ML080100119

Core Operating Limits Report for Unit 1. Cycle 18, Revision 4

ML080100119
Person / Time
Site:	Calvert Cliffs
Issue date:	01/08/2008
From:	Flaherty M Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML080100119 (27)

Text

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 0Constellation Energy~

Nuclear Generation Group January 8, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-3 17 Core Operating Limits Report for Unit 1. Cycle 18. Revision 4 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 1, Cycle 18, Revision 4 is provided for your records.

Please replace the report (Attachment 1) in its entirety.

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

Attachment:

(1) Core Operating Limits Report for Unit 1, Cycle 18, Revision 4 cc: Resident Inspector, NRC (Without Attachment)

D. V. Pickett, NRC S. J. Collins, NRC R. 1. McLean, DNR

ATTACHMENT (1)

CORE OPERATING LIMITS REPORT FOR UNIT 1, CYCLE 18, REVISION 4 Calvert Cliffs Nuclear Power Plant, Inc.

January 8, 2008

• Constellation Energy~

Calvert ClIffs. Nuclear Power Plant, Inc.

Core Operating Limits: Report Unt. 1 Cycl e 018 Revisioni 4-lj Effective Pale: J)2/'3 IRESPONSIBLE ENGINEE D ATE" INDEPENDENT REVIEWER I I(AE ENGINEERING SUPERVISOR - PWR CORE ANALYSIS I-DATE Rev.4 Page I of 25 lCalventliffi, I, qyclc CaIv~rt Cliffs 1, 18 COLR Cyclc 18 COLR agic 1:0f25 Rev.: 4 1

CORE OPERATING LIMITS REPORT CAL VERT CLIFFS UNIT 1, CYCLE 18 The following limits are included in this Core Operating Limits Report:

Specification Title Page Introduction.................................................................................. 4 Definitions ................................................................................... 5

~K3.1. 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 (F, ) ................................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 ............................................... I........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 Fig ure 3.2.1-3 Total Planar Radial Peaking Factor (F,,y ).vs.

Scaling Factor (N-Factor)................................................................ 14 Figure 3.2.2 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 Rev.4 1, Cycle 18 COLR Page 2 of 25 Calvert Cliffs

-Calvert Cliffs 1, Cycle 18 COLR Page 2 of 25 Rev. 4 1

UNIT 1 CORE OPERATING LIMITS REPORT LIST.OF EFFECTIVE PAGES Page No. Rev. No.

1 4 2 4 3 4 4 4 5 __

.6 4 7 4 8 4.

__9 4 I_11 4 12 4 13 4'__

14 4 15 4

___16 4

____17 4

___18 4 19 4 20 4 21 4 22 4 23 4 24 4 25 ~ 4 Calvert Cliffs 1, Cycle 18 COLR Pg 3 off225 Page e. 4 Rev. 1

INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 18. 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)T 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 1 Cycle 18 (U1IC 18) COLR per Safety Evaluation SE00497 Rev. 0. U1IC 18 is only allowed to operate in Mode 6 or in a defueled condition. Although UlICl18 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 of UIC18 in plant modes 5, 6, or defueled per SE00497 Rev. 1. Although U 1C 18 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 operation ofU ICl18 in all plant modes per SE00497 Rev. 2.

COLR Revision 3 Revised Figure 3.2.1-3 (N-Factor) as part of the corrective action for IRE-017-571.

COLR Revision 4 Revised the Refueling Boron Concentration requirements to support the end-of-cycle core shuffle (2008 RFO).

The revised minimum refuieling boron concentration continues to be significantly larger than that required by 10 CFR 50.59 Safety Evaluation SE00497 Revision 3.

Rev.4 Page 4 of 25 Calvert Calvert Cliffs Cycle 18 1,Cycle Cliffs 1, 18 COLR COLR Page 4 of 25 Rev.4 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 = 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.

Y1=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 - Fy 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.

Rev.4 Page 5 of 25 Calvert 1, Cycle Cliffs 1, Calvert Cliffs 18 COLR Cycle 18 COLR Page 5 of 25 Rev. 4 1

CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 18 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~ApPF0 at rated thermal power.

3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.11.1)

.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 (Fr Ty,~ If COLR Figure 3.1.4 is used, the pre-misaligned F, value used to determine the allowable time to realign the GEA 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.4 Cycle 18 COLR Page 6 of 25 Cliffs 1, Calvert Cliffs 1, Cycle 18 COLR Page 6 of 25 Rev. 4 1

CYCLE SPECIFIC LIMITS FOR UNIT 1, 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 thermnal 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 ofFxyT shall be limited to < 1.70.

The allowable combination of thermal power, CEA position, and F,,YT are shown on COLR Figure 3.2.2.

3.2.3 Total Integrated Radial Peaking Factor (rT ) (SR 3.2.3.1)

The calculated value of Fr Tshall. be limited to < 1.65.

