ML041170185

Core Operating Limits Report for Unit 1, Cycle 17, Revision 0

ML041170185
Person / Time
Site:	Calvert Cliffs
Issue date:	04/21/2004
From:	Vanderheyden G Constellation Energy Group, Constellation Generation Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041170185 (26)

Text

4 - I George Vz.derheyden 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 Energy Group April 21, 2004 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-317 Core Operating Limits Report for Unit 1, Cycle 17, Revision 0 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 1, Cycle 17, Revision 0 (Attachment 1) is provided for your records.

Please replace the Unit I 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 truly yo rs, GV/CAN/bjd

Attachment:

(1) Core Operating Limits Report for Unit 1, Cycle 17, Revision 0 cc: (Without Attachment)

J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate 1-1, NRC R. 1. McLean, DNR G. S. Vissing, NRC 3 bo (

ATTACHMENT (1)

CORE OPERATING LIMITS REPORT UNIT 1, CYCLE 17, REVISION 0 Calvert Cliffs Nuclear Power Plant, Inc.

April 21, 2004

i CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT for UNIT 1,.CYCLE 17 REVISION 0 Kent A.L. WOo . a ' ~7 RESPONSIBtEINE/ IDATE J. Houston Pennv// '* /

INDEPENDE i REVIEWE DA Philp . WenCloski A "I PRINCIPAL ENGINEfER - FOSU"/ DATE Rev. 0 17 COLR Page 1 of 24 1, Cycle Cliffs 1, Calvert Cliffs Cycle 17 COLR Page I of 24 Rev. 0

4.

CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 1, CYCLE 17 The following limits are included in this Core Operating Limits Report:

Specification Title Pane 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 (F1 yT) .............................. 7 3.2.3 Total Integrated Radial Peaking Factor (FJT) .............................. 7 3.2.5 Axial Shape Index (ASI) ... 7..........................7 3.3.1 Reactor Protective System (RPS) Instrumentation - Operating .............................. ;.7 3.9.1 Boron Concentration .............................. 8 5.6.5 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 Qycle"... . 9 Figure 3.1.4 Allowable Time To Realign"CtA 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 Figure 3.2.1-3 Total Planar Radial Peaking Factor (Fy ) vs.

Scaling Factor (N-Factor) .14 Figure 3.2.2 Total Planar Radial Peaking Factor (FyT) vs. Allowable Fraction of Rated Thermal Power .15 T

Figure 3.2.3 Total Integrated Radial Peaking Factor (Fr ) vs.

Allowable Fraction of Rated Thermal Power .16 Figure 3.2.5 DNB Axial Flux Offset Control Limits ......... .......................... 17 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power .18 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1.19 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 ................................... 20 Rev. 0 COLR Page 2 of 24 Cycle 17 1, Cycle Calvert Cliffs 1, 17 COLR Page 2 of 24 Rev. 0

UNIT I 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 I- ---- -- --- i - - -- - - - 1 22 0 23 j _0 24 1 0 Calvert Cliffs 1, Cycle 17 COLR Page 3 of 24 Rev. 0

INTRODUCTION This report provides the cycle-specific core operating limits for operation of Calvert Cliffs Unit 1, Cycle 17. It contains the limits for:

Shutdown Margin (SDM)

Moderator Temperature Coefficient (MTC)

Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear Heat Rate (LHR)

Total Planar Radial Peaking Factor (F, T)

Total Integrated Radial Peaking Factor (FrT)

Axial Shape Index (ASI)

Reactor Protective System (RPS) Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which provides 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 the Technical Specifications. The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologles" secdoh of this report and the Technical Specifications. Ao. A COLR Revision 0 COLR Revision 0 is the initial issue for Unit 1 Cycle 17, ..it is limited to

.0 operation

• ao in Modes 5 and in Moe and 6.

Rev. 0 Page 4 of 24 Calvert Cycle 17 Cliffs I,1, Cycle Calvert Cliffs COLR 17 COLR P'age 4 of 24 Rev. 0

DEFINITIONS Axial Shape Index (ASI)

ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core.

