Rev. 0 Calvert Cliffs l, Cycle 18 COLR Page 7 of 25 Rev. 0
3.9.1 Boron Concentration (SR 3.9.1.1)
The refueling boron concentration will maintain the kcff at 0.95 or less (including a 1% Ak/ick conservative allowance for uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained < 140 OF.
The "0 Credited CEAs" requirement (Option 2 or 3) shall apply for all Post-Refueling Upper Guide Structure or Reactor Vessel Head Lifts of more than 12 inches.
Note Option 1 Is the designated refueling boron concentration for UlC18. The Control Room Shift Manager or Control Room Supervisor shall contact both Chemistry and Nuclear Fuel Services prior to implementing one of the other refueling boron concentration options to confirm all affected groups have appropriate controls In place.
Refueling Boron Concentration Limits OOtion I Option 2 Option 3
.,rdie f
aOredt e
Post-Refueling UGS or RV Head lift height 512 inches No restriction No restriction restrictions.
COLRJTech Spec Limit 2264 ppm 2396 ppm 2396 ppm Chemistry Sampling 23 ppm 24 ppm 24 ppm Boron-10 Depletion 47 ppm 50 ppm 50 ppm Refueling Boron Concentration
> 2334 ppm
> 2470 ppm
> 2470 ppm Limit including Chemistry Sampling uncertainty and Boron-] 0 Depletion Dilution of the Refueling Pool between Low and 73 ppm 78 ppm 78 ppm High Level Alarms with Refueling Pool Flooded Any number of Temporary An allowance of 20 An allowance of 20 An allowance of 20 ppm is Rotations of Fuel ppm is already included ppm is already included already included in the Assemblies in the above in the above above COLRITech Spec COLR/Tech Spec Limit COLRITech Spec Limit Limit An allowance of 50 An allowance of 50 An allowance of 50 ppm is UICI8 Allowance for ppm is already included ppm is already included already included in the Holes in the Pattern in the above in the above above COLRITech Spec COLR/Tech Spec Limit COLRJTech Spec Limit Limit Refueling Boron Concentration Administrative Limit
> 2407 ppm
> 2548 ppm
> 2548 ppm (Note I)
Note:
(I) The above table specifies the minimum technical requirements. It is acceptable for NEOP-13 to conservatively list higher ppm values.
Calvert Cliffs 1, Cycle 18 CQLR Page 8 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 8 of 25 Rev. 0
6 5 A 5.
I 0 z3 QI
.14 ACCEPTABLE OPERATION (EOC, 4.5)
REGION (BOC, 3.5)
MINIMUM SHUTDOWN MARGIN UNACCEPTABLE OPERATION REGION I
I 0
BOO ECO BOC
- EOC, TIME IN CYCLE Figure 3.1.1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 18 COLR Page 9 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 9 of 25 Rev. 0
70 60 (1.53, 60) 50 40 978 - 600 Fr1 30 0 20 1
i ALLOWED REGION I
I II 1
1:11(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)
Cal'vert Cliffs 1, Cycle 18 COLR Page 10 of25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 10 of 25 Rev. 0
(1.00 FRTP, Group 5 @ 35% Inserted)
L 0It.
3 LU 0
IL0 z
Ui
/
1.000 0.900 0.800 0.700 0O.90 FR-P, Groul5 5
IJ Insert l
I I
Iser-d
-I-L- {'.
I IK1A,&("rhPTI&nI it 75 FRTF (0.70 F Group ITP, Gn a 0s jp 5 @
inserted
'0% Inse OPE RATI NG ted)
'L___
.j__
=Ef
^
C-0.
o w.
si0 0.
0.Ce h
b (0.6. FRTP.,
roup 5 ( i 85% In erted)
MEt,WUIU 0.5(
0.4(
0.3(
0.2(
0.1(
Ab ZPP uu i ;
I
-,4 jmf_,
_ vg '
6-FRTP Group J (X 50% nserted:
C_..1le Transit Ion Limit I
° (0.20OFTP,Grciup3@
0%Inse ed).