The allowable combinations of thermal power, CEA position, and Fr 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 (TMILP) 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.4 Cycle 18 1, Cycle COLR Page 7 of 25 Calvert Cliffs 1, 18 COLR Page 7 of 25 Rev. 4 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 'F.

Refueling Boron Concentration Limits Post-Refueling UGS or No restriction RV Head lift height restrictions.

COLRFTech Spec Limit 2396 ppm

-Chemistry Sampling 24 ppm

-Boron- 10 Depietion 50 ppm Refueling Boron Concentration

> 2470 ppm Limit including Chemistry Sampling uncertainty and Boron- 10 Depletion Dilution of the Refueling Pool between Low and 78 ppm High Level Alarms with

-Refuieling Pool Flooded Any number of Temporary An allowance of 20 ppm is already Rotations of Fuel included in the above COLRITech Assemblies Spec Limit An allowance of 50 ppm is already U1CIC 8 Allowance for included in the above COLR/Tech

-Holes in the Pattern Spec Limit Additional conservatism to support the end-of-cycle incore shuffle (2008 72 ppm RFO) prior to bringing in fresh Batch I1Z fuel. _______________

Refueling Boron Concentration Administrative Limit >2620 ppm (Note 1) ________________

Note:

(1) The above table specifies the minimum technical requirements. It is acceptable for NEOP- 13 to conservatively list higher ppm values.

Rev.4 Page 8 of 25 Calvert Cliffs 1, Cycle 18 1, Cycle 18 COLR COLR Page 8 of 25 Rev. 4 1

Figure 3.1.1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 18 COLR Page 9 of 25 Rev. 41

70.

60 (1.53, 60).

-. 50 z

~40 978 -600FW z 30 W

020 10 ALLOWED REGION 0 1I I I I I(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 (Fr T Rev.4 Page 10 of25 Calvert 1, Cycle Cliffs 1, Calve~C1iffs 18 COLR Cycle 18 COLR Page 10 of 25 Rev. 4 1

(1.00 FRTP, Group 5 @35% Inserted) 1.000 11 1 0.90 FRIPGrouj 5@35% Ifserte J) 0.900 ________ ________ 4.

I--

-10 90*

0.800 (L0.75 FRTP, Group 5@ 50%lInserted) -- r- !AC-(:E-P-T 4SLE OPE RATI \IG 2j~*. KkP (01 I rcup 5 @ 60% Insitled) 0 a.

u.tuU o.:

ow.

~t.

FRTP, ( roup 5 85% Inm erted) IMMUIUN, c2~

0.600 C

iP2~~~71

ý(01 (0.56 FRTPI Group 4@ 50% Inserted) 5 _ 4

.i 1 0.500 Ch_ _I _ _

0.400 0

w 0.300 _____ ~ ____.~ ___ Transient Inselion Lirnýt{

0

____ ___ co O ___ .(0.20_F TP_ Grd up 3 @6V U0% Insered)I 0 0.200 0- J__ I __-___

- ~ ___i __

0.100 Above L(Above Zero POter PDIL jSetpoint,1 Group 31@ 60% (nserted)

Setpoint REGLATNGGROP REGLATNGGROP REGULAINGGOP-I I 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100% 20% 40% 60% 80% 100%

135" 108", 81", 54A" 27" 0"1 135" 108" Bi1l 54" 27, 01, 135" 108" 81" 5,A" 27" 0" I REULATNG GOU-S = RGULTIN GRUP -

1 1 I I I I 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80% 100%

1-35ý 108" 81" 54" 27" 0" 135" 108" 81" 54A" 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.4 Page 11 of25 Calvert Cliffs 1, Cycle 18 1, Cycle 18 COLR COLR Page I I of 25 Rev. 4

17.0 16.5 U-LL 16.0 F-15.5 WW UJ + 15.0 UNACCEPTABLE OPERATION W wU14.5 02 !::,14.3 0

-j 14.0 ACCEPTABLE OPERATION 13.5 13.0 BOG EOC TIME IN CYCLE Figure 3.2.1 -1 Allowable Peak Linear Heat Rate vs. Time in Cycle Rev.4 Cycle 18 1,Cycle COLR Page 12 of25 Cliffs 1, Calvert Cliffs 18 COLR Page 12 of 25 Rev. 4 1

1.10-1.05-1.00- (-0.08, 1.00)(01,.0 0.95--UACPAL UNACCEPTABLE 0.90- OPERATION OPREGION EGO 0.85-- REGIONR 0.80-0 0.75-0:

0.70- (-0.3, 0.70) ACCEPTABLE (0.3, 0.70)

LI 0.65--OPERATION 065 REGION 0 0.60-z 0 0.55-P:

L), 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-

-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-1 3 for Administrative Limits)

Rev.4 Page 13 of2S 1,Cycle Calvert Cliffs 1, 18 COLR Cycle 18 COLR Page 13 of 25 Rev. 4 1

1.00 0.90-0 S0.80-U-

0.70-0 I--

o0.60-U-

0 ACCEPTABLE VALUE z

i0.50-0.40-0.307 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 FT Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fy~T) VS.