ASI lower - upper = YE lower + upper The Axial Shape Index (Y) 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 - FyT

.:The Total Planar Radial Peaking Factorfis 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 1,Cycle Cliffs 1, 17 COLR Cycle 17 COLR Page 5 of 24 Rev. 0

CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 17 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)

Tavg > 200 TF- Modes 3 and 4:

Not applicable in Modes 5 and 6.

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)

Not applicable in Modes 5 and 6.

3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1)

Not applicable in Modes 5 and 6.

3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR 3.1.6.1 and SR 3.1.6.2)

Not applicable in Modes 5 and 6.

3.2.1 Linear Heat Rate (LIIR) (SR 3.2.1.2 and SR 3.2;1.4)

Not applicable in Modes 5 and 6.

Rev. 0 Page 6 of 24 Calvert Cliffs Calvert 1,Cycle Cliffs 1, 17 COLR Cycle 17 C OLR Page 6 of 24 Rev. 0

CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 17 3.2.2 Total Planar Radial Peaking Factor (FIiT) (SR 3.2.1.1 and SR 3.2.2.1)

Not applicable in Modes 5 and 6.

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

Not applicable in Modes 5 and 6.

3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1)

Not applicable in Modes 5 and 6.

3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Reactor Trip Setpoints) (IS Table 3.3.1-1)

Not applicable in Modes 5 and 6.

Calvert Cliffs 1, Cycle 17 COLR Page 7 of 24 Rev. 0

3.9.1 Boron Concentration (SR 3.9.1.1)

The refueling boron concentration will maintain the Keffat 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 height restrictions: <12 inches No restriction COLR/Tech Spec Limit 2264 ppm 2556 ppm Chemistry Sampling 23 ppm 26 ppm Boron-10 Depletion 47 ppm 53 ppm Refueling Boron Concentration Limit including Chemistry Sampling > 2334 ppm > 2635 ppm uncertainty and Boron-10 Depletion Dilution of the Refueling Pool between Low and High Level Alarms with 73 ppm 2 Refueling Pool Flooded  ;

Any number of Temporary Rotations of (an allowance of 20 ppm is (an allowance of 20 ppm is Fuel Assemblies already included in the above already included in the above COLR/TS limit) COLR/RS limit)

UlC17 In-Core Shuffle Allowance (an allowance of 50 ppm is Not required post-refueling.

already included in the above COLR/TS limit)

Refueling Boron Concentration > 2407 ppm > 2717 ppm Administrative Limit CLR Clffs1, Calvd age of24 Ccle17 Rv.

Calvert Cliffs 1, Cycle 17 COLR Page 8 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.1.1 Shutdown Margin vs. Time in Cycle Rev. 0 1, Cycle 17 COLR Page 9 of 24 Calvert Cliffs 1, Cycle 17 COLR - Page 9 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.1.4 Allowable Time to Realign CEA Versus*

Initial Total Integrated Radial Peaking Factor (FrT)

Rev. 0 1,Cycle COLR 17 COLR Page 10 of 24 Calvert Cliffs 1, Cycle 17 Page 10 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Calvrt COR lifs 1 1 of4 1 Cyce Pge Rv.

Calvert Cliffs 1, Cycle 17 COLR Page 11 of 24 Rev. O

Not Applicable in Modes 5 and 6 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Rev. 0 1, Cycle COLR 17 COLR Page 12 of 24 Cliffs 1, Calvert Cliffs Cycle 17 Page 12 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits (LCO Limits are not needed below 20% thermal power)

(See NEOP-13 for Administrative Limits)

Rev. 0 Page 13 of 24 Cliffs 1, Calvert Cliffs 1, Cycle 17 COLR Cycle 17 COLR Page 13 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.2.1-3 Total Planar Radial Peaking Factor (F,,yT) vs.