-Abov 1emPo e+/-PDL 6tpin Group 31@0%1rted)i Selpoin il__it__
in.
I917 4
M I V 1 ----
1 0%
20%
40%
60%
135' o10' 81 54U Mu 80%
27r 100%
o0 0%
135' 20%
- 108, 40%
81"
.60%
54.
80%
2r I
100%
0O 0%
135' 20%
108' 40%
81" 60%
54.
2r 100%
0o W
I I
Is l
l1 r
0%
20%
40%
60%
80%
100%
0%
135" 108" 81" 54-27' 0-135' "a.
F I -
I I
20%
40%
60%
80%
108-81-54-27' 100%
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 Calvert Cliffs 1, Cycle 18 COLR Page 11 of25 Rev. C' Calvert Cliffs 1, Cycle 18 COLR Page 1 1 of 25 Rev. Id
17.0 16.5 tL 16.0 us a i
15.5 UW 0
X + 15.0 2
wJ1.
W *F
,, w 14.5 g.i4.3 0
as 14.0 UNACCEPTABLE OPERATION ACCEPTABLE I ___
==____
ACCEPTABLE OPERvAlON=
U 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 18 COLR Page 12of25 Rev. 0 Calvert Cliffs I, Cycle I18 COLR Page 12of 25 Rev. 0
0:
LU U-0z 0
F C,
1.10 -
1.05 1.00 0.95 0.90 0.85 0.80 0.75 0.70 0.65 0.60 0.55 0.50 0.45 0.40 0.:35 0.30 0.25 0.20
-0.60 UNACCEPTABLE OPERATION REGION
(-0.3, 0.70)
(-0.3. 0.50)
/(-OA'
(-0.08, 1.00)P (O
12,1.00)
/
\\
UNAC(
RE ACCEPTABI F CEPTABLE RATION
- GION
? (0.3, 0.70)
OPERATION REGION I
42, 0.20)
(0.3, 0.20) 1
-0.40
-0.20 0.00 0.20 0.40 1.60 PERIPHERAL AXIAL SHAPE INDEX, Yt 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-1 3 for Administrative Limits)
( i Calvert Cliffs 1, Cycle 18 COLR Page 13 of2S Rev. 0 Calvert Cliffs l, Cycle l 8 COLR Page 13 of 25 Rev. 0
I>
1.00 I0 0.90 (1.785, 0.79) 0.80.
A E 0.70 - -
0 o0.60 L.60 ACCEPTABLE VALUE zj 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 Fxy Figure 3.2.1-3 Total Planar Radial Peaking Factor (FxyT) vs.
Scaling Factor (N-Factor)
(See NEOP-13 for Administrative Limits)
Calved Cliffs 1, Cycle 18 COLR Page 14 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 14 of 25 Rev. 0
W LU 0
IL
-J w
W.
z x
I-lLLu IL0z 0
I IL.
W
-j"C 1.60 1.65 1.70 1.75 1.80 T
Figure 3.2.2 1.85 1.90 Total Planar Radial Peaking Factor (FX7T) vs.
Allowable Fraction of Rated Thermal Power While operating with F Tgreater than 1.70, withdraw CEAs to or above the Long Term S"eady State Insertion Limits (Figure 3.1.6)
( v.
Calvei-t Cliffs 1, Cycle 18 COLR Page 15 of25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page IS of 25 Rev. ()
K) 1.05 (1.65, 1.00)
UNACCEPTABLE lu 0.95 OPERATION o
\\
REGION
-0.85 (1.7325,0.80)
Lu 0.75 I-\\
FT LIMIT CURVE wU 0.65
. 0.55 0
° 0.45 ACCEPTABLE OPERATION
.REGION
,v, 0.35 0.25
.\\
0 (1.819,0.20) 4-'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 18 COLR Page 16 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 16 of 25 Rev. 0
-j w
0 a-
?-J 0
~2 IL0z0 1.10 -_
1.05 -.