Scaling Factor (N-Factor)

(See NEOP-1 3 for Administrative Limits)

Calvert. Cliffs 1, Cycle 18 COLR Pg Page 144o2 of 25 e. 4 Rev. 1

1.05 W0.95- (1.70, 1.00) utREGIO 1N a-0.85-

~ 0.75(1.785, 0.8) z FXY' LIMIT CURVE C' 0.65-u-. 0.55 0

z 0

i-0.45-Uj 0.35- ACCEPTABLE

-i - OPERATION ca REGION S0.25 3 ~(1.874, 0.20) 0.15-0.05 1.60 1.65 1.70 1.75 1.80 1.85 1.90 FT Figure 3.2.2 Total Planar Radial Peaking Factor (F,YT) 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.4 Page 15 of25 Calvert Cliffs 1, 1, Cycle 18 COLR Cycle 18 COLR Page 15 of 25 Rev. 4

1.05 WU UNMAU1-V I IAbLt 3:0.95 OPERATION 0 REGION C-

-i0.85-n (1.7325, 0.80)

LU 0.75-wU0.65-LL 0.55-0 z

00.45- ACCEPTABLE OPERATION 0.35 REGION LU S0.25-S0.15;.

0.05 1.60 1.65 1.70 1.75 1.80 1.85 Fr T Figure 3.2.3 Total Integrated Radial Peaking Factor (Fr T) VS.

Allowable Fraction of Rated Thermal Power While operating with FrTgreater than 1.65, withdraw CEAs to or above the Long Term Steady State Insertion Limits (Figure 3.1.6)

Calvert Cliffs 1, Cycle 18 COLRPae1o2Rv4 Page 16 of 25 Rev. 4 1

1.10 1.05 1.00

> 0.95 w

0.90 w

3' 0.85 0

a- 0.80 w0.75 0 0.70

-I0.65 0.60 S0.55 M 0.50 U-0 0.45 0.3 U.

0.30 0.25 0.20

-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.4 Cycle 18 COLR Page 17of25 Cliffs 1, Calvert Cliffs 1, Cycle 18 COLR Page 17 of 25 Rev. 4 1

1.300-1.250 1.200 1.150 1.100 1.050 1.000 W 0.950 0 0.900

-j 0.850 0.800 0.750 I-0.700 0

0.650 z 0.600 0

0.550 C-,

0.500 0.450 0.400 0.350 0.300 0.250 0.20 0.10500

-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 18 COLR Pg 188o2 Page of 25 e. 4 Rev. 1

1.60 1.50 Q:= AixQR1 1.40 1.30 (-0.6, 1.3) 1.20__ _ _ _

Al +0.1667xASI+1.ý 1.10 _ __ _ _ _ _ _

Ai= -0.5x/ SI +1 0 1.00 _ _ _ _ _ _ _ _ _ _

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. Al)

Rev.4 Cycle 18 1,Cycle COLR Page 19 of25 Cliffs 1, Calvert Cliffs 18 COLR Page 19 of 25 Rev. 4

T =269.5 x(Al) x(QR1) +17.98 xTi,- 10820 va QD)NB =Al xQR1 1.2 (1.2, 1.2) 1.1.

1.0 0,9 0,8 0.7

~0,6 CY 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. QRI)

Rev.4 Page 20 of 25 Calvert Cliffs 1, Cycle Cliffs 1, 18 COLR Cycle 18 COLR Page 20 of 25 Rev. 4 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.

Addition ally, 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 f 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- 19 1(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 1 Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN- 19 1(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) CEKPD-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 18 COLR Pg 211o2 Page of 25 e. 4 Rev. 1

(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, 3.2.31- 3.2.5)

(16) CENPD-3 82-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- 16 1-(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 I1-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-16 1(B), Supplement I1-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, 198 1, LD-81-095, Enclosure I1-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-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- 13 5, Supplement 5" (29) CENPD-137, Supplement '1-P, "Calculative Methods for the C-B 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. B. 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. B. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD-138, Supplement 2-P" (34) Letter from Mr. A. B. 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 con~tains 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. B. 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. B. 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&B) 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&B), dated July 7, 1987, Docket Nos. 50-3 17 and 50-3 18, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)

(Support for Specification 3.1.4)

(40) CBNPD-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:

1. CENPD-153-P, Revisiion 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- 11596-P-A, "Qualification of thePHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.

(49) WCAP-1I0965-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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(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.

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