Scaling Factor (N-Factor)

(See NEOP-13 for Administrative Limits)

Pae 1 of 4 Rv..

1,Cyce Calvrt lifs1 COL Calvert Cliffs 1, Cycle 17 COLR Page 14 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.2.2 Total Planar Radial Peaking Factor (FyT) vs.

Allowable Fraction of Rated Thermal Power COL lifs 1,Cyce 1Pae 1 of 4 Rv.

Calvrt Calvert Cliffs 1, Cycle 17 COLR Page 15 of 24 Rev. O

Not Applicable in Modes 5 and 6 Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT).VS.

Allowable Fraction of Rated Thermal Power Rev. 0 Page 16 of 24 Calvert Cliffs 1, Cycle Cliffs 1, 17 COLR Cycle 17 COLR Page 16 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.2.5 DNB Axial Flux Offset Control Limits (See NEOP-13forAdministrative Limits)

Page 17of24 Rev. 0 1, Cycle Calvert Cliffs 1, COLR 17 COLR Cycle 17 Page 17 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Rev. 0 COLR Page 18 of 24 Calvert Cliffs Cycle 17 1, Cycle Cliffs 1, 17 C0LR Page 18 of 24 Rev. 0

Not Applicable in Modes 5 and 6 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part I (ASI vs. Al)

Page 19 of 24 Rev. 0 Calvert Cliffs 1, Cycle Cliffs 1, 17 COLR Cycle 17 COLR Page 19 of 24 Rev. 0

• Not Applicable in Modes 5 and 6 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power-vs. QR1 )

Calvert Cliffs 1, Cycle 17 COLR Page 20 of 24 .Rev. 0

LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev l-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 IU,"

December 1979 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.2, 3.2.3)

(3) CEN-124(B)-P, "Statistical Combination ofUncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"

January 1980 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5)

(4) CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.2.5)

(5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5) .

(6) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit 1 Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)]

(7) CEN-348(B)-P, "Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 3.3.1, 3.1.6, 3.2.3, 3.2.5)

(8) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-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)

Calvert Cliffs 1, Cycle 17 COLR Page 21 -of24 Rev. 0

(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)

(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, DocketNos. 50-317 and 50-318, "SafetyEvaluation of Topical Report CEN-161-(B)-P, Supplement I-P, Improvements to Fuel Evaluation Model" (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 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-1 33, Supplement 5, "CEFLASH-4A, a FORTRAN77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2)

(25) CENPD-134, Supplement 2, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1, 3.2.2)

(26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31, 1986, "Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2)

(27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1, 3.2.2)

Calvert Cliffs 1, Cycle 17 COLR Page 22 of 24 Rev. 0

(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6, 1978, "Evaluation of Topical Report CENPD-135, Supplement 5" (29) CENPD-137, Supplement 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-137, Supplement 1-P" (32) CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1, 3.2.2)

(33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10, 1978. "Evaluation of Topical Report CENPD-138, Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for.

Specifications 3.1.1 and 3.1.3 and 3.1.6)

(35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, "Safety Evaluation Report Approving Unit 1 Cycle 8 License Application" (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, "Amendment to Operating License No. 50-317, Fifth Cycle License Application" (Section 7.1.2 contains Methodology for Specifications 3.1.1, 3.9.1)

(37) Letter from Mr. R. A. Clark (NRC) to Mr.A. E. Lundvall, Jr. (BG&E), dated December 12, 1980, "Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 &

50-318, Request for Amendment" (Methodology for Specifications 3.1.4)

(39) Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7, 1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2) (Support for Specification 3.1.4)

(40) CENPD-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)

(41) The power distribution monitoring system referenced in various specifications and the BASES, is described in the following documents:

Calvert Cliffs 1, Cycle 17 COLR Page 23 of 24 Rev. 0

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 ZIRLOT mCladding 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" Rev. 0 Page 24 of 24 Calvert Cliffs 1, Cycle Cliffs 1, 17 COLR Cycle 17 COLR Page 24 of 24 Rev. 0