1.00 -.
0.95-.
0.90 -.
0.85 -
0.80.
0.75 0.70 -
0.65.
0.60.
0.55.
0.50-
-3.45 -.
0.40.
0.35 - -
0.30 -.
(1.25 -.
().20 -1_
-0.60 UNACCEPTABLE
- OPERATION REGION
(-0.3, 0.70)
(-0.3, 0.50).
(-0.08,1.00)
(O 15, 1.00)
UNACCEPTABLE OPERATION
/
\\
REGION-(0.3, 0.80)
ACCEPTABLE OPERATION REGION 0.42, 0.20)
(0.3, 0.20)
I I
-0.40
-0.20
- 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yo 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)
It inj Calvert Cliffs 1, Cycle 18 COLR Page 17 of 25 Rev. 0 Calvert C'liffs 1, Cycle I18 COLR Page 17 of 25 Rev. 0
K) 1.300 1.250 -
1.200 1.150 1.100 1.050.
1.000.
It 0.950 o 0.900 ZS0.850.
0.800.
-I i
0.750 Lu 2
0.700 0us~ 0.750.
Zo 0.600.
0 0.550.
L 0.500 0.450 0.400 0.350 0.300 0.250 0.200 0.150 _
-0.80 U-
-0.60
-0.40
-0.20 0.00 0.20 0.40 PERIPHERAL AXIAL SHAPE INDEX, Yi 0.60 0.80 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 18 COLR Page 18 of25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 18 of 25 Rev. 0
1.60 -
P var 2869.5 x (Ai) x (QRi) + 17.98 x Tin - 10820 1.50 QDNB Ai X QRi
,.40-1.30 ;(-0.6, 1.20 Ai -NA +0.1667:KA I + 1.tl
/
1\\
L (0.6, 1.1 )
1.10 -
p-A1 =0.5 x I+ 1 0 1.00 l 0.90 I
-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 I (ASI vs. A1)
Calvert Cliffs 1, Cycle 18 COLR Page 19 of 25 Rev. 0
PTdP = 2869.5 x (A1) x (QR1) + 17.98 x T1n - 10820 QDNB
=Al x QRI 1.2 7
(1.2,1.2) 1.1 -
QR= (RTP) + 0.0 1.0-0.9 -
0.8 06w08w
=_
QR, = 0.375 x (RTP) + 0.625 XQR= 0.9 167 x (RTP) + 0.3 0.3 0 (0.I, 0.3 )
_ _ _Il 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 (RTP)
Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QRl)
K2 Calvert Cliffs 1, Cycle 18 COLR Page 20 of 25 Rev. 0 Calvert Cliffs 1, Cycle 18 COLR Page 20 of 25 Rev. 0
LIST OF APPROVED METHODOLOGIES (1)
CENPD-1 99-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 I.,"
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-l 91(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-19 l(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)
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(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 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 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-IT, 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,
"'3valuation 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, 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)
Latter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27, 1977, "1Evaluation of Topical Reports CENPD-1 33, 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, I 985, "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. Luindvall, Jr. (B &E) to' Mr. ". A. ClarrC(NRC), dated September 22, 1980, "AmendIment 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) to6Mr. 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. Tieman (BG&E), dated July 7, 1987, Dccket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)
(Support for Specification 3.1.4)
(40)
CE;NPD-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 I, Cycle 18 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:
- 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 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-I99-P, Supplement 2-P-A, Appcndix A, Latest Approved Revision, "CE Setpoint 7'4Iethodology," June 1998.
(45)
CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLO' Cladding Material in CE Nuclear Power Fuel Assembly Designs".
(46)
CHNPD-132, Supplement 4-P-A, Latest Approved Revision, "Calculative Methods for til' 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.
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. I (51)
WCAP-1 6045-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.
KY,
(